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Sample records for dinamika yadernogo reaktora

  1. Indium-Gallium Radiation Contour of the IRT Nuclear Reactor; Circuit d'activation d'indium-gallium dans le reacteur nucleaire IRT; Indij-gallievyj radiatsionnyj kontur yadernogo reaktora IRT; Circuito de radiaciones de indio-galio del reactor IRT

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    Breger, A K; Ryabukin, Y S; Tulkes, S G; Volkov, E N

    1960-07-15

    -industrielles. (author) [Spanish] Basandose en un trabajo teorico ya publicado, se preparo en el reactor IRT un circuito de radiaciones de indio-galio que constituye una nueva fuente de rayos gamma de elevada intensidad. El primer circuito de este tipo ''RK-1'' se construyo para el reactor IRT en el Instituto de Fisica de la Academia de Ciencias de la Republica Socialista Sovietica de Georgia. Este trabajo estudia los puntos siguientes: calculo de la activacion de la desintegracion del conjunto indio-galio; estructura del circuito RK-1 y su disposicion en el tanque del reactor y en la camara activa; dispositivo de admision de las sustancias liquidas y gaseosas en la zona de la irradiacion; transportador de las sustancias solidas sometidas a irradiacion. En el reactor IRT, cuya potencia es de 2 000 kW, la intensidad de irradiacion del circuito es igual a la de una fuente de radiacion gamma equivalente a 20 000 g de radio. En el trabajo se estudian las posibilidades de utilizacion de este circuito con fines semi-industriales y de investigacion. (author) [Russian] Osnovyvayas' na uzhe opublikovannoj teoreticheskoj rabote, byl podgotovlen indij-gallievyj radiatsionnyj kontur yadernogo reaktora IRT, kotoryj yavlyaetsya novym moshchnym istochnikom gamma-oblucheniya . Pervyj kontur ehtogo tipa RK-1 byl podgotovlen na reaktore IRT v Institute fiziki Akademii nauk Gruzinskoj SSR. V doklade dayutsya raschety aktivizatsij dlya indij-gallievogo splava, strukturnye kompanovki RK-1 i ikh raspolozhenie v bake reaktora i goryachej kamere, ustrojstvo podachi zhidkikh i gazoobraznykh veshchestv v zonu oblucheniya i konvejer dlya tverdykh veshchestv, kotorye podlezhat oblucheniyu. V reaktore IRT moshchnost'yu 2000 kW moshchnost' oblucheniya kontura ehkvivalentna moshchnosti oblucheniya gamma-izluchatelya, obladayushchego aktivnost'yu v 20000 g ehkv. radiya. V doklade obsuzhdayutsya perspektivy ispol'zovaniya indij-gallievogo radiatsionnogo kontura dlya issledovatel'skikh i polupromyshlennykh tselej

  2. DINAMIKA MASYARAKAT LOKAL DI PERBATASAN

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    Zaenuddin Hudi Prasojo

    2012-12-01

    Masyarakat perbatasan yang ada di Indonesia cenderung masuk dalam kelompok masyarakat yang tertinggal dari berbagai aspek pembangunan. Kajian mengenai masyarakat lokal di wilayah-wilayah perbatasan di Indonesia belum terlalu meng­gembirakan baik dari segi jumlah maupun dari segi dampak hasil kajian yang berupa aksi kebijakan pasca kajian. Nanga Badau yang terletak di daerah per­batasan Kalimantan Barat (Indonesia dan Serawak (Malaysia merupakan salah satu wilayah perbatasan yang tertinggal. Tulisan ini memoret isu-isu dinamika dan eksistensi tradisi lokal dalam kerangka globalisasi. Tampak bahwa sikap ramah dan menghormati pendatang merupakan salah satu bentuk nyata bahwa mereka sangat terbuka dengan adanya arus global dan lokal. Mereka juga me­miliki kesadaran diri akan posisi mereka sebagai bagian dari penduduk dunia. Adanya ruang interaksi bagi dunia luar, seperti mudahnya akses keluar masuk ke negara lain mengakibatkan pola interaksi, informasi dan komunikasi etnis Iban menjadi berkembang. Hal tersebut dapat dilihat pada aktivitas masyarakat Iban sehari-hari yang telah memanfaatkan dan menggunakan perangkat handphone, televisi dan teknologi modern lainnya.

  3. Dinamika Teater Modern Di Bandung 1958 - 2002

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    Tatang Abdulah

    2015-09-01

    Full Text Available Penelitian ini mengkaji dinamika perkembangan teater modern di Bandung dari tahun 1958 sampai dengan 2002. Objek Sampel penelitian ini adalah ‘Studiklub Teater Bandung’ (STB. Penelitian ini dilakukan dengan pendekatan sejarah dengan tujuan untuk mengetahui metode dan ideology karya-karya Suyatna Anirun.  Dari penelusuran melalui dokumen dan wawancara dengan berbagai pihak akhirnya ditemukan kesimpulan bahwa STB di bawah penyutradaraan Suyatna Anirun selalu bertitik tolak dari naskah Barat yang dianggap berat. Untuk mengakrabkan antara tontonan dengan penonton, naskah sebagai titik tolak garapan seringkali disadur terlebih dulu. Setiap pertunjukan STB selalu menonjolkan posisi actor, artinya deol slalu menjadi titik pusat petunjukan. Dalam pengelompokan gaya, STB dianggap sebagai salah satu kelompok teater yang konsisten membawakan gaya teater realis. Pola metode dan deology berkarya Suyatna Anirun sangat mempengaruhi kelompok-kelompok teater modern lainnya yang tumbuh dan berkembang di kota Bandung. Kata kunci: Metode,  Penyutradaraan, Pertunjukan Teater.

  4. Regulations for RA reactor operation; Propisi nuklearnog reaktora 'RA'

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    NONE

    1980-09-15

    Regulations for RA reactor operation are written in accordance with the legal regulations defined by the Law about radiation protection and related legal acts, as well as technical standards according to the IAEA recommendations. The contents of this book include: fundamental data about the reactor; legal regulations for reactor operation; organizational scheme for reactor operation; general and detailed instructions for operation, behaviour in the reactor building, performing experiments; operating rules for operation under steady state and accidental conditions. [Serbo-Croat] Propisi o radu nuklearnog reaktora RA pisani su tako da svi zakonski propisi definisani 'Zakonom o zastiti od jonizujuceg zracenja' i pratecim propisima (devet pravilnika) kao i tehnicke norme prema preporukama MAAE budu postovani u punoj meri pri radu reaktora. Sadrzaj ove knjige obuhvata: osnovne podatke o reaktoru; zakonske propise; organizaciju rada reaktora RA; opste propise o rezimu rada, kretanju u zgradi reaktora, izvodjenju eksperimenata; pogonske propise za rad u normalnom rezimu i u slucaju udesa.

  5. Corak Etnik dan Dinamika Batik Pekalongan

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    Irfa'ina Rohana Salma

    2016-04-01

    Full Text Available ABSTRAKBatik Pekalongan mempunyai ciri khas atau karakter yang berbeda dengan batik dari daerah pesisir lainnya. Corak yang berbeda ini karena adanya pengaruh budaya dari etnis-etnis pembuat batik yang berdomisili di Pekalongan, yaitu etnis Jawa, etnis Cina dan etnis Belanda. Tulisan ini bertujuan untuk melakukan tinjauan dan mengkritisi lebih dalam ciri khas atau karakter corak dari batik yang dihasilkan para pembatik dari etnis yang berbeda di Pekalongan. Metode pendekatan yang dipakai yaitu studi kepustakaan dan eksplorasi di lapangan. Beberapa sampel motif dari ketiga etnis pembatik dianalisis untuk mengetahui keunikan dan kekhasannya masing-masing, serta dengan tinjauan aspek-aspek lain yang melingkupi dinamika industri batik di Pekalongan. Hasilnya menunjukkan bahwa latar belakang budaya yang berbeda menghasilkan corak batik baru yang kemudian menjadi ciri khas batik Pekalongan secara umum. Ada tiga corak batik Pekalongan yaitu: Batik Pekalongan bergaya Jawa, Batik Pekalongan bergaya Cina, dan Batik Pekalongan bergaya Belanda, yang mempunyai keunikan sendiri-sendiri yang membedakan corak batik di antara mereka. Kajian ini dapat menjadi inspirasi pembinaan seni dan industri kreatif di daerah lain yang multietnis.Kata-kata kunci: batik, corak, etnisABSTRACTPekalongan batik has a specific or a different characteristic from other batik of coastal areas. Thestyle is differently from other because of the cultural influences of ethnic batik maker who lives in Pekalongan, namely Javanese, Chinese and Dutch. This paper aims to conduct a review and criticize the deeper characteristics or specific pattern of the Pekalongan batik results from the different ethnics. Approximation method used is library research and exploration in the field. Several samples of the three ethnic batik motifs were analyzed to determine the uniqueness and each characteristic, as well as the review of other aspects surrounding the dynamics of the industry in Pekalongan batik

  6. Dinamika Gerakan Pembentukan Daerah Otonom Baru Kabupaten Mandau-Riau

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    Muhammad Ashsubli

    2016-04-01

    Full Text Available The purpose of this study was to identify and analyze the dynamics of the movement forming a new autonomous region in the district of Mandau. The method used in this research is qualitative descriptive analysis. Sources of data in this study are primary data the authors obtained from interviews with informants and secondary data obtained from the nature of the documents, archives, and other results are available. The results found that the dynamics of the social movements of tangible movement collectivity of people in it to carry or resist change. All that could happen due to the nature of the people themselves who want change it is marked on the organizing societies Mandau and Pinggir were struggling collectively to realize combustion Mandau regency or Duri City. Tujuan dari penelitian ini adalah untuk mengetahui dan menganalisa dinamika gerakan pembentukan daerah otonomi baru di Kabupaten Mandau. Metode yang digunakan pada penelitian ini adalah Analisis Deskriptif Kualitatif. Sumber data dalam penelitian ini adalah data primer yang penulis peroleh dari hasil wawancara dengan informan serta data sekunder yang didapat dari dokumen-dokemen, arsip-arsip, dan hasil lain yang tersedia. Hasil penelitian menemukan adanya dinamika gerakan sosial yang berwujud gerakan kolektifitas orang-orang di dalamnya untuk membawa atau menentang perubahan. Semua itu bisa terjadi disebabkan sifat masyarakat itu sendiri yang menginginkan perubahan hal ini ditandai dari pengorganisasian masyarakat-masyarakat Mandau dan Pinggir yang berjuang secara kolektif untuk mewujudkan pemekaran daerah Kabupaten Mandau atau Kota Duri.

  7. Dinamika Budaya Material pada Desain Furnitur Kayu di Indonesia

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    Arianti Ayu Puspita Ayu Puspita

    2016-09-01

    ABSTRAK   Perubahan kondisi ekonomi hingga abad ke-21, dan meningkatnya kebutuhan furnitur baik dari luar maupun dalam negeri, kemudian perkembangan ilmu desain di Indone sia, secara tidak langsung berhubungan de ngan permasalahan ekologi. Ketersediaan sumber daya alam seperti kayu, semakin berkurang sehingga mendorong industri furnitur di Indonesia untuk menggunakan alternatif berbagai macam kayu solid, kayu olahan hingga kayu limbah. Dari waktu ke waktu, perubahan kondisi sosial, ekonomi, dan gaya hidup, turut berperan pada kemunculan bentuk-bentuk furnitur baru di Indonesia. Pada penelitian ini, transformasi   kebutuhan material kayu pada furnitur akan dikaitkan dengan dinamika sosial budaya yang terjadi dari abad ke-18 hingga abad ke-21 di Indonesia. Tansformasi  akan dilihat berdasarkan perubahan teori Material Cultural Studies, yang kemudian akan menghasilkan kesimpulan bahwa konsep ekologi berperan penting dalam perkembangan desain furnitur kayu di Indonesia.   Kata kunci: transformasi budaya, furnitur, kayu, Indonesia, ekologi

  8. Dinamika Pertunjukan Topeng pada Budaya Ngarot di Lelea Indramayu1

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    Asep Sulaeman

    2014-12-01

    ABSTRAK   Berdasarkan riset yang telah dilakukan beberapa tahun yang lalu, tentang dinamika per- tunjukan Topeng dalam upacara adat Ngarot, yaitu sebuah kegiatan atau praktik kultural ten- tang upacara adat bagi masyarakat Indramayu untuk mencapai pertemuan transedental. Ke- berangkatan penelitian ini mendorong  keingintahuan atas fenomena yang terjadi pada objek yang akan diteliti, maka dapat diidentifikasikan beberapa masalah yang akan dijadikan dasar untuk mengetahui lebih jauh tentang fenomena tersebut yaitu ada perubahan nilai-nilai filoso- fis, fungsi dan peran pertunjukan topeng dalam budaya Ngarot, yang jadi problematikanya adalah bagaimana wujud transformasi tari topeng dalam Ngarot dari masa ke masa? Masalah utama yang akan diungkapkan dalam penelitian ini adalah perubahan dilihat dari asfek nilai- nilai filosofis, fungsi dan peran.  Penelitian ini menggunakan metode kualitatif,  karena ma- salah-masalah penelitian ini ada dalam wilayah ruang seni yang sempit, variabel sederhana namun rumit dalam tataran konten, mempersoalkan makna, dan mempertanyakan fenomena. Sedangkan pendekatan yang diterapkan adalah multidisiplin dengan menggunakan pendeka- tan seni, pendekatan budaya, dan pendekatan sosiologi. Target luaran yang ingin dicapai dari penelitian ini menghasilkan konsep pendalaman makna, dan atau menginovasikan tari Topeng untuk masyarakat. Konsep yang dihasilkan dapat dijadikan salah satu panduan juga untuk berkreasi/berkarya dalam upaya merevitalisasi dan menginovasi tari Topeng lainnya.   Kata kunci: Pertunjukan Topeng, ngarot, transformasi, perubahan

  9. Eksistensi Gula Gending di dalam Dinamika Budaya Lombok

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    I Nyoman Triyanuartha

    2015-10-01

    Full Text Available Penelitian ini bertujuan untuk mengungkap eksistensi gula gending di dalam dinamika budaya yang terjadi di Lombok. Gula gending merupakan sebuah pertunjukan musik yang dimainkan ketika pedagang harum manis mepromosikan barang dagangannya untuk menarik perhatian calon pembeli. Seiring dengan perjalanan waktu, pertunjukan musik ini menjadi langka dan jarang ditemukan di dalam masyarakat. Kini gula gending muncul kembali dengan beberapa perkembangan yang menyertainya. Analisis dilakukan terhadap fakta musikal yang meliputi dimensi sonorik, dimensi visual dan dimensi kinestetik. Untuk membahas mengenai penyebab dan hasil dari perkembangan akan digunakan konsep music and cutural dynamic.   This research aims to gasp the exsistence of gula gending in cultural dynamic which occurs in Lombok. Gula gending was a music performance played when the arbanat seller was promoting their goods to attract the customers’ attention. As the time goes by, this music performance becomes rare, so we seldom find its existence in society. In spite of the fact, nowdays gula gending reappears along with few following developments. An analysis has been done to the musical facts which may include among athers are sonoric dimention, visual dimention, and kinesthetic dimention. To gain the explanation about the causes and results of the development, music and cultural dynamic concepts are conducted.

  10. Possibilities for power reactor structural material and fuel testing in reactor RA; Mogucnosti reaktora RA za testiranje konstrukcionih materijala i goriva energetskih reaktora

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    Martinc, R; Lazarevic, Dj; Stefanovic, D; Cupac, S; Pesic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-05-15

    Nuclear reactor RA at Vinca has been designed as a high flux general purpose research reactor. Among other it was intended to play a role of material testing reactor. A scope of activities of Material Laboratory and Reactor RA Department of Boris Kidric Institute is presented in this report. Reactor RA capacity for reactor structural material and fuel irradiation is also described. The increase of RA reactor irradiation capacity is based on the improvement of VISA type fuel channel for fast neutron irradiations, as well as on the general neutron flux increase, due to introduction of highly enriched uranium fuel into reactor core and the advanced in-core fuel management. The irradiation capacities described allow for the reactor material and fuel testing to the considerable extent. Istrazivacki reaktor RA u Vinci je projektovan kao visokofluksni istrazivacki reaktor opste namene. Pored ostalog, on je namenjen i za testiranje reaktorskih konstrukcionih materijala i goriva. U radu je dat pregled aktivnosti Laboratorije za materijale IBK i reaktora RA na tom podrucju, kao i opis povecanih mogucnosti reaktora RA za ozracivanje reaktorskih materijala i goriva u cilju njihovog testiranja. Povecanje mogucnosti reaktora RA zasniva se na usavrsavanju specijalnog gorivnog kanala tipa VISA (za ozracivanje materijala brzim neutronima), kao i na opstem povecanju neutronskog fluksa na osnovu uvodjenja i nacina koriscenja visokoobogacenog uranskog goriva u reaktoru RA. Opisane mogucnosti reaktora RA dozvoljavaju u znatnoj meri ispitivanje konstrukcionih materijala i goriva energetskih reaktora.

  11. Diagrams about RA reactor operation, Annex 7; Prilog 7 - Rad reaktora RA po godinama - dijagrami

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    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This Annex 7 includes diagrams about RA reactor operation (MWh) from 1960-1975; mean values of reactor power per day and month in 1975, and percent of utilisation of experimental space during 1975. [Serbo-Croat] Ovaj prilog sadrzi dijagrame o radu reaktora (MWh) po godinama (1960-1975); srednje vrednosti dnevne snage reaktora u 1975. godini; rad reakrora (MWh) po mesecima u 1975; procenat iskoriscenja eksperimentalnog prostora u 1975. godini.

  12. Problems of space-time behaviour of nuclear reactors; Problemi prostorno-vremenskog ponasanja nuklearnih reaktora

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    Obradovic, D [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper covers a review of literature and mathematical methods applied for space-time behaviour of nuclear reactors. The review of literature is limited to unresolved problems and trends of actual research in the field of reactor physics. Dat je pregled literature i matematickih metoda koje se koriste prilikom tretiranja prostorno-vremenskog ponasanja nuklearnih reaktora. Pregled literature ogranicen je na jos neresene probleme i pravce u kojima su danas usmerena istrazivanja u ovoj oblasti fizike nuklearnih reaktora (author)

  13. SURVEI DINAMIKA PENULARAN MALARIA DI DESA BANJARETNO, KECAMATAN KAJORAN, KABUPATEN MAGELANG, JAWA TENGAH

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    Ristiyanto Ristiyanto

    2012-09-01

    Full Text Available Dalam rangka menurunkan angka endemisilas malaria di Kabupaten Magelang telah dilakukan studi dinamika penularan. Tujuan survei dinamika penularan ini adalah mengetahui proses terjadinya penularan malaria dan faktor-faktor risiko kejadian malaria. Lokasi survei di Desa Banjaretno, Kecamatan Kajorun, Kabupaten Magelang, Jawa Tengah, Juni 2004. Metode survei adalah metode survei dinamika penularan yang telah distandardkan dalam pelatihan ICDC. Hasil survei parasit malaria menunjukkan bahwa 5 orang (5,10% dari 98 orang mengandung parasit Plasmodium falciparum. Hasil survei entomologi di liga rumah kasus malaria diperoleh angka man baiting rate (MBR nyamuk Anopheles aconitus di dalam rumah 0,5/jam/orang dan di luar rumah 1,08/jam/orang. Parity rate nyamuk tersebut 0%. Tempat perindukan di sekitar rumah kasus malaria adalah sawah, kolam, dan saluran irigasi. Penanaman padi tidak serempak, sehingga, tempat perindukan An. aconitus tersedia sepanjang tahun. Kepadatan larva nyamuk An. aconitus berkisar antara 0,3-2,1 perciduk. Hasil survei perilaku pada 31 responden (5 kasus malaria dan 26 orang tetangga kasus malaria diketahui bahwa pengetahuan, dan sikap responden mendukung untuk melakukan pencegahan penularan malaria (80% dari 31 responden, tetapi tidak diikuti dengan tindakan mencegah malaria (39,76% dari 31 responden. Semua rumah kasus malaria berdinding kayu atau bambu, belum menggunakan langit-langit, jendela dan ventilasi belum rapat nyamuk (100% rumah kasus malaria. Kebiasaan pada malam hari (5 kasus malaria yang mendukung penularan malaria adalah kebiasaan menonton TV bersama-sama pada malam hari dengan keadaan pintu dan jendela terbuka. Pelayanan kesehatan oleh Puskesmas tidak melakukan kunjungan rutin ke daerah endemis malaria karena tidak ada JMD. Hasil survei dinamika penularan ini memperlihatkan bahwa penularan malaria di Desa Banjaretno. Kecamatan Kajoran, Kabupaten Magelang, Jawa Tengah terjadi pada musim kemarau, di dalam rumah pada

  14. Safety analysis of RA Reactor operation I-III; Analiza sigurnosti rada Reaktora RA I - III, IZ-213-0322-1963

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    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This safety analysis report covers the following three parts: Technical and operational characteristics of the RA reactor; Accidents analysis; and Environmental effects of the maximum possible accident. [Serbo-Croat] Ovaj izvestaj o analizi sigurnosti rada reaktora RA sastoji se od tri dela: Tehnicke i pogonske karakteristike reaktora RA; Analiza akcidenta; i Posledice maksimalno moguceg akcidenta na okolinu reaktora.

  15. DINAMIKA PENANAMAN NILAI-NILAI BELA NEGARA KADET MAGUWO DALAM PERSPEKTIF HISTORIS

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    Yulianto Hadi

    2014-12-01

    Full Text Available Penelitian ini bertujuan untuk mengidentifikasi, mengetahui, memahami, dan menemukan: 1 formulasi nilai-nilai bela negara yang terkandung dalam peristiwa Serangan Fajar dan jatuhnya pesawat Dakota VT-CLA pada tanggal 29 Juli 1947; 2 dinamika interpretasi tokoh  dan pejabat TNI AU terhadap bela negara; 3 rumusan dinamika proses penanaman nilai-nilai bela negara di Sekbang; 4 faktor-faktor yang berpengaruh terhadap dinamika penanaman nilai-nilai bela negara di Sekbang. Penelitian ini merupakan penelitian kualitatif yang menggunakan kombinasi dari berbagai pendekatan dan metode penelitian. Simpulan dari penelitian ini adalah: 1 core value bela negara Kadet Maguwo yang masih relevan; sesuai dengan landasan historis dan landasan filosofis pendidikan meliputi nilai-nilai kesetiaan dan kecintaan terhadap negara Indonesia dengan tetap didasari nilai-nilai ketuhanan, ketulusan, kekuatan tekad, kesatria, moralitas, keteladanan, integritas, profesionalitas, dan kedisiplinan; 2 bela negara awalnya bersifat filosofis, dan diperkuat secara ideologis untuk mengembangkan eksistensinya yang mengutamakan keberanian dengan integritas dan profesionalitas; 3 penanaman nilai diawali secara sederhana dengan landasan filosofis yang penuh makna, berlanjut dengan intensitas yang tinggi untuk pemantapan ideologis, dan psikologis, kemudian mengarah ke sosiologis yang intensitasnya menuru; 4 dinamika penanaman nilai-nilai bela negara dipengaruhi oleh faktor ekonomi, politik, zaman, dan budaya yang berada pada empat tingkatan, yaitu nasional/internasional, departemen, unit pelaksana, dan individu siswa. Proses penanaman nilai-nilai bela negara yang berpola behavioristik dan melibatkan kesadaran siswa untuk turut aktif dalam proses pendidikan akan berdampak sangat dalam, merasuk kedalam jiwa dan menjadi sikap hidup sepanjang hayat siswa, karena telah mencapai pada tataran titik kesadaran integral. Kata kunci: penanaman nilai, nilai bela negara

  16. Research in nuclear reactor theory and experimental reactors; Istrazivanja u teoriji nuklearnih reaktora i ekspeimentalni reaktori

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    Pop-Jordanov, J [Elektrotehnicki fakultet, Beograd (Yugoslavia)

    1978-05-15

    The paper is devoted to the possibilities of using experimental reactors for scientific research in nuclear power with a stress on problems in nuclear reactor theory. The stationary and nonstationary neutron fields, burnup prediction and analyses as well as fuel element development and the corresponding role of test-reactors were dealt with. It was shown that the investigations in nuclear reactor theory in Yugoslavia were developing continuously and in a useful interaction with experiments on research reactors. The needs for continuing the work on fundamental problems in neutron transport theory and on improving the calculation methods for thermal power reactors, together with the improvement of performances of existing research systems, were pointed out. A new quality in scientific work could be obtained dealing with the problems connected to a possible introduction of test-reactors, and fast systems later on. It was also pleaded for the corresponding orientations in fundamental sciences. (author) Rad je posvecen mogucnostima koriscenja eksperimentalnih reaktora za naucna istrazivanja u nuklearnoj energetici, sa akcentom na probleme teorije nuklearnih reaktora. Obradjena su stacionarna i nestacionarna neutronska polja, predikcija i analize sagorevanja, kao i razvoj gorivnih elemenata te uloga test-reaktora u osvajanju njihove tehnologije. Pokazano je da su se istrazivanja u teoriji nuklearnih reaktora u nas odvijala kontinualno i u korisnoj interakciji sa eksperimentima na istrazivackim reaktorima. Istaknuta je potreba nastavljanja rada na fundamentalnim problemima transportne teorije neutrona i na usavrsavanju metoda proracuna termalnih enerrgetskih reaktora, uz poboljsanje performansi postojecih istrazivackih sistema. Novi kvalitet u naucnom radu bi predstavljala orijentacija na probleme vezane sa eventualnim uvodjenjem test-reaktora, a zatim i brzih sistema. Pledirano je i za odgovarajuca usmeravanja u fundamentalnim naukama. (author)

  17. RA reactor kinetic parameters - Progress report; Kineticki parametri reaktora RA - Izvestaj o napredovanju -

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Obradovic, D; Jevtovic, V; Velickovic, Lj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    The objective of nuclear reactor kinetics study is to analyze the stability of reactor operation in practice. The obtained parameters should define the needed properties of automatic control system relevant for the stability of the designed reactor system. Refining the analytical models is done by using the analysis and interpretation of experimental data. Results of measured the reactor response obtained by using the reactor oscillator ROB-1 are explained by using the space independent model of the zero power reactor, by power reactor model with one feedback circuit, and by a complex model. It was assumed that the perturbations of the system are small and that linearized kinetic equations could be used. Linearized kinetic equation of the reactor system are transformed into the frequency region in order to analyze the measured values directly. The objective of this paper is to measure the RA reactor kinetics parameters, and analyze the stability of reactor operation at power levels high than nominal. Istrazivanja u oblasti kinetike nuklearnih reaktora imaju za cilj da dovedu analizu stabilnosti rada reaktora na nivo 'radne tehnologije'. Dobijeni pararametri treba da specificiraju potrebne karakteristike sistema automatske kontrole za odgovarajucu stabilnost projektovanog reaktorskog sistema. Doterivanjem analitickih modela do takvog nivoa da se zapazeni fenomeni mogu anailitcki predvideti ide preko analize i interpretacije eksperimentalnih podataka. Eksperimentalni rezultati merenja odziva reaktora, izvedeni reaktorskim oscilatorom ROB-1, interpretirani su na osnovu prostorno nezavisnog modela za reaktor nulte snage, modelom reaktora snage sa jednim kolom povratne sprege, kao i kompleksnim modelom. U ovom radu se poslo od toga da su perturbacije parametara sistema male, pa se mogu upotrebiti linearizovane kineticke jednacine. Linearizovane kineticke jednacine reaktorskog sistema transformirane su u frekventno podrucje s ciljem direktne analize mernih rezultata

  18. Miskonsepsi Buku Ajar Fisika SMA Kelas X Pada Pokok Bahasan Dinamika Gerak

    Directory of Open Access Journals (Sweden)

    Fachmi Nurdiansyah

    2018-03-01

    Full Text Available Penelitian ini bertujuan untuk memaparkan bentuk-bentuk miskonsepsi pada pokok bahasan dinamika gerak dalam buku ajar fisika SMA kelas X. Adapun buku ajar yang digunakan dalam penelitian ini, yaitu: (1 Fisika untuk SMA/MA Kelas X Semester I karangan RA dan SI yang diterbitkan tahun 2012 oleh penerbit IP, (2 Fisika untuk SMA/MA Kelas X Semester I karangan TPM yang diterbitkan tahun 2013 oleh penerbit VP, dan (3 Fisika Peminatan untuk SMA/MA Kelas X karangan SN dan SZ yang diterbitkan tahun 2013 oleh penerbit YW. Penelitian ini merupakan penelitian kualitatif deskriptif. Objek dalam penelitian ini adalah data berupa aspek penjelasan konsep, penulisan rumus, penulisan simbol, penulisan satuan, dan penyajian gambar pada pokok bahasan dinamika gerak dalam buku ajar fisika SMA. Penelitian dilakukan dengan cara menganalisis data dalam buku ajar fisika SMA yang dibandingkan dengan buku teks fisika universitas. Berdasarkan analisis data yang telah dilakukan, dapat disimpulkan bahwa miskonsepsi pada pokok bahasan dinamika gerak terdapat dalam buku ajar fisika SMA. Buku ajar IP mengalami miskonsepsi pada aspek penjelasan konsep dengan persentase 10%, penulisan rumus dengan persentase 57,14%, penulisan simbol dengan persentase 46,15%, dan penyajian gambar dengan persentase 20%. Buku ajar VP mengalami miskonsepsi pada aspek penjelasan konsep dengan persentase 10%, penulisan rumus dengan persentase 85,71%, penulisan simbol dengan persentase 79,62%, dan penyajian gambar dengan persentase 80%. Buku ajar YW mengalami miskonsepsi pada aspek penjelasan konsep dengan persentase 10%, penulisan rumus dengan persentase 85,71%, penulisan simbol dengan persentase 69,23, dan penyajian gambar dengan persentase 20%. Pada aspek penulisan satuan, tidak terdapat miskonsepsi dalam buku ajar IP, VP, dan YW.

  19. IV Training program for the staff of the laboratory for the RA reactor exploitation; IV Programi obuke osoblja Laboratorije za eksploataciju reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    All the staff members of the laboratory for RA reactor exploitation are obliged to learn the following: fundamental properties of the RA reactor, the role and functionality of the reactor components, basic and auxiliary reactor systems, basics of radioactivity, measures for preventing contamination. The personnel working in shifts must be acquainted with the regulations and instructions for reactor operation. Training programs for reactor operators, mechanics, electricians, instrumentators and dosimetrysts are described separately. Svi saradnici Laboratorije za eksploataciju reaktora RA moraju poznavati sledece oblasti: Osnovne karakeristike reaktora RA, princip rada, ulogu i funkcionisanje komponenti reaktora, osnovnih i pomocnih sistema reaktora; osnovne pojmove o radioaktivnom zracenju, mere za sprecavanje kontaminacije. Osoblje koje radi u smenama mora dodatno poznavati propise i uputstva za rad reaktora. Posebno je naveden program obuke operatora reaktora, mehanicara, electricara, instrumentatora, dozimetrista.

  20. Chemical dosimetry of the RA reactor at Vinca, Yugoslavia; Hemijska dozimetrija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Gal, O; Markovic, V; Radak, B [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The ten-year work on in-pile chemical dosimetry of the Radiation chemistry Department at the Boris Kidric Institute at Vinca is reviewed. As an introduction, the general theory of the dosimetry of two-component radiation field is given and the uses of the derived equations in calorimetry and chemical dosimetry have been discussed. The chemical systems worked out for the in-pile use: solid oxalic acid and their solutions in light and heavy water, are then described and also the procedures of their use. The latter two are treated as a double system particularly suitable for two-component radiation fields. Finally, the limitations in use are discussed and some other systems, the study of which is in progress, mentioned (malonic and succinic acid) (author) [Serbo-Croat] Merenje energije koju apsorbuje sistem izlozen zracenju sastavni je deo svakog radijaciono-hemijskog eksperimenta. Time se moze objasniti veliki interes za koriscenje postojecih i razvijanje novih metoda dozimetrije u laboratorijama koje se bave radijacionom hemijom. Poslednjih godina posebna paznja se posvecuje dozimetriji vrlo visokih doza (10{sup 2}-10{sup 3} mrad) narocito onih sa kojima se radi u polju mesovitog zracenja reaktora. U laboratoriji za radijacionu hemiju Instituta 'Boris Kidric' u Vinci na dozimetriji zracenja reaktorskog jezgra radi se vec skoro 10 godina. Ta aktivnost je deo rada na hemijskoj dozimetriji uopste, kojom se bavi ova laboratorija od svog postanka (kraj 1955. godine). Sa radom na dozimetriji kod nas otpocelo se u periodu prvog podizanja na snagu reaktora RA, krajem 1959. godine. Paralelno su razvijane i primenjivane i hemijske i kalorimetrijske metode i njima vrsena dozimetrijska kalibracija reaktora. U ovom radu ucestvovalo je vise istrazivaca iz Laboratorije za radijacionu hemiju uz tesnu saradnju sa reaktorskim fizicarima i osobljem reaktora RA. Cilj ovog napisa je da sumira nas rad na hemijskoj dozimetriji reaktora. Pri tom se, najpre, zeli da ukaze na sustinu

  1. PERSEPSI DAN SIKAP PEREMPUAN TIONGHOA TERHADAP DINAMIKA POLITIK MASA REFORMASI DI KABUPATEN NGAWI

    Directory of Open Access Journals (Sweden)

    Khoirul Huda

    2017-11-01

    Full Text Available Penelitian ini bertujuan untuk mengetahui persepsi dan sikap kaum perempuan Tionghoa terhadap dinamika politik masa reformasi di Kabupaten Ngawi pada pelaksanaan pemilu Tahun 2014. Metode penelitian ini adalah kualitatif  dengansumber data primer diperoleh melalui wawancara informan dan data sekunder berupa foto atau arsip/dokumen diperoleh ketika observasi masyarakat perempuanTionghoa Kabupaten Ngawi.Analisis data menggunakan analisis data model interaktif Miles dan Huberman yang bergerak pada tiga tahap yaitu reduksi, sajian data dan verifikasi data. Berdasarkan hasil penelitian mengungkapkan bahwa persepsi dan sikap perempuan pada masyarakat Tionghoa dalam dinamika politik masa Reformasi kurang memiliki pengaruh yang signifikan. Kemudian mereka menganggap bahwa masa reformasi pasca tahun 1998 masih mempunyai sikap nasionalisme yang tinggi, akan tetapiseiring berjalannya waktu nasionalisme tersebut berubah pada bentuk tidak nasionalis, sebab banyak kasus korupsi oleh petinggi negara. Di dalam hal ini perempuan pada masyarakat Tionghoa tidak berpihak terhadap kepemimpinan mana yang layak dan baik, karena semua pemimpin dengan segala kebijakannya terdapat unsur positif dan negatif.Masyarakat Tionghoa khususnya perempuan kurang mempunyai andil dalam dimensi politik.Hal tersebut disebabkan karena mereka mimiliki jiwa dagang (bisnis yang tinggi dan sikap mereka dalamhal berpolitik dapat dilihat tatkala menggunakan hak suara dalam pemilihan umum yang dilakukan sejak masa reformasi hingga sekarang.

  2. Keterkaitan Dinamika Penduduk dan Kinerja Pembangunan Ekonomi Kabupaten/Kota di Provinsi Jambi

    Directory of Open Access Journals (Sweden)

    Hardiani Hardiani

    2017-03-01

    Full Text Available Abstrak. The study aimed to analyze: (1 The dynamics of population in districts/cities in Jambi province that include population condition and growth as well as the quality of population; (2 The relationship between dynamics of population and economic development performance. The data were analyzed in descriptive quantitative and qualitative methods using demographic indicators. Furthermore, to analyze the relationship between dynamics of population and economic development performance, correlation analysis was used. Results indicated that: 1 The total population in Jambi province is relatively small in number with low population density but with high inequality of population distribution among districts/cities; 2 Jambi province is one of the areas in Indonesia with a relatively rapid population growth; 3 Population’s age structure in Jambi province is no longer belong in the young age structure, but doesn’t meet the category of old age structure; 4 Compared to other provinces in Indonesia, education and health conditions in Jambi province has been relatively adequate; 5 Poverty level in Jambi province is relatively low compared with national poverty level, with declines that also is faster in comparative; 7 There is a positive correlation between quantity of population and economic growth but no correlation between quality of population and economic growth in Jambi province. Keywords: Education, Health, Poverty Abstrak. Penelitian ini bertujuan untuk menganalisis: (1 Dinamika penduduk pada kabupaten/kota di Provinsi Jambi yang mencakup kondisi dan perkembangan kuantitas penduduk serta kualitas penduduk (2 Keterkaitan dinamika penduduk dan kinerja pembangunan ekonomi pada kabupaten/kota di Provinsi Jambi. Data dianalisis secara deskriptif kuantitatif dan kualitatif, dengan memanfaatkan indikator-indikator kependudukan. Selanjutnya untuk menganalisis keterkaitan dinamika penduduk dan kinerja pembangunan ekonomi digunakan analisis korelasi.

  3. DINAMIKA SISTEM KOTA-KOTA DAN PEMILIHAN ALTERNATIF PUSAT PERTUMBUHAN BARU DI PROPINSI DAERAH ISTIMEWA YOGYAKARTA

    Directory of Open Access Journals (Sweden)

    Bambang Sriyanto Prakoso

    2016-10-01

    Full Text Available ABSTRAK Tujuan penelitian adalah menganalisa dinamika dan variasi perkembangan sistem kota-kota dan karakter kekotaan, guna memilih atau menentukan alternatif pengembangan pusat pusat baru di Propinsi sehingga pembangunan lebih merata. Penelitian menggunakan metode deskriptifianalitis dengan analisis data sekunder. Lingkup daerah penelitian meliputi seluruh desa di Propinsi DIY, sejumlah 438 desa yang tersebar di lima Kabupaten. Variabel yang digunakan meliputi variabel demografis untuk menganalisa sistem dan hirarki kota-kota dan variabel karakter kekotaan. Teknik analisis data yang digunakan adalah Index primacy, Analisis Faktor, Crosstab dan Korelasi, Pembuatan Tipologi Wilayah. Sedangkan analisis spasial atau pemetaan dengan program Arc View. Hasil penelitian menunjukkan, dinamika sistem kota-kota di Propinsi DIY sepanjang tahun 1960-2002 memperlihatkan gejala primacy atau pemusatan perkembangan di Kota Yogyakarta dan sekitarnya (pinggiran. Hal tersebut mengindikasikan adanya kesenjangan perkembangan wilayah dan beban kota semakin meningkat. Semakin tinggi peringkat wilayah, semakin dinamis perubahan yang terjadi, sena semakin tinggi karakter kekotaan yang dimilikinya. Fenomena pemusatan perkembangan yang tedadi di kota Yogyakarta dan sekitarnya merupakan bukti empiris pemusatan sistem perkotaan. Berdasarkan analisis yang komprehensif, ditetapkan kluster pusat pertumbuhan baru di lima Kabupaten Kota, yaitu Kluster Sentolo (Kabupaten Kulonprogo, Kluster Srandakan-Galur (Kabupaten Bantul, Kluster Playen-Patuk (Kabupaten Gunung Kidul, Kluster Tempel-Sleman (Kabupaten Sleman, dan Kluster Giwangan (Kota Yogyakarta. Penelitian merekomendasikan redistribusi hasil-hasil pembangunan melalui pengembangan dan penguatan pusat pertumbuhan baru, pembentukan tata ruang perwilayahan dan sistem perkotaan yang fungsional. Pusat pertumbuhan baru harus `mandiri. dan diintegrasikan dengan wilayah belakangnya (hinterland, sehingga tercipta keterkaitan fisik

  4. Regulations and instructions for RA reactor operation; Propisi i uputstva za pogon reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This regulatory guide consists of following 4 chapters: Description of the RA reactor, organization scheme, regulations for performing experiments; Regulations for staff on duty; Instructions for operating the vacuum systems, heavy water and helium systems; and evacuation in case of accident. [Serbo-Croat] Ovaj pravilnik sadrzi sledeca 4 poglavlja: Opis reaktora RA, sema organizacije rada, propisi za izvodjenje eksperimenata; Pravilnik za rad dezurnog osoblja; Uputstva za rada sa vakuum sistemima, sistemom teske vode, sistemom helijuma; evakuacija u slucaju udesa.

  5. Nuclear Reactor RA Safety Report, Vol. 12, Accidents during reactor operation; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 12, Akcidenti u dosadasnjem radu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    This volume includes description and analysis of typical accidents occurred during operation of RA reactor in chronological order, as follows: contamination of primary coolant circuit; leakage of heavy water from the primary coolant loop; contamination of vertical experimental channel; air contamination in the reactor building and loss of circulation of the primary coolant; failures of the vacuum pump and spent fuel packaging device; rupture of the spent fuel element cladding; dethronement's of capsule for irradiation of fuel element; rupture of the vertical experimental channel and contamination of the surroundings; swelling of a fuel element; appearance of deposits on the surface of the fuel elements cladding. The last chapter describes similar accidents occurred on nuclear reactors in the world. [Serbo-Croat] Ova knjiga sadrzi hronoloski pregled i analizu karakteristika akcidenata u dosadasnjem radu reaktora RA: kontaminacija primarnog kola hladjenja; isticanje teske vode is primarnog kola hladjenje; kontaminacija eksperimentalnog vertikalnog kanala; kontaminacija vazduha u hali reaktora i prestanak cirkulacije primarnog hladioca; otkaz vakum pumpe i uredjaja za prepakivanje ozracenog goriva; proboj kosuljice ozracenog gorivnog elementa; dehermetizacija kapsule za ozracivanje nuklearnog goriva; proboj eksperimentalnog vertikalnog kanala i kontaminacija prostorija; bubrenje gorivnog elementa; pojava taloga na kosuljicama gorivnih elemenata. Poslednje poglavlje opisuje udese na koji su se dogodili na nuklearnim reaktorima u svetu.

  6. Annex VII - Diagrams: 1. Reactor operation (1960-1977); 2. Mean daily reactor power density in 1977; 3. Monthly reactor power for 1977; 4. percent of utilization of experimental space in 1977; Prilog VII - Dijagrami: 1. Rad reaktora (MWh) po godinama (1960-1977); 2. Srednja dnevna snaga reaktora u 1977. godini; 3. Rad reaktora (MWh) po mesecima za 1977. godinu i 4. Procenat iskoriscenja eksperimentalnog prostora u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-15

    This Annex includes the following diagrams: 1. Annual Reactor RA power production (MWh) for the period from 1960-1977; 2. Mean daily reactor power density MW in 1977; 3. Monthly reactor power production (MWh) for 1977; 4. percent of utilization of experimental space in 1977. [Serbo-Croat] Ovaj prilog sadrzi dijagrame: 1. Rad reaktora (MWh) po godinama (1960-1977); 2. Srednja dnevna snaga reaktora u 1977. godini; 3. Rad reaktora (MWh) po mesecima za 1977. godinu i 4. Procenat iskoriscenja eksperimentalnog prostora u 1977. godini.

  7. Dinamika Kerukunan Intern Umat Islam Dalam Relasi Etnisitas Dan Agama Di Kalteng

    Directory of Open Access Journals (Sweden)

    Joko Tri Haryanto

    2013-06-01

    Full Text Available AbstrakAgama Islam dianut oleh sebagian besar penduduk Kalimantan Tengah yang terdiri dari berbagai etnis seperti Dayak, Banjar, Jawa, Madura, dan lainnya. Penelitian ini mengkaji dinamika hubungan intern umat Islam dalam konteks relasi etnisitas dan agama di Kalimantan Tengah. Permasalahannya adalah bagaimana dinamika hubungan inten umat Islam, faktor pendukung kerukunan, dan strategi adaptasi membangun harmoni di Kalimanta Tengah. Penelitian ini dilaksanakan dengan pendekatan kualitatif dimana pengumpulan data dilakukan melalui wawancara, observasi, Focus Group Discussion (FGD, dan telaah dokumen. Hubungan intern umat Islam di Kalimantan Tengah diwarnai dengan tanggapan terhadap konflik etnistahun 2001 antara Etnis Dayak dan Madura. Faktor yang mendukung kerukunan yang tercapai saat ini antara lain adanya daya tawar budaya, simbiosisme ekonomi, peran tokoh masyarakat, dan peran pemerintah. Adapun strategi adaptasi yang dilakukan untuk memelihara harmoni dilakukan secara kultural dengan revitalisasidan akulturasi budaya dan nilai-nilai lokal, serta secara struktural dengan politik uniformitas baik yang dilakukan oleh pranata Adat Dayak maupun pemerintah Kalimantan Tengah.Kata kunci: Kerukunan, Budaya Dominan, Politik Uniformitas, Strategi Adaptasi AbstractIslam is professed by the majority of people in Central Kalimantan who consists of various ethnic groups such as the Dayak, Banjar, Javanese, Madurese, and others. This study discusses about the dynamics of internal relationship among Muslim in the context of the relationship of ethnicity and religion in Central Kalimantan. The problems are how the dynamics of the internal relationship amongst Muslims in CentralKalimantan and what factors are supporting to the reconciliation and adaptation strategies to build harmony amongst them. This research was carried out with the qualitative approach in which data were collected through interviews, observation, Focus Group

  8. Instructions for RA reactor decontamination - Annex 10; Prilog 10 - Uputstvo za dekontaminaciju Reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Instructions for RA reactor decontamination includes: action plan for decontamination of the heavy water system by 7% water solution of H{sub 3}PO{sub 4} + 2% CrO{sub 3} acid; description of the preparatory work including calculation of the pipes volume and installation of special pipes; detailed instructions for decontamination procedure. [Serbo-Croat] Uputstvo za dekontaminaciju Reaktora RA sadrzi: plan operacija za dekontaminaciju sistema teske vode 7% vodenim rastvorom kiseline H{sub 3}PO{sub 4} + 2% CrO{sub 3}; opis pripremnih radova ukljucujuci proracun zapremine covovoda i montiranje posebnih cevovoda; detaljno uputstvo za izvodjenje operacija pri dekontaminaciji.

  9. Nuclear Reactor RA Safety Report, Vol. 8, Auxiliary system; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 8, Pomocni sistemi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    This volume describes RA reactor auxiliary systems, as follows: special ventilation system, special drainage system, hot cells, systems for internal transport. Ventilation system is considered as part of the reactor safety and protection system. Its role is eliminate possible radioactive particles dispersion in the environment. Special drainage system includes pipes and reservoirs with the safety role, meaning absorption or storage of possible radioactive waste water from the reactor building. Hot cells existing in the RA reactor building are designed for production of sealed radioactive sources, including packaging and transport. [Serbo-Croat] Ova knjiga obuhvata opis pomocnih sistem reaktora RA: sistem specijalne ventilacije, sistem specijalne kanalizacije, vruce komore, sistemi za unutrasnji transport. Ventilacioni sistem je znacajan deo sistema zastite i sigurnosti reaktora. Njegova je uloga da onemoguci disperziju radioaktivnih cestica u okolinu. Sistem specijalne kanalizacije sastoji se od agregata, cevovoda i rezervoara sa sigurnosnom armaturom i ima zadatak da prihvata i u sebe deponuje radioaktivne otpadne vode iz objekarta reaktora RA. U zgradi reaktora RA postoje vruce komore koje su namenjene za proizvodnju zatvorenih izvora zracenje, ukljucujuci i mehanicku obradu, prepakivanje i transport.

  10. Influence of absorbers on the reactivity of the reactor; Odredjivanje uticaja apsorbera na reaktivnost reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Influence of absorbers on the reactivity of the reactor was calculated by two-group diffusion theory applying corrections for boundary conditions derived from the transport theory because diffusion theory in not applicable in the vicinity of boundary surfaces especially in case of strong absorbers. This report shows the calculations of central absorber efficiency in the core with and without reflector, and efficiency of the group of absorbers randomly placed in the core. Approximation method for determining the efficiency of the absorber is described as well as numerical verification of results. Effective absorber dimensions and the influence of gaps on the reactor dimensions are shown. [Serbo-Croat] Uticaj apsorbera na reaktivnost reaktora racunat je primenom difuzione dvogrupne teorije uz korekcije kod primene granicnih uslova koje daje transportna teorija za efektivne dimenzije apsorbera posto difuziona teorija ne moze da primeni u blizini granicnih povrsina posebno kod jakih apsorbera. U ovom izvestaju dati su proracuni efektivnosti centralnog apsorbera u reflektovanom u nereflektovanom reaktoru, efektivnosti grupe proizvoljno ubacenih apsorbera. Dat je i prikaz aproksimativne metode za odredjivanje efektivnosti apsorbera kao i numericka provera rezultata. Prikazane su efektivne dimenzije apsorbera kao i uticaj supljina na kriticne dimenzije reaktora.

  11. EFEKTIVITAS PELAKSANAAN PROGRAM DINAMIKA KELOMPOK DENGAN METODE OUTBOUND PADA DIKLAT FUNGSIONAL AUDITOR DI PUSDIKLATWAS BPKP

    Directory of Open Access Journals (Sweden)

    Yuniar Palupi

    2017-01-01

    Full Text Available The objective of this research is to analyze the implementation effectiveness of the group dynamic program using outbound method.  The training is organized by Pusdklatwas BPKP and attended by all the government internal auditors in Indonesia.  The research uses Structural Equation Modeling (SEM with Partial Least Square approach.  The effectiveness of the program is scored using Kirkpatrick’s Four Level Training Evaluation model by measuring the participant’s perception on the implemented training, the learning process, and the benefit that can be obtained from the training.  The result shows that as an output, the training influences the participants learning process positively and significantly (trust, openness, responsibility, interdependency, self confidence, & stress management.  In addition, as a short term result the training also gives a positive and significant impact to the learning condition and for the medium term result is the adaptive performance of the participants.Keywords: audit, employee, performance, psychology, SEM AbstrakTujuan dari penelian ini adalah menganalisis efektivitas pelaksanaan program dinamika kelompok dengan metode outbound yang diselenggarakan oleh Pusdiklatwas BPKP untuk seluruh auditor internal pemerintah dari seluruh Indonesia.  Penelitian ini dianalisis menggunakan Structural Equation Modeling (SEM dengan pendekatan Partial Least Square (PLS. Efektivitas program dinilai dengan menggunakan teori evaluasi pelatihan empat level yang dikemukakan oleh Kirkpatrick, dengan mengukur persespi peserta program tentang pelaksanaan program, serta pembelajaran dan manfaat yang dirasakan oleh peserta program.  Hasil dari penelitian ini menunjukkan bahwa program efektif pada setiap tahapan evaluasi.  Hasil menunjukkan bahwa program ini secara positif dan signifikan berpengaruh terhadap pembelajaran peserta (trust, openness, responsibility, interdependency, self confidence, & stress management sebagai output

  12. Nuclear Reactor RA Safety Report, Vol. 5, Reactor cooling systems; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 5, Hladjenje reaktora i pripadajuci sistemi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    RA reactor cooling system enable cooling during normal operation and under possible accidental conditions and include: technical water system, heavy water system, helium gas system, system for heavy water purification and emergency cooling system. Primary cooling system is a closed heavy water circulation system. Heavy water system is designed to enable permanent circulation and twofold function of heavy water. In the upward direction of cooling it has a coolant role and in the downward direction it is the moderator. Separate part of the primary coolant loop is the system for heavy water purification. This system uses distillation and ion exchange processes. [Serbo-Croat] Sistemi za hladjenje reaktora RA obezbedjuju hladjenje u svim rezimima eksploatacije i potenijalno udesnim satnjim i obuhvataju: sistem tehnicke vode, sistem teske vode, gasni sistem helijuma, sistem za preciscavanje teske vode i sistem za akcidentalno hladjenje. Primarni sistem za hladjenje je zatvoreni cirkulacioni sistem teske vode. Specificnost sistema teske vode vezana je za neprekidnost cirkulacije i razlicite funkcije teske vode. U uzlaznom strujanju, teske vode ima ulogu hladioca a u silaznom ulogu moderatora. Poseban deo primarnog sistema predstavlja sistem za preciscavanje teske vode. Ovaj sistem koristi destilacioni i jonoizmenjivacki postupak.

  13. Kaindea: Dinamika Pengelolaan Hutan Adat di Pulau Kecil (Studi Kasus: Pulau Wangi-Wangi Kabupaten Wakatobi

    Directory of Open Access Journals (Sweden)

    Nur Arafah

    2011-01-01

    Full Text Available Indonesia adalah Negara Kepulauan yang mempunyai keragaman ekologi dan budaya dalam pengelolaan sumberdaya alam. Termasuk dalam pengelolaan hutan, masyarakat pulau-pulau kecil mempunyai system pengelolaan hutan adat yang terpelihara secara turun-temurun. Penelitian ini bertujuan mengkaji dinamika pengalolaan hutan adat berdasarkan kearifan masyarakat Pulau Wangi-Wangi. Penelitian ini kualitatif dengan metode studi kasus dalam perspektif emik, yaitu pandangan masyarakat Mandati di Pulau Wangi-Wangi terhadap pengelolaan hutan adat. Data dianalisis dengan pendekatan sejarah secara deskriptif. Hasil penelitian menunjukkan bahwa Masyarakat Mandati di Pulau Wangi-Wangi masih mempunyai pengelolaan hutan adat berbasis masyarakat yaitu Kaindea. Kaindea dikelola berdasarkan aturan adat yang berfungsi konservasi, ekonomi dan sosial budaya. Kelestarian pengelolaan hutan adat secara turun-temurun berkaitan dengan eksistensi hubungan antara “Kaindea-Koranga” (hutan-kebun dengan masyarakat. Disarankan agar transformasi kelembagaan pengelolaan hutan adat sebagai pilihan kebijakan berdasarkan kearifan dan kondisi ekologi local. Kata kunci: Kaindea, hutan adat, pulau-pulau kecil, kearifan lokal. Kaindea: Dynamic Management of Indigenous Forest in Small Island (Study Case: Wangi-wangi Island, Wakatoby Regency Abstract Indonesia as the archipelago country has diverse ecological and natural resources. Similarly, the type of forest management and its conditions also vary widely, so it requires an appropriate management system adapted to the local conditions. The objective of this study is to find out local wisdom in the Kaindea management system and ecological, economic and social-cultural fungction on Wangi-Wangi Island. This study is qualitative research with a case study method in emics perspective. Data is then analyzed descriptively by historical approach. The result of the study showed that Mandati community in Wangi- Wangi Island has a unique forest

  14. Operation and maintenance of RA Reactor, Annual report 1977; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    During 1977, the RA Reactor was operated at nominal power of 6.5 MW for 183 days. Total production was 28582 MWh which is 10% higher than planned. Second phase of introducing the 80% enriched fuel was fulfilled according to the plan. This means that the reactor core will be filled with highly enriched fuel in 1978. Refueling was done three time during the past year. After completing the first phase of the fuel exchange which was related mostly to reactor safety, the second phase will be devoted to the more efficient increase of neutron flux . This second phase is of utmost importance because higher neutron flux will provide better and more efficient reactor application from economic point of view. This will justify the application of the new more expensive highly enriched fuel. The budget for reactor operation and maintenance is hardly enough to cover the maintenance of the components and instrumentation. During 1977 there were no accidents related nor incidents related to the instrumentation or related to radiation protection. [Serbo-Croat] Reaktor RA je u toku 1977. godine ostvario rad od 28583 MWh odnosno 183 dana rada na nominalnoj snazi, sto u odnosu na plan rada iznosi 10% vise od planiranog. Druga faza uvodjenja 80% obogacenog goriva izvrsena je prema planu sto znaci da ce se punjenje jezgra reaktora 80% gorivom zavrsiti u toku 1978. godine. Izvrsene su tri izmene goriva. Posle isteka prvog dela prelaznog rezima koji je usmeren na maksimalnu sigurnost reaktora preci ce se na drugi deo usmeren na vece i brze povecanje neutronskog fluksa. Druga faza je od izuzetnog znacaja jer ce omoguciti bolje i znatno ekonomicnije koriscenje reaktora i opravdati upotrebu novog i skupljeg goriva. Sredstva za pogon i odrzavanje reaktora RA su jedva dovoljna za odrzavanje neophodnog nivoa opreme. Akcidenata u toku 1977. godine nije bilo ni sa opremom ni u pogledu zastite od zracenja.

  15. Simulasi Dinamika untuk Menentukan Stabilitas Sistem Tenaga Listrik Menggunakan Thyristor Controlled Braking Resistor pada Sistem IEEE 34 Node Test Feeder

    Directory of Open Access Journals (Sweden)

    Andi Taufiq

    2012-09-01

    Full Text Available Terdapat berbagai macam metode untuk meningkatkan stabilitas sistem  tenaga listrik. Salah satunya adalah dengan menggunakan metode pengereman dinamis (dynamic braking. Generator sinkron sebagai distributed generator yang digerakkan oleh mesin diesel. Pada saat terjadi gangguan pada sistem, digunakan sebuah Thyristor Controlled Braking Resistor (TCBR untuk meredam osilasi yang terjadi. Sistem yang hendak dianalisis dinamika dan stabilitasnnya adalah IEEE 34 node test feeder. Dengan sistem ini diilustrasikan karakteristik dan keefektifan TCBR untuk meredam osilasi frekuensi rendah dan mencegah terjadinya ketidakstabilan transien sistem. Dari hasil analisis diperoleh bahwa dengan adanya penambahan TCBR (Thyristor Controlled Braking Resistor maka respon transien sistem akan menjadi lebih baik. Hal ini ditunjukkan dengan adanya penurunan overshoot dan settling timenya. Dengan demikian sistem akan menuju kondisi stabil dengan lebih cepat setelah terjadi gangguan.

  16. Measurement of zero power reactor dynamic response by cross correlation method; Merenje dinamickog odziva reaktora nulte snage kros korelacionom metodom

    Energy Technology Data Exchange (ETDEWEB)

    Kostic, Lj; Petrovic, M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1969-07-15

    Pulse response is comprehensive description of linear system dynamics. In this paper, cross correlation method was used for measuring the response of zero power reactor. Reactor system was perturbed by pseudo-random signal, which was cross correlated with the reactor signal responding to this perturbation on the digital ZUSE Z-23 computer. Cross-correlation functions were measured for different positions of stochastic oscillator and ionization chamber in the critical system. From numerical processing of performed experimental data, it was concluded that a more powerful faster computer would be needed for processing statistical experiments. In that case it would be possible to obtain information about spatial effects in the reactor and propagation of neutron waves in the multiplication medium. Impulsni odziv je potpuni opis dinamike linearnog sistema. Za merenje impulsnog odziva nultog reaktora, u ovom radu, koriscena je kros korelaciona metoda. Reaktorski sistem je perturbovan pseudoslucajnim signalom, koji je u digitalnom racunaru ZUSE Z-23 kroskorelisan sa signalom odziva reaktora na ove perturbacije. Merene su kroskorelacione funkcije za razlicite polozaje stohastickog oscilatora i jonizacione komore u kriticnom sistemu. Iz numericki obradjivanih eksperimenta namece se kao zakljucak da bi za obradu statistickih eksperimenata kod nultih reaktora bio potreban racunar veceg kapaciteta i brzine. U tom slucaju bi se iz ovako postavljenog eksperimenta moglo doci i do informacija o prostornim efektima u reaktoru i prostiranju neutronskih talasa kroz multiplikativnu sredinu. (author)

  17. Resonance absorption of nuclear gamma radiation; Absorption par resonance des rayons gamma; Rezonansnaya absorbtsiya i rasseyanie yadernogo gamma-izlucheniya; Absorcion por resonancia de las radiaciones gamma en los nucleos

    Energy Technology Data Exchange (ETDEWEB)

    Hanna, S S; Perlow, G J [Argonne National Laboratory, Argonne, IL (United States)

    1962-01-15

    radiacion do resonancia con y sin polarizacion. Estos estudios les han conducido a una interpretacion de la estructura hiperfina en funcion de las propiedades de los estados nucleares y de la interaccion hiperfina en el hierro. Tambien han investigado los efectos de un campo magnetico externo sobre la estructura hiperfina. Por otra parte, la absorcion por resonancia en el {sup 57}Fe permitio estudiar la relacion entre la cronologia de la desintegracion de im estado nuclear y el espectro de la radiacion observada. Se realizaron observaciones detalladas sobre el espectro de las radiaciones de resonancia filtradas, en funcion del tiempo, en condiciones muy diversas. (author) [Russian] Kak pokazal Messbauehr, ispuskanie i pogloshchenie yadernogo izlucheniya bez otdachi yadra obespechivaet prostoj metod izucheniya vzaimodejstviya yader s ehlektromagnitnym izlucheniem i, chto ochen' vazhno, yavlyaetsya chrezvychajno chuvstvitel'nym sredstvom issledovaniya bol'shogo kolichestva fizicheskikh zadach. V sluchae yader zheleza-57 sozdaetsya ves'ma blagopriyatnoe polozhenie, tak kak v ehtom sluchae rezonansnoe pogloshchenie mozhet ispol'zovat'sya v kachestve ochen' chuvstvitel'nogo detektora izmeneniya chastoty ehlektromagnitnogo izlucheniya. Detal'no izuchalos' rezonansnoe pogloshchenie v zheleze-57. Intensivnost' pogloshcheniya, forma i liniya sdviga nablyudalis' v zavisimosti ot temperatury. Polyarizatsiya radioaktivnogo izlucheniya nablyudalas' posredstvom ehksperimentov s namagnichennymi istochnikami i poglotitelyami. Sverkhtonkij spektr rezonansnoj radiatsii analizirovalsya s polyarizatsiej i bez nee. EHti issledovaniya priveli k tolkovaniyu sverkhtonkoj struktury v otnoshenii svojstv yadernykh sostoyanij i sverkhtonkogo vzaimodejstviya v zheleze. Bylo rassmotreno takzhe vliyanie vneshnego magnitnogo polya na sverkhtonkuyu strukturu. Rezonansnoe pogloshchenie v zheleze-57 bylo ispol'zovano dlya izucheniya svyazi mezhdu razvitiem raspada yadernogo sostoyaniya vo vremeni i spektrom

  18. Operation, maintenance and utilization of the RA reactor, Annual report 1978; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1978. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    It has been planned for 1978 that the RA reactor would be operated for 158 dana at nominal power of 6.5 MW meaning production of 24 648 MWh. The plan was fulfilled since 24 652 MWh was produces. Reactor operation for 158 days is relevant to reactor operation for 200 days in the period before 1975. The reason is increased neutron flux achieved due to improved fuel management and the characteristics of the new 80% enriched fuel. At the end of 1978 the reactor core contained 45% of 80% enriched fuel elements. Increase of neutron flux has shortened the typical time needed for irradiation of the most important samples for isotope production. This significant success in reactor operation is at the same time an obligation for increasing its utilization. Some new trends proposed for increasing reactor utilization capacities were presented at the Conference on utilization of research nuclear reactors in Yugoslavia held in May 1978. [Serbo-Croat] Reaktor RA imao je u planu za 1978. godinu 158 dana rada na nominalnoj snazi od 6.5 MW, sto odgovara radu od 24 648 MWh. Ostvareno je 24 652 MWh sto znaci da je plan ostvaren. Rad reaktora od 158 dana odgovara radu reaktora od 200 dana u periodu pre 1975. godine. Razlog je povecanje neutronskog fluksa zahvaljujuci usavrsenom rukovanju gorivom i karakteristikama novog 80% obogacenog goriva. Krajem 1978. godine 45% jezgra reaktora bilo je popunjeno novim 80% obogacenim gorivom. Povecani neutronski fluks omogucio je skracenje vremena ozracivanja vaznih uzoraka za proizvodnju radioaktivnih izotopa. Ovaj znacajan uspeh je istovremeno obaveza znatno veceg iskoriscenja reaktora RA. Rezultati napora da se postigne vece iskoriscenje reaktora RA prezentirani su na Konferenciji o koriscenju nuklearnih reaktora u Jugoslaviji koja je odrzana u maju 1978.

  19. Action plan during reactor shutdown in October 1965, Annex 5; Prilog br. 5 - Plan radova u toku stajanja reaktora u mesecu oktobru 1965. godine

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The action plan of the division for reactor maintenance during reactor shutdown includes detailed list of tasks for mechanics, electronic and electrical equipment group during the reactor shutdown period in October 1965. It contains tasks for planned shutdown periods in September, August, July, May, April, March, and February 1965. [Serbo-Croat] Plan radova Odelenja odrzavanja reaktora RA za period stajanja reaktora u oktobru mesecu 1965. sadrzi detaljnu listu zadataka masinske grupe, elektro grupe i elektronske grupe. Ovaj prilog sadrzi i zadatke koji ce biti obavljeni tokom planiranih perioda kada je reaktor zaustavljen u septembru, avgustu, julu, junu, maju, aprilu, martu i februaru 1965.

  20. RA Research nuclear reactor Part 1, RA Reactor operation and maintenance in 1987; Istrazivacki nuklearni reaktor RA Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1987. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1987-12-15

    RA research reacto was not operated due to the prohibition issued in 1984 by the Government of Serbia. Three major tasks were finished in order to fulfill the licensing regulations about safety of nuclear facilities which is the condition for obtaining permanent operation licence. These projects involved construction of the emergency cooling system, reconstruction of the existing special ventilation system, and renewal of the system for electric power supply of the reactor systems. Renewal of the RA reactor instrumentation system was initiated. Design project was done by the Russian Atomenergoeksport, and is foreseen to be completed by the end of 1988. The RA reactor safety report was finished in 1987. This annual report includes 8 annexes concerning reactor operation, activities of services and financial issues, and three special annexes: report on testing the emergency cooling system, report on renewal of the RA reactor and design specifications for reactor renewal and reconstruction. [Serbo-Croat] Reaktor RA nije radio usled zabrane Izvsnog veca Skupstine Srbije od 27. avgusta 1984. U cilju povecanja pouzdanosti rada reaktora a da bi se udovoljilo zakonskim propisima sto je uslov za dobijanje stalne dozvole za rad realizovana su tri velika zahvata na reaktoru RA. Ovi zahvati obuhvatili su izgradnju sistema za hladjenje jezgra reaktora u slucaju nuzde, rekonstukciju postojeceg sistema specijalne ventilacije i rekonstrukciju sistema napajanja elektricnom energijom neophodnih potrosaca reaktora RA. Zapoceti su radovi na modernizaciji intrumentacije reaktora RA, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, a trebalo bi da se realizuje do kraja 1989. godine. U cilju povecanja prostora za skladistenje ozracenog nuklearnog goriva i njegovog efikasnijeg koriscenja, izradjen je su projekti za rekonstrukciju postojecih uredjaja za rukovanje gorivom, povecanje smestajnog kapaciteta i preciscavanje vode u bazenima za odlezavanje. Realizaija ovih

  1. Maximum neutron flux at thermal nuclear reactors; Maksimum neutronskog fluksa kod termalnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1968-10-15

    Since actual research reactors are technically complicated and expensive facilities it is important to achieve savings by appropriate reactor lattice configurations. There is a number of papers, and practical examples of reactors with central reflector, dealing with spatial distribution of fuel elements which would result in higher neutron flux. Common disadvantage of all the solutions is that the choice of best solution is done starting from the anticipated spatial distributions of fuel elements. The weakness of these approaches is lack of defined optimization criteria. Direct approach is defined as follows: determine the spatial distribution of fuel concentration starting from the condition of maximum neutron flux by fulfilling the thermal constraints. Thus the problem of determining the maximum neutron flux is solving a variational problem which is beyond the possibilities of classical variational calculation. This variational problem has been successfully solved by applying the maximum principle of Pontrjagin. Optimum distribution of fuel concentration was obtained in explicit analytical form. Thus, spatial distribution of the neutron flux and critical dimensions of quite complex reactor system are calculated in a relatively simple way. In addition to the fact that the results are innovative this approach is interesting because of the optimization procedure itself. [Serbo-Croat] Savremeni reaktori za fizicka i tehnoloska istrazivanja predstavljaju tehnicki komplikovanu i skupu masinu. Iz tog razloga su opravdana nastojanja da se podesnim rasporedom goriva u jezgru reaktora dodje do sto ekonomicnijeg rjesenja. U literaturi postoji vise radova, cak i konkretnih realizacija u vidu reaktora sa reflektorom u centru, koji se bave odredjivanjem takve prostorne zavisnosti koncentracije goriva koja pod odredjenim uslovima daje najveci neutronski fluks. Zajednicki nedostatak svih pomenutih rjesenja je u tome sto se polazi od pretpostavljenih prostornih distribucija

  2. Wpływ czasu napowietrzania na pracę reaktora SBR i SBBR

    Directory of Open Access Journals (Sweden)

    Małgorzata Makowska

    2016-06-01

    Full Text Available W pracy przedstawiono efekty oczyszczania małych ilości ścieków w bioreaktorach porcjowych. Przebadano dwa równolegle pracujące reaktory, z czego jeden był klasycznym systemem SBR, a drugi to reaktor SBBR ze złożem ruchomym. Obydwa ciągi technologiczne oczyszczały taką samą ilość ścieków bytowych wstępnie podczyszczonych w piaskowniku. Trzy kolejne serie badań różniły się długością napowietrzania. Porównano pracę reaktorów w kolejnych seriach oraz analizowano wyniki uzyskane w obu systemach. Największą skuteczność usuwania związków węgla organicznego (jako ChZT i azotu (jako N-NH4 uzyskano w reaktorze SBBR w trzeciej serii badań (średnio odpowiednio 90 i 62%. Reaktor SBBR pracował bardziej stabilnie oraz usuwał na drodze biologicznej fosfor z największą średnią skutecznością 83% w serii trzeciej. Ścieki oczyszczone w tym reaktorze charakteryzowały się mniejszym stężeniem zawiesiny, co świadczy o skuteczniejszej pracy reaktora z wypełnieniem w fazie sedymentacji.

  3. RA reactor action plan for 1977 - Annex VI; Prilog VI - Plan rada reaktora RA za 1977. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-12-15

    In the RA reactor action plan for 1977 it is foreseen that the reactor would be operated for 181 days, mostly at nominal power of 6.5 MW. It is planned to produce 28236 MWh in total. Five reactor core exchanges (refuelling) are planned. The plan includes time for repair of components as well as for cooling. [Serbo-Croat] Plan rada reaktora RA predvidja rad tokom 181 dana, vecim delom na nominalnoj snazi od 6,5 MW tokom 1977. godine. Planirano je da ukupni rad iznosi 28236 MWh. Planom je predvidjeno i pet izmena goriva kao i vreme potrebno za remont opreme i hladjenje.

  4. Regulations for the maintenance division of the RA reactor, Annex 6; Prilog 6 - Pravilnik poslovanja Odelenja odrzavanja i remonta reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The regulations for the Division of reactor maintenance include the organizational scheme, tasks of the Division, and operation procedures for all the staff members. [Serbo-Croat] Pravilnik o radu Odelenja za odrzavanje reaktora RA sadrzi opis organizacione strukture sluzbe, zadataka Odelenja, organizacije rada, nacin poslovanja za sve saradnike Odelenja.

  5. Operation, safety and utilization of the RA reactor in 1978 - Report; Prilog I - Rad, sigurnost i iskoriscenost reaktora RA u 1978. godini - Izvestaj

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This report includes a review of work related to development of reactor operation capacities and increase of the RA reactor safety and economic operation. Statistical data about reactor operation and utilization are included as well. Introducing of the new 80% enriched fuel into the the reactor core enabled increase of the neutron flux, i.e. increase of its production capabilities. Safety and optimization analyses concerned with introduction of the new fuel have shown that the most safe and economic procedure was gradual introducing of the highly enriched fuel. This procedure was based on the concept of mixed core configuration with 2% and 80% enriched fuel elements. By applying this original concept the following significant savings were achieved: fuel elements savings, shortening of the annual period of reactor operation, savings in spent fuel casks, electric power savings, slowing down of heavy water degradation. [Serbo-Croat] Ovaj izvestaj sadrzi pregled o radu na razvoju eksploatacionih mogucnosti i povecanju sigurnosti i ekonomicnosti reaktora RA. Prilozeni su i statisticki podaci o radu i iskoriscenosti reaktora u 1978. godini. Uvodjenje novog 80% obogacenog goriva u jezgro reaktora omogucilo je povecanje neutronskog fluksa tj. povecanje njegovoh proizvodnih mogucnosti. Sigurnosne i optimizacione analize uvodjenja novog goriva pokazale su da je nasigurniji i najekonomicniji postupak postupnog uvodjenja visokoobogacenog goriva koji se zasniva na konceptu mesane resetke sa 2% i 80% obogacenim gorivom. Ovaj originalni koncept omogucio je da se postignu znatne ustede u gorivu, skracivanje godisnjeg rada reaktora, usteda sudova za odlaganje isluzenog goriva, usteda elektricne energije, usporavanje degradacije teske vode.

  6. Operation and maintenance of the RA nuclear reactor for 1977, Report Annex I; Rad i iskoriscenost reaktora RA u 1977. godini, izvestaj Prilog I

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    RA reactor operation plan was fulfilled, meaning 28583 MWh. In addition to 183 days of operation at full power, during 1977 the reactor was operated for 14 days at lower power level according to the demand of users. The utilization level of rector irradiation capability (neutron flux and time of operation) was 14%. This annex includes detailed statistical data about reactor operation, utilization, power level, savings concerned with new 80% enriched fuel. All the 9 vertical experimental channels were used for irradiation in the reactor core. Digression from the action plan were caused by refueling and demand od the users. There have been 11 safety shutdowns, of which 6 caused by power cuts, 4 due to failure of the instruments, and 1 due to earthquake in March 1977. [Serbo-Croat] Planirani rad reaktora na nominalnoj snazi ostvaren je u iznosu od 28583 MWh. U toku 1977. godine reaktor je radio 14 dana na manjim snagama i u posebnom eksperimentalnom rezimu na zahtev korisnika. Iskoriscenost kapaciteta reaktora za ozracivanje uzoraka (na bazi neutronskog fluksa i vremena rada reaktora) bila je 41%. Ovaj izvestaj sadrzi detaljne statisticke podatke o radu i iskoriscenosti reaktora, podatke o ustedi goriva prelaskom na 80% obogaceno gorivo. Korisceno je svih 9 vertikalnih eksperimentalnih kanala u aktivnoj zoni. Uzroci odstupanja od plana rada osim zamene goriva bili su zahtevi korisnika. Bilo je 11 sigurnosnih zaustavljanja, 6 usled nestanka napona, 4 usled kvarova opreme i instrumentacije, i 1 put usled zemljotresa u martu.

  7. Nuclear Reactor RA Safety Report, Vol. 14, Safety protection measures; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 14, Sigurnosne zastitne mere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Nuclear reactor accidents can be caused by three type of errors: failure of reactor components including (1) control and measuring instrumentation, (2) errors in operation procedure, (3) natural disasters. Safety during reactor operation are secured during its design and construction and later during operation. Both construction and administrative procedures are applied to attain safe operation. Technical safety features include fission product barriers, fuel elements cladding, primary reactor components (reactor vessel, primary cooling pipes, heat exchanger in the pump), reactor building. Safety system is the system for safe reactor shutdown and auxiliary safety system. RA reactor operating regulations and instructions are administrative acts applied to avoid possible human error caused accidents. [Serbo-Croat] Uzroci udesa na nuklearnim reaktorima mogu se svrstati u jednu od sledece tri grupe: (1) otkaz pojedinih delova opreme, ukljucujuci mernu i kontrolnu instrumentaciju, (2) greske u pogonu i eksploataciji, (3) prirodne nepogode, katastrofe. Bezbednost i sigurnost u radu nuklearnog reaktora osiguravaju se odredjenim merama koje se preduzimaju pri njegovoj izgradnji i kasnije njegovoj elsploataciji. Te mere se mogu podeliti u sledece dve kategorije: (1) mere tehnicke zastite, i (2) administrativne mere. Mere tehnicke zastite sastoje se od barijere fissionih produkata, kosuljice gorivnih elemenata, primarnog kola reaktora RA (reaktorski sud, cevovod primarnog kola, toploizmenjivac u pimpi), zgrada reaktora. Sigurnosni sistem cini sistem za sigurnosno zaustavljanje reaktora i pomocni sigurnosni sistem. Kroz odgovarajuce propise i uputstva za rad na reaktoru RA primenjene su administrativne mere neophodne za sprecavanje udes koji bi mogao nastati kao posledica ljudskog faktora.

  8. Dinamika Penyesuaian Diri Penyandang Disabilitas di Tempat Magang Kerja: Studi Deskriptif di Balai Rehabilitasi Terpadu Penyandang Disabilitas (BRTPD Yogyakarta

    Directory of Open Access Journals (Sweden)

    Ani Nur Sayyidah

    2015-06-01

    Hasil penelitian ini menunjukkan proses pelaksanaan magang kerja selama 25 hari dengan tahapan pelaksanaan bimbingan vokasional, orientasi dan konsultasi, penempatan klien di tempat magang kerja, pelaksanaan bimbingan kerja, penarikan klien dari tempat magang, evaluasi dan monitoring. Penyandang disabilitas rungu wicara ditempatkan di perusahaan yang bergerak dibidang distributor alat-alat rumah tangga, penyandang disabilitas netra ditempatkan di panti pijat dan penyandang disabilitas daksa ditempatkan di perusahaan yang bergerak dibidang percetakan dan sablon. Dinamika penyesuaian diri dari ketiga informan tersebut yang memiliki penyesuaian yang lebih sehat yaitu penyandang disabilitas rungu wicara karena mampu memenuhi 3 dari 4 aspek dalam penyesuaian diri yang sehat. Aspek yang terpenuhi yaitu aspek kematangan sosial, aspek kematangan intelektual, aspek kematangan tanggung jawab personal dan aspek yang kurang dapat terpenuhi yaitu aspek kematangan emosional. Penyandang disabilitas netramampu memenuhi 2 aspek penyesuaian diri dan 2 aspek kurang dapat terpenuhi. Aspek yang terpenuhi yaitu aspek kematangan sosial dan aspek kematangan tanggung jawab personal, aspek yang kurang dapat terpenuhi yaitu aspek kematangan emosional dan intelektual. Sedangkan penyandang disabilitas daksa terdapat tiga aspek yang kurang dapat terpenuhi yaitu aspek kematangan emosional, sosial dan tanggung jawab personal, hanya 1 aspek yang terpenuhi yaitu aspek kematangan intelektual

  9. RA research nuclear reactor operation in forced regime, Annex 5; Prilog 5 - Rad istrazivackog nuklearnog reaktora RA u forsiranom rezimu, Prvo saopstenje

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    In order to increase the flux and experimental potentials of the RA reactor, properties of the reactor operating in the forced regime have been inspected four times, twice with the spent fuel (core C), and twice with partly fresh fuel (cores E and F). Forced regime means power higher than nominal 6.5 MW. From the analyses of technology parameters during operation in the forced regime at power levels of 7 and 11 MW, state and behaviour of the components, efficiency of the biological protection and other parameters it was concluded that the reactor operation is possible at power levels of 10 MW during a whole year, and under certain conditions even longer operation at power levels up to 15 MW. This paper examines the reactor operation conditions in the forced regime and gives conclusions related to real increase of the experimental possibilities, isotope production and economic factors. Radi povecanja fluksa i eksperimentalnih mogucnosti reaktora RA, cetiri puta su proverene osobine reaktora u forsiranom rezimu, tj. na snagama vecim od nominalne (6,5 MW) i to dva puta sa istrosenim gorivom (jezgro C) i dva puta sa delimicno svezim (jezgra E i F). Iz analize tehnoloskih parametara u toku eksperimentalno rada reaktora u forsiranom rezimu na snagama od 7 do 11 MW, stanja i ponasanja opreme, efikasnosti bioloske zastite i ostalih parametara, zakljucuje se da je moguc permanentan rad reaktora tokom cele godine na snagama do 10 MW, a pod izvesnim uslovima i duzi rad na snagama do 15 MW. U radu su diskutovani uslovi rada reaktora u forsiranom rezimu i donose se zakljucci o realnom povecanju eksperimentalnih mogucnosti, proizvodnje radioizotopa i o ekonomskim faktorima (author)

  10. Experimental study of space dependent nuclear reactor kinetics - Progress report; Eksperimentalno proucavanje prostorno zavisne kinetike nuklearnih reaktora - Izvestaj o napredovanju

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Petrovic, M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    This paper describes experimental study of space-time behaviour of nuclear reactors by local complex-periodic perturbation of the absorption cross section and by measuring the local reactor response to this perturbation. Perturbation was done by BOR-1 fast oscillator. Cross correlation between the response and the perturbation was done numerically after completing the measurement by using digital computer. Obtained experimental results are preliminary and are measured with significant errors which were analysed in this paper. Results show qualitative agreement with those obtained by theoretical model. This paper is the first progress report in this field in our country. U radu je opisan eksperimentalni prilaz proucavanju prostorno-vremenskog ponasanja nuklearnih reaktora, vrseci lokalnu slozeno-periodicnu perturbaciju apsorpcionog preseka i mereci lokalni odziv reaktora na tu perturbaciju. Perturbacija je vrsena brzim oscilatorom BOR-1. Kroskorelacija izmedju odziva i perturbacije vrsena je numericki posle obavljenog merenja upotrebom digitalne racunske masine. Dobijeni eksperimentalni rezultati imaju preliminarni karakter i odredjeni su sa znatnim eksperimentalnim greskama koje su, u radu analizirane. Izlozeni rezultati pokazuju kvalitativna slaganja sa teorijski dobijenim modelom. Ovaj rad predstavlja prvi izvestaj o napredovanju na ovoj problematici kod nas (author)

  11. Nuclear Reactor RA Safety Report, Vol. 1, Introduction; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 1, Uvod

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Based on the agreement between governments of Socialist Federal Republic of Yugoslavia and USSR of January 28 1956, a contract was signed about construction of RA research reactor in the Boris Kidric Institute of nuclear sciences. Building of the RA reactor started in 1956, and has reached criticality in 1959. Since then it has been in almost permanent operation, except for five longer shutdown periods: in 1963 because of heavy water and primary coolant system contamination with cobalt; in 1970 because of transporting the heavy water to France for isotopic regeneration; in 1979/1980 and 1983 because of aluminium oxyhydrate deposition on the fuel element cladding in reactor active region; in 1985/1986 because of ventilation system reconstruction and construction of emergency core cooling system. RA reactor is a heavy water cooled and heavy water moderated research reactor. Since the beginning of its operation, 2% enriched metal uranium fuel was used. From 1976, 80% enriched uranium oxide fuel elements were used partially in some core regions and since 1981 the complete core was filled with this highly enriched fuel. RA reactor was designed to operate under normal conditions at 6.5 MW power and at 10 MW power under forced regime. As a powerful neutron source the reactor was meant to be used for research in the field of reactor and neutron physics, solid state physics, radiation chemistry, biology and radioactive isotopes production. RA reactor was build by Yugoslav companies based on USSR basic design project. Main components of the systems were produced in USSR. [Serbo-Croat] Na osnovu Sporazuma izmedju vlada SFRJ i SSSR od 28. januara 1956. godine, sklopljen je ugovor o izgradnji istrazivackog reaktora RA u Institutu za nuklearne nauke Boris Kidric u Vinci. Reaktor RA je poceo da se gradi 1956. godine, a kriticnost je postigao 1959. godine. Od tada je takoreci neprekidno bio u radu, izuzev u pet slucajeva duzeg stajanja: 1963. godine - zbog kontaminacije teske vode

  12. Measurement of graphite and aluminium absorption cross sections via reactor period by danger coefficient method; Merenje apsorpcionih preseka grafita i aluminijuma preko periode reaktora metodom koeficijenta opasnosti

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Markovic, V; Velickovic, Lj [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1963-07-01

    Full text: This activity is a logical continuation of the experiment at the RA reactor during 1962 which was based on compensating the effect by means of control rod. Since results are given with significant errors, new method for measuring the absorption cross sections via reactor period. Experiment was done at the RB reactor which was particularly prepared for this type of experiments. Reactor power was from 50 mW to 2 W. Absorption cross sections were measured for two types of material: domestic graphite No.3 and French graphite 'Pachiney', and two types of aluminium. Total errors in applying this method are {+-} 5%, where the source of major part of error comes from uncertainty of the standard absorption power (previous method gave {+-} 10 do 55% ). Comparison of French graphite absorption cross section obtained via reactor period and via control rod showed approximate agreement with discrepancy of 5.4% which is considered within the precision of this method. Considering the accuracy of measurement results and reactor economy it is concluded that measuring absorption cross sections of samples via period of RB reactor is more favourable than measurements by control rod at the RA reactor. Pun tekst: Ovaj rad predstavlja logican nastavak eksperimenta na reaktoru RA u toku 1962. godine, koji je bazirao na kompenzaciji efekta pomocu kontrolne sipke. Kako su rezultati dati sa velikim greskama, to se prislo novom nacinu merenja apsorpsionih preseka preko periode reaktora. Eksperiment je radjen na reaktoru RB koji je specijalno pripremljen za ovu vrstu eksperimenta. Snaga reaktora se kretala od 50 mW do 2 W. Preko periode reaktora RB odredjeni su apsorpcioni preseci za dve vrste materijala i to: domaci grafit No.3 i francuski 'Pachiney', i dve vrste aluminijuma. Ukupne greske pri ovom nacimu merenja iznose oko {+-} 5%, gde glavni deo greske nosi neodredjenost apsorpcione moci standarda (ranija metoda je dala {+-} 10 do 55% ). Poredjenjem vrednosti apsorpcionih preseka

  13. RA reactor Action plan for 1978 - Annex VI; Prilog VI - Plan rada reaktora RA za 1978. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-15

    This annex include a detailed monthly action plan of the RA reactor for 1978. It was planned that the reactor will operate at nominal and lower power levels for 158 days. The plan is made with the aim to achieve same annual neutron flux as in 1977, which is somewhat higher then the annual production in the period from 1968-1975. [Serbo-Croat] Ovaj prilog sadrzi detaljan plan rada reaktora RA za 1978. godinu. Planirano je da reaktor radi na nominalnoj snazi of 6,5 MW i na manjim snagama ukupno 158 dana. Plan je napravljen tako da se ostvari godisnja proizvodnja neutronskog fluksa u obimu koji je relaizovan 1977. godine sto je nesto vise od godisnje proizvodnje u periodu 1968-1975.

  14. RA reactor operation and maintenance, Annual report 1974; Pogon i odrzavanje reaktora RA - Izvestaj o radu u 1974. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1974-12-15

    During 1974, RA reactor was operated at nominal power for 194 days and 13 days at lower power levels. The total production was 30711 MWh which is 2.4% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 437 users. This report contains detailed data about reactor power and experiments performed in 1974. Total number of afety shutdowns was 11, of which 8 were caused by power cuts, and 3 due to human error. Maximum individual personnel exposure dose was 50% of the maximum permissible dose. There were no accidents during this year. Decontamination of surfaces was less than during previous years. About 805 m{sup 2} of surfaces and 178 objects were decontaminated. It was concluded that the successful operation in 1974 has a special significance taking into account the financial problems. [Serbo-Croat] Reaktor RA je u 1974. godini radio na nominalnoj snazi 194 dana i 13 dana na manjim snagama. Ukupni rad iznosio je 30711 MWh odnosno 1,4% vise od planiranog. Prakticno nije bilo odstupanja od plana rada. Reaktor je koriscen za ozracivanja i eksperimente za 437 korisnika. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 11 sigurnosnih zaustavljanja, od cega 8 zbog elektricnog napona i 3 usled greske osoblja. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Maksimalna doza po oveku bila je 50% manja od maksimalno dozvoljene doze. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1974. godini ima poseban znacaj kada se imaju na umu problemi finansiranja reaktora.

  15. Purification of cooling water for nuclear reactors using ion exchangers; Preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca

    Energy Technology Data Exchange (ETDEWEB)

    Ruvarac, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    Zirconiumphosphate, zirconiumoxide and natural magnetite as inorganic substances with favourable adsorption properties were the subject of investigations dealing with problems of water purification for nuclear rector cooling. Study on adsorption of impurities form reactor water to 300 deg C and 100 Atm was done by specially constructed autoclaves. On the other hand, a pre-project covering a laboratory plant for investigation of inorganic ion exchangers under real dynamic conditions is given. In order to obtain necessary data on the basis of which techno-economical analyses regarding utilization of zirconiumphosphate, zirconiumoxide and magnetite for water purification is cooling the reactors types BWR and PWR, could be performed, systematic investigations of physical and chemical properties of these substances were commenced. Equilibrium constants have been determined for adsorption processes at different pH values, as well as under various temperatures. Obtained equilibrium constants were used for calculation of thermodynamic quantities {delta}H, {delta}G and {delta}S (author) [Serbo-Croat] Cirkonijumfosfat, cirkonijumoksid i prirodni magnet, kao neorganski materijali sa pogodnim adsorpcionim osobinama, bili su predmet istrazivanja vezanih za probleme preciscavanja vode za hladjenje nuklearnih reaktora. Izucavanje adsorpcije necistoca iz reaktorske vode do 300 deg C i 100 Atm vrseno je pomocu specijalno konstruisanog autoklava, a za ispitivanje neorganskih jonoizmenjivaca pri realnim dinamickim uslovima dat je idejni projekt jednog laboratorijskog postrojenja. Za dobijanje potrebnih podataka, na osnovu kojih se mogu napraviti tehno-ekonomske analize o koriscenju cirkonijumfosfata, cirkoijumoksida i magnetita za preciscavanje vode za hladjenje reaktora tipa BWR i PWR, zapoceto je sa sistematskim proucavanjima fizickih i hemijskih osobina pomenutih materijala, odredjivane su konstante ravnoteze za procese adsorpcije pri razlicitim pH vrednostima, kao i na razlicitim

  16. Nuclear Reactor RA Safety Report, Vol. 15, Analysis of significant accidents; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 15, Analiza znacajnih akcidenata

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Power excursions of the RA reactor a mathematical model of reactor kinetic behaviour was formulated to describe power and temperature coefficients for both reactor fuel and moderator. Computer code TM-1 was written for analysis of possible reactor accidents. Power excursions caused by uncontrolled control rod removal and heavy water flow into the central vertical experimental channel were analyzed. Accidents caused by fuel elements handling were discussed including possible fuel element damage. Although the probability for uncontrolled radioactive materials release into the environment is very low, this type of accidents are analyzed as well including the impact on the personnel and the environment. A separate chapter describes analysis of the loss of flow accident. Safety analysis covers the possible damage of the outer steel Ra reactor vessel and the water screens which are part of the water biological shield. [Serbo-Croat] Radi analize dinamickog ponasanja reaktora RA u toku ekskurzije snage formulisan je matematicki model koji opisuje promene snage i temperature goriva i moderatora. Za analizu predpostavljenih akcidenata realizovan je racunarski program TM-1. Analizirane su ekskurzije snage usled nekontrolisanog izvlacenja kontrolnih sipki i punjenja centralnog vertikalnog eksperimentalnog kanala teskom vodom. Analizirani su akcidenti pri rukovanju nuklearnim gorivom ukljucujuci ostecenje nuklearnog goriva. Iako je verovatnoca za nekontrolisano rasturanje radioaktivnog materijala mala, analizirani su i ovakvi moguci akcidenti koji mogu uticati kako na osoblje reaktora tako i na okolinu. Posebno poglavlje obuhvata analizu akcidenta u slucaju prestanka cirkulacije primarnog hladioca. Analiza sigurnosti reaktora obuhvata i moguce ostecenje spoljasnjeg celicnog suda reaktora RA kao i vodenih ekrana koji su deo vodenog bioloskog stita.

  17. Results of environmental radiation monitoring and meteorology measurements (material prepared for obtaining the licence for RA reactor experimental operation); Rezultati merenja zracenja u okolini i rezultati meteoroloskih merenja (materijal pripremljen radi dobijanja dozvole za pustanje Reaktora RA u probni rad)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-10-15

    According to the demands for obtaining the licence for restarting the Ra reactor and the experimental operation this document includes the radiation monitoring measured data in the working space and environment of the RA reactor, i.e. Boris Kidric Institute. The meteorology measured data are included as well. All the measurements are performed according to the radiation protection program applied actually from the first reactor start-up at the end of 1959. [Serbo-Croat] Saglasno zahtevu za dobijanje dozvole za ponovno pustanje u probni rad reaktora RA, ovaj dokument sadrzi rezultate merenja zracenja u okolini (radnoj i zivotnoj) reaktora RA odnosno instituta 'Boris Kidric' kao i podatke o meteoroloskim merenjima. Sve merenja rade se prema programu mera zastite od zracenja koje se sprovode prakticno od prvog pustanja reaktora u rad krajem 1959. godine.

  18. RA reactor operation in 1991, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1991. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    pouzdan rad reaktora i skladu sa novim zakonskim propisima, u toku 1991. zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciju postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji instrumentacije reaktora ali njegova realizacija u 1991. godini kasni usled zastoja u isporuci opreme iz Sovjetskog saveza. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport, ali je MAAE privremeno zabranila isporuke opreme Jugoslaviji iz politickih razloga. Kontrola i odrzavanje opreme, kao i potrebni remontni radovi izvrsavani su redovno u zavisnosti od raspolozivosti rezervnih delova. Obuka postojeceg osoblja sprovodi se redovno ali nedostatak sredstava onemogucava prijem novih radnika sto bi bilo neophodno za rad u smenama i redovno odrzavanje.

  19. RA reactor operation and maintenance in 1994, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1994. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1994-12-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. The spent fuel elements used from the very beginning of reactor operation are stored in the existing pools. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988 and was fulfilled in 1990. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciji postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Zapoceti su radovi na modernizaciji, odnosno zameni instrumentacije reaktora ali njegova realizacija kasni

  20. Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - I deo, Pustanje u rad reaktora RA i merenje fizickih parametara novog jezgra reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included. [Serbo-Croat] Svrha merenja je odredjivanje neutronskog fluksa u reaktoru RA. S obzirom na uvecani broj tehnoloskih kanala of 56 na 68 u vezi projekta VISA-2, bilo je potrebno ponovo dovesti reaktora RA do kriticnosti i izvrsiti merenja karakteristika fluksa neutrona. Posebno je pripremljen 'program pustanja u pogon reaktora RA', koji je sadrzan u ovom dokumentu. Program merenja bio je podeljen na dve faze. Prva faza je merenje fluksa pre podizanju reaktora na nominalnu snagu. Slicna merenja vrsena su i na vecim snagama u drugoj fazi, pod uslovima ravnoteznog zatrovanja reaktora ksenonom, jer se tada pokazuju izvesne promene u odgovarajucim karakteristikama fluksa neutrona. Ovaj izvestaj sadrzi merene vrednosti raspodele fluksa i apsolutne vrednosti termalnih i brzih neutrona kao i kadmijumskih odnosa koji su korisceni za odredjivanje fluksa epitermalnih neutrona. Opisana je kalibracija regulacionih sipki za hladan nezatrovan reaktor.

  1. Research reactor RB, technical characteristics and experimental possibilities; Zbornik radova, Konferencija o koriscenju nuklearnih reaktora u Jugoslaviji

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Vranic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1978-05-15

    Nuclear research reactor RB tn the Nuclear Engineering Laboratory at the Institute of Nuclear Sciences 'Boris Kidric' in Vinca is the first reactor system built in Yugoslavia in 1958. In this report, the basic technical characteristics of this reactor are described, as well as the experimental possibilities it offers to the users. Its relatively simple construction and flexibility enables direct measurements of a series of physical parameters, and the absence of the biological protection shield makes it very useful for Various biological and other irradiations and dosimetric measurements Where strong neutron source is required. (author) Istrazivacki nuklearni reaktor RB u Laboratoriji za nuklearnu energetiku i tehnicku fiziku Instituta za nuklearne nauke 'Boris Kidric' u Vinci je prvi reaktorski sistem izgradjen u Jugooslaviji 1958. godine. U ovom radu opisane su osnovne tehnicke karakteristike tog reaktora, kao i mogucnosti za izvodjenje eksperimenata koje on pruza korisnicima. Njegova relativno jednostavna konstrukcija i fleksibilnost omogucavaju da se na njemu izvrse direktna merenja niza fizickih parametara, a s druge strane odsustvo bioloskog zastitnog omotaca cini ga veoma pogodnim za razna bioloska i druga ozracivanja, a takodje i dozimetrijska merenja gde se zahteva snazan izvor neutrona. (author)

  2. Experimental RA reactor operation with 80% enriched fuel - Program of experimental operation: a) Program of experimental operation with 80% enriched fuel at low power, b) contents of the experimental operation with 80% enriched fuel at higher power levels; Program probnog rada: a) Program probnog rada reaktora sa 80% obogacenim gorivom na malim snagama, b) sadrzaj programa probnog rada reaktora RA sa 80% obogacenim gorivom na vecim snagama

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Sotic, O; Skoric, M; Cupac, S; Bulovic, V; Maric, I; Marinkov, L [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-10-15

    Highly enriched (80%) uranium oxide fuel was regularly used in the mixed reactor core with the 2% enriched fuel since 1976. The most important changes related to reactor operation, in comparison with the original design project were related to reactor core fuelling schemes. At the end of 1979 reactor was shutdown due to the corrosion coating noticed on some fuel elements and due to decrease quality of the heavy water. Subsequently the Sanitary inspector of Serbia has prohibited further reactor operation. Restart of the reactor will not be a simple continuation of operation. It is indispensable to perform complete experimental program including measurements of critical parameters at different power levels for the core with fresh 80% enriched fuel. The aim of this document is to obtain working permission and its contents are in agreement with the procedure demanded by the Safety Committee of the Institute. It includes results of optimization and safety analysis for the initial reactor core. Since the permission for restart is not obtained, a separate RA reactor safety report is prepared in addition to the program for experimental operation. This report includes: detailed program for reactor experimental operation with 80% enriched fuel in the core at low power levels, and contents of the experimental operation with 80% enriched fuel in the core at higher power levels. [Serbo-Croat] Od decembra 1976. godine redovno je korisceno 80% obogaceno gorivo u mesanoj resetki reaktorskog jezgra sa 2% obogacenim gorivom. Najvece izmene na reaktoru u odnosu na originalni projekat izvrsene su u nacinu rukovanja gorivom. Krajem marta 1979. godine obustavljen je rad reaktora usled naslaga na gorivnim elementima i loseg stanja teske vode. Naknadno je izdata zabrana za rad reaktora od strane Sanitarnog inspektora SR Srbije. Ponovno pustanje reaktora u rad nece biti jednostavan nastavak rada. Neophodno je da se izvede kompletan program merenja kriticnih parametara i drugih

  3. Dinamika Kurikulum di Indonesia

    Directory of Open Access Journals (Sweden)

    M. Asri

    2017-09-01

    Full Text Available Education does not have a standard reference, which covers access for revision by the authorities. Because education continues to grow along with the rolling times. Therefore, all matters relating to education also do not have a standard reference, including educational curriculum. The curriculum is one of the important elements that has a role to advance education in Indonesia, in accordance with the ideals of the constitution. Curriculum changes are not taboo for education in developed countries of the world (such as Japan, Finlandia,  USA, etc.. Basically the dynamics of curriculum in Indonesia aims to make education in Indonesia able to compete with the developed countries in the world.

  4. Dinamika Elit Lokal Madura

    Directory of Open Access Journals (Sweden)

    Imam Zamroni

    2012-01-01

    Full Text Available The priyayi played a vital role in leading the Indonesian community during the colonial era. The same applies to Madura society. During the colonial era, power wielded by the priyayi was constricted on the basis of Madura culture and was strengthened by the bureaucratic power structure at both the village and district/ city level. This was manifested in such ways as serving as a klébun or bupati. However, the pattern of priyayi power, which was underpinned by feudalism waned, being replaced by Islamic religious leaders known as kiai. During the New Order regime, kiai in Madura played a very dominant role which was not only limited to the realm of religion, but also all aspects of life ranging from social, politics, economic, to culture. Nevertheless, with the dawn of the reformation era, economic elites have catapulted themselves to prominence, and there are growing signs that they are replacing the role which religious leaders used to play in Madura society in general and in the political domain in particular through forming shadow state as a tool used to exert control over Madura Political dynamics. This concise paper presents as discussion of ‘political fights’ among cultural, religious, bureaucratic, and economic elites in Madura.

  5. Operation, maintenance and utilization of the RA reactor, Annual report for 1980; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1980. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    During 1980 the activities of RA reactor staff was conducted in two directions: repair works and determination of the state of the existing equipment; and preparing and constructing additional equipment and completing the documentation needed to fulfill the new legal regulations. preparation of the existing equipment for future operation was finished, but construction of the additional equipment (according to the regulations) is not done at planned rate due to different reasons such as lack of budget, administration, import. This report includes a chapter devoted to the analysis of the operation difficulties that caused prohibition of reactor operation as well as difficulties in achievement of the planned activities for 1980. Data about financial issues are included as well. [Serbo-Croat] U toku 1980. godine rad OOUR-a Nuklearni reaktor RA odvijao se u dva smera: remontnim radovima i utvrdjivanju stanja postojece opreme i u pripremi i ugradnji potrebne dodatne opreme i kompletiranju neophodne dokumentacije prema novim zakonskim propisima. Priprema postojece opreme za rad je u potpunosti izvrsena, dok se projekti i ugradnja dodatne opreme (prema zakonskim obavezama) ne odvija potrebnom brzinom zbog raznih objektivnih razloga, kao nedostatak sredstava, odobrenja, uvoza. Ovaj izvestaj sadrzi poglavlje posveceno analizi teskoca u radu koje su dovele do zabrane rada reaktora, i teskoca u realizovanju plana rada u 1980. godini, ako i podatke o finansiranju projekta 'pogon, odrzavanje i eksploatacija reaktora RA'.

  6. Nuclear Reactor RA Safety Report, Vol. 16, Maximum hypothetical accident; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 16, Maksimalni hipoteticki akcident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    Fault tree analysis of the maximum hypothetical accident covers the basic elements: accident initiation, phase development phases - scheme of possible accident flow. Cause of the accident initiation is the break of primary cooling pipe, heavy water system. Loss of primary coolant causes loss of pressure in the primary circuit at the coolant input in the reactor vessel. This initiates safety protection system which should automatically shutdown the reactor. Separate chapters are devoted to: after-heat removal, coolant and moderator loss; accident effects on the reactor core, effects in the reactor building, and release of radioactive wastes. [Serbo-Croat] Sema granjanja za maksimalni hipoteticki akcident obuhvata osnovne elemente: pocetak akcidenta, faze razvoja akcidenta i stablo razvoja - sema potencijalnih akcidentnih tokova. Uzrok pocetka akcidenta je pucanje cevovoda primarnog rashladnog sistema jezgra, sistema teske vode. Gubitak primarnog hladioca izaziva pad pritiska u primarnom sistemu hladjenja na ulazu u reaktorski sud. Ovaj poremecaj pobudjuje sigurnosno kolo zastite koje automatski treba da prekine rad reaktora. Posebno je razmatrano generisanje zaostale snage, isticanje hladioca i moderatora, efekti akcidenta na jezgro, efekti u zgradi reaktora, oslobadjanje radioaktivnih produkata.

  7. Operation and maintenance of the RA reactor, RA Research reactor. Annual report 1976; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1976. godini

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    remonta do kojih je dolazilo zbog kvarova (nastalih zbog neizvrsavanja investicionog odrzavanja u toku poslednjih 6 godina) zatim nemogucnost ranijeg pocetka koriscenja novog goriva u reaktoru RA i istrosenosti rezervi starog 2% obogacenog goriva i na kraju zbog obimnog programa eksperimenata u oblasti sigurnosnih analiza vezanih za uvodjenje novog visokoobogacenog goriva u reaktor RA. Na reaktoru RA uspesno su izvrseni eksperimentalni i teorijski radovi u oblasti sigurnosnih analiza za prevodjenje reaktora RA na novo 80% obogaceno gorivo, krunisani eksperimentalnom kampanjom reaktora RA u decembru 1976, kojom se zavrsava 17-to godisnji period koriscenja 2% obogacenog goriva i otpocinje period koriscenja novog 80% obogacenog goriva u reaktoru RA. Ovaj uspeh je od izuzetnog znacaja za reaktor RA i njegove korisnike, jer ce rezultovati u povecanju osnovne proizvodnje neutronskog fluksa od 50%, pri porastu cene kostanja rada reaktora od oko 4%. Podnet je zahtev za konacno odobrenje prelaznog rezima za uvodjenje ovog goriva, kojim se postize usteda od najmanje 2 200 000 dinara. Ovim se obezbedjuje da u 1977. godini i dalje, rad reaktora ne bude vise ometan ''kriticnim'' ili drugim eksperimentima u vezi sa uvodjenjem novog goriva u reaktor. Izvrsen je obiman program remontnih i drugih radova veoma akutne prirode, koji takodje omogucuju nesmetan rad u 1977. godini. Neki od ovih radova nisu radjeni nikad ranije, a drugi nisu radjeni u proteklih 6 godina. Najzacajniji zahvati ove vrste bili su: nabavka Al-cevi od specijalne legure, izrada i montiranje tehnoloskoh kanala; obimno ispitivanje uzroka curenja spoljasnjeg suda; remont teskovodne pumpe; zamena dva vertikalna tehnoloska kanala. Nabavljena je osnovna oprema za izgradnju sistema za hladjenje u slucaju udesa. Izvrseno je opremanje vrucih komora reaktora RA.

  8. Ra reactor operation plan for 1976 - Annex 6; Prilog 6 - Plan rada reaktora RA za 1976. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    Contrary to previous years the RA reactor operation plan for 1976 is conditioned by more uncertainties than ever for the following reasons. It is planned for February to repair the components in order to eliminate the consequences of leaking from the vertical experimental channel VK-4 which happened in december 1975. Apart from this, measurements related to transfer of the core to highly enriched fuel under minimum power are foreseen to be performed in February. In April, it would be indispensable to locate the point of He gas leaking and its prevention. Core transfer to highly enriched fuel is planned for April for testing of the fuel elements under operating conditions and step by step increase of the power density up to the nominal power. Complete plan for core transfer would be available by the end of February 1976. It is planned to make-up for the mentioned delays from May-December 1976. [Serbo-Croat] Za razliku od prethodnih godina izrada plana rada reaktora RA za 1976. godinu vezana je za mnogo vise neizvesnosti nego ikada ranije iz sledecih razloga. U februaru se vrsi remont opreme i uklanjanja posledica procurivanja vertikalnog eksperimentalog kanala VK-4, koje se dogodilo decembra 1975. Sem toga u februaru se vrse merenja na minimalnim snagama u sklopu priprema za prelazak na novo gorivo. U aprilu ce biti neophodno lociranje mesta gde istice He gas kao i otklanjanje uzroka ovog curenja. Planirano je da se u aprilu ubaci novo gorivo u jezgro u cilju testiranja pod radnim uslovima uz postepeno povecanje snage do nominalne. Planirano je da se smanjeni obim rada usled navedenih uslova nadoknadi u potpunosti u periodu maj-decembar 1976.

  9. Detection of tritium in the air surrounding the heavy water reactors; Elementi detekcije tricijuma u vazduhu kod teskovodnih nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Matic-Vukmirovic, Z; Hadzisehovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1967-03-15

    This paper contains the study of the literature concerned with physical properties of the tritium, problems of detection control of the tritium level in the atmosphere in the vicinity of heavy water reactors. It is stated that a complete and efficient control of tritium activity, from radiation protection point of view can be achieved only by simultaneous triple measurements: direct measurement of tritium in the air by stationary or movable instruments; air sampling and measurement of activity by laboratory instrumentation; and measurement of tritium in the bio-material of the personnel who have inhaled air contaminated with tritium. Laboratory equipment was adapted for tritium detection in air samples. A method for measuring the specific tritium activity was developed and implemented. The tritium level and distribution in the air were measured during exchange of the fuel channel in the RA reactor. The obtained results indicate that tritium could be dangerous for the staff involved. Proucena je literatura u kojoj se tretiraju osnovne fizicke karakteristike tricijuma, kao i problemi detekcije i kontrole u vazduhu kod teskovodnih nuklearnih reaktora. Utvrdjeno je da kompletna i efikasna kontrola aktivnosti tricijuma, sa aspekta zastite od zracenja, moze biti ostvarena samo ako se vrse istovremeno trostruka merenja: merenje aktivnosti tricijuma u vazduhu direktno, prenosnim ili stacioniranim instrumentima; uzimanje uzoraka vazduha i merenje aktivnosti na laboratorijskoj aparaturi; i merenje aktivnosti tricijuma u biomaterijalu osoblja koje je udisalo vazduh kontaminiran tricijumom. Izvrsena je adaptacija laboratorijske aparature za potrebe detekcije tricijuma u uzorcima vazduha. Razradjen je i uhodan postupak merenja koncentracije aktivnosti tricijuma u uzorcima vazduha. Izvrsena su merenja i dobijeni su rezultati o nivou i raspodeli tricijuma u vazduhu pri operaciji zamene kanala sa gorivom na reaktoru RA u Vinci. Dobijeni rezultati ukazuju na opasnost koju po radno

  10. Determination of reactor parameters in a simulated RA reactor lattice by measuring the reactivity level of heavy water in D{sub 2}O moderated RB reactor; Odredjivanje reaktorskih parametara u simuliranoj resetki reaktora RA merenjem reaktivnosti nivoa teske vode u D{sub 2}O moderiranom reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Takac, S M; Markovic, H D; Dimitrijevic, Z B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1974-07-01

    Direct method for experimental determination of the neutron age {tau} in the reactor lattice is not developed. Fermi theory for determining {tau} by measuring the reactivity level of the heavy water can be applied for a limited number of reactor lattices. An attempt was made to apply this approach for a complex reactor core with side and upper reflector. As expected the obtained results were not satisfactory, and {tau} was determined by Dessauer formula which gives more realistic estimation of thermalization in the reactor cell. major discrepancies are resulting from the fact that the lower reflector was neglected. But it is possible to to determine {tau} for reactor core with reflectors by additional measurements of axial distribution and other experimental data for {tau}. This is quite tedious numerical procedure. Obtained experimental data for a number of reactor parameters are compared to the initial data of the RA reactor core showing very good agreement. [Serbo-Croat] Ekspeimentalna metoda za direktno odredjivanje starosti neutrona {tau}, u resetki reaktora do danas nije razvijena. Primenjena Fermijeova teorija za odredjivanje {tau} preko merenja reaktivnosti nivoa teske vode, ocigledno se moze koristiti samo na ogranicen spektar reaktorskih resetki. U ovom radu pokusano je da se vidi primenljivost iste u slozenom - bocno i odozdo - reflektovanom jezgru reaktora. Naravno dobijeni rezultati nisu zadovoljili, sto se i moglo ocekivati, pa je {tau} odredjen preko Dessauer-ove formule, sto daje daleko blizu sliku stvarnog stanja procesa termalizacije u celiji reaktora. Ocigledno vece neslaganje primenjene teorije dolazi od zanemarivanja donjeg reflektora u jezgru reaktora. Medjutim, dopnskim merenjem aksijalne raspodele i na osnovu ostalih eksperimentalnih podataka za {tau}, moguce je odrediti eksperimentalno reflektorski koeficijent za visestruko reflektovano jezgro reaktora, sto numericki predstavlja mukotrpan i dugotrajan rad na racunaru. Dobijeni

  11. RA reactor operation and maintenance in 1989, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1989. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    , koja je zavrsena 1989, i izradu uredjaja za rukovanje ozracenim gorivom, koji je u fazi montiranja. Planirano je da ovi poslovi budu zavrseni do sredine 1990. godine. Obuka postojeceg osoblja sprovodi se redovno ali novoprimljeni radnici obuceni za rad u pogonu nisu mogli da steknu potrebno sikustvo posto reaktor nije bio u pogonu od 1984. Nedostatak sredstava onemogucava prijem novih radnika i utice na celokupni status i aktivnosti vezane za rekonsrukciju i modernizaciju reaktora RA.

  12. Dosimetry and radiation protection at the RA reactor in 1972; Dozimetrija i zastita kod reaktora RA u 1972. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M M [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1973-07-01

    Dosimetry results collected within radiation protection of the RA reactor during this year are presented. Neutron and gamma radiation data were measured at characteristic control points. Statistical review of the total number of measurement is given as well. The report includes contents of radioactive gasses and aerosols in the air, as well as the contamination data of surfaces, clothes and uncovered body parts of the personnel. Particular accident which occurred during dismantling of the experimental channel containing the capsule with the new fuel element was analysed. This accident occurred at the RA reactor at the beginning of this year. It was found that that the maximum individual external dose was 2.2 R, and that only one individual was exposed to this dose. About 15% of the personnel was exposed to doses between 1 and 2 R, the remaining 85% was exposed to doses less than 1 R. Base on the frequency of activities undertaken in the contaminated regions, safety and control measures and expected internal exposure of the personnel, it was evaluated that the internal exposure could be neglected compared to the external exposure of the personnel. Prikazani su rezultati sakupljani u toku godine u okviru dozimetrijske kontrole i zastite kod reaktora. Dati su podaci o nivoima neutrona i gama zracenja na karakteristicnim kontrolnim mestima, kao i statisticki pregledi ukupnog broja merenja. Navedeni su rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela radnog osoblja. Analiziran je specifican akcident koji se odigrao na reaktoru pocetkom godine, pri demontazi eksperimentalnog kanala sa kapsulom novog gorivog elementa. Na kraju, izlozena je analiza ozracivanja radnog osoblja. Konstatovano je da je maksimalna individualna doza spoljasnjeg ozracivanja bila 2,2 (R), i da je ovoj dozi bilo izlozeno samo jedno lice. Oko 15% osoblja bilo je izlozeno dozama izmedju 1 i 2 (R), a ostalih 85

  13. Independent CO{sub 2} loop for cooling the samples irradiated in vertical experimental channels of the RA reactor, Vol. I; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Album I

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Pavlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-06-15

    Project 'independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor' is presented in two volumes: volume I - head of the low temperature coolant loop for reactor RA, and volume II - Outer low-temperature reactor coolant loop. Volume I includes: the design specifications for the head of the low-temperature coolant loop, technical description, thermal calculation, calculations of mechanical loads, antireactivity and activation of the components of the coolant loop head, engineering schemes and drawings, cost estimation data. [Serbo-Croat] Projekat 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', sastoji se od dva albuma: album I - Glava niskotemperaturno rashladne petlje za reaktor RA, album II - Spoljno kolo niskotemperaturne rashladne petlje za reaktora. Album I sadrzi projektni zadatak glave niskotemperaturne petlje, tehnicki opis, termicki proracun, proracun mehanickih naprezanja, antireaktivnosti i aktivacije kontrukcionih elemenata glave petlje, konstrukcione seme i crteze glave petlje, predracun.

  14. RA reactor operation and maintenance in 1990 with comparative evaluation from 1986-1990, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1990. godini, uz uporedni pregled za period 1986-1990. godina

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Vasovic, B; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The new emergency cooling system and the reconstruction of the existing ventilation system were finished in 1989, the conditions for further reactor operation were fulfilled. In the meantime new licensing regulations adopted in 1988 were not demanding the mentioned conditions for reactors operated at power less than 10MW, RA reactor power being 6.5 MW. But the reactor could not be restarted due to planned renewal of the reactor instrumentation. It is planned to exchange the complete instrumentation by the end of 1991. Training program for the staff operating and maintaining the reactor components was prepared in 1985. Reconstruction, modification and construction of components demanded new documentation needed for further safe reactor operation. New version of RA reactor safety report was finished in 1986 according to the recommendations of IAEA and licensing regulations of Yugoslavia. In 1989, new documents were written covering regulations and instructions for reactor operation. The new reactor experimental loop was designed in 1986, and constructed and tested in 1990. All the reactor components were maintained by specific reactor services. Financing of the reactor remains a permanent problem. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula 1984. godine Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Radovi na izgradnji sistema za udesno hladjenje i rekonstrukciji postojeceg sistema specijalne ventilacije zavrseni su 1989. godine. Uslovi za nastavak rada reaktora

  15. Activity of the RA Reactor Physics group in 1980 - Definition of the Operation conditions for future safe and economical RA reactor operation with 80% enriched fuel; Prilog Ia - Rad sluzbe za fiziku reaktora RA u 1980. godini - Definisanje pogonskih uslova za dalji siguran i ekonomican rad reaktora RA sa 80% obogacenim gorivom

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    During 1980. the RA reactor was not in operation. That is why this period was devoted to definition of operating conditions for further reactor operation with 80% enriched fuel. The fuel elements which were in the core at the moment of shutdown in March 1979will not be used again (388 80% enriched fuel elements, and 511 2% enriched fuel elements). The reactor will be operated only with 80% enriched fuel, staring with initiat core configuration with 440 elements on the borders gradually changing to equi;librium core with 720 fuel elements. The analyses were concerned with safety issues of future operation. [Serbo-Croat] Reaktor RA tokom 1980 godine nije radio. Zbog toga je ovaj period iskoriscen za intenzivan rad na definisanju pogonskih uslova za dalji rad reaktora sa 80% obogacenim gorivom. Gorivo sa kojim je reaktor prestao da radi marta 1979. godine (388 gorivnih elemenata 80% obogacenoh i 511 elementa 2% obogaceno) nece biti vraceno u jezgro, vec ce reaktor raditi samo sa 80% obogacenim gorivom, pocev od konfiguracije sa 440 elemenata na periferiji do ravnotezne konfiguracije sa 720 elemenata. Sve nalize su se bavile sigurnosnim aspektima rada reaktora sa visokoobogacenim gorivom u jezgru.

  16. Operation, maintenance and utilization of the RA reactor - Report on operation in 1979; Pogon, odrzavanje i eksploatacija reaktora RA, Izvestaj o radu u 1979. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M

    1979-12-15

    During 1979 the RA reactor was in operation only three months, i.e. only 24% of the planned activity was achieved. The reactor operation was interrupted in March due to problems that could not be solved by the existing equipment. Alkalinity of the heavy water resulting from the existing ammonia ions could not be removed by the existing distillation system. In addition deposition of aluminium oxyhydrate on the fuel elements was increased. This was noticed during routine control when the reactor was shutdown for refueling. The decision of the Director general of the Institute and sanitary Inspector followed, prohibiting further reactor operation. A separate chapter of this report is devoted to the analysis of the difficulties and possible solution of the problem in cooperation with the experts from different laboratories of the Institute. Aged and damaged instruments at the reactor were not exchange due to lack of budget. During the operation there were no accidents. [Serbo-Croat] U toku 1979. godine plan rada ostvaren je sa 24%, odnosno reaktor je radio samo prva tri meseca. U martu je doslo do prekida rada reaktora zbog pojave koja se nije mogla otkloniti postojecom opremom. Alkalnost teske vode, posledica prisustva amonijum jona, ne moze se odstraniti sistemom destilacije. Pored toga usled dotrajalosti opreme povecano je talozenje aluminijum oksihidroksida na gorivnim elementima. Ova pojava uocena je tokom rutinske kontrole prilikom izmene goriva a usledila je obustava rada resenjem Direktora i sanitarnog inspektora. Posebno poglavlje ovog izvestaja posveceno je analizi teskoca u radu i reaktora i resavanju nastalih problema sa gorivom u saradnji sa saradnicima drugih laboratorija Instituta. Dotrajali uredjaji i oprema nisu zamenjeni usled nedostatka sredstava. U toku rada nije bilo akcidenata.

  17. RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1986; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1986. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    In order to enable future reliable operation of the RA reactor, according to new licensing regulations, three major tasks started in 1984 were fulfilled: building of the new emergency system, reconstruction of the existing ventilation system, and reconstruction of the power supply system. Simultaneously in 1985/1986 renewal of the instrumentation and reconstruction of the system for handling and storage of the spent fuel in the reactor building have started. Design projects for these tasks are almost finished and the reconstruction of both systems is expected to be finished until 1988 and mid 1989 respectively. RA reactor Safety report was finished according to the recommendations of the IAEA. Investments in 1986 were used for 8000 kg of heavy water, maintenance of reactor systems and supply of new components, reconstruction of reactor systems. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Sa ciljem da se obezbedi pouzdan rad reaktora RA a u skladu sa zakonskim propisima, zavrsena su tri velika zahvata zapoceta 1984: izgradnja novog sistema za udesno hladjenje, rekonstrukcija postojeceg sistema za ventilaciju, i modernizacija reaktorske instrumentacije. Istovremeno tokom 1985/1986. zapoceta je modernizacija instrumentacije i rekonstrukcija sistema za rukovanje i skladistenje iskoriscenog goriva u zgradi reaktora. Projekti za navedene radove su vec zavrseni ili su u zavrsnoj fazi, a ocekuje se da ce rekonstrukcija oba sistema biti zavrsena do kraja 1988. odnosno sredine 1989. godine. Izrada izvestaja o sigurnosti reaktora RA, prema preporukama MAAE zavrsena je 1986. Investiciona ulaganja na reaktoru Ra u 1986. iskoriscena su za: nabavku 8000 kg teske vode, za investiciono odrzavanje reaktorskih sistema i nabavku opreme, za rekonstrukciju reaktorskih sistema. Ovaj izvestaj sadrzi 8 priloga koji opisuju rad reaktora, rad strucnih sluzbi i finansiranje.

  18. The training of the staff for work with radioactive materials and work on nuclear reactor in the Institute; Obuka kadrova za rukovanje radioizotopima i pogon nuklearnih reaktora u Institutu 'Boris Kidric' - Vinca

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Mladjenovic, O; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1978-05-15

    A short informational review of the activities in the 'Boris Kidric' Institute on the training courses for the use of radioactive materials and for operating nuclear reactors including power reactors. The survey of the courses is given in the enclosures. (author) Kratak informativni pregled delatnosti u IBK na kursevima za obuku kadrova u rukovanju readioaktivnim materijalima i pogonu nuklearnih reaktora, ukljucujuci reaktore snage. pregled kurseva i materijala za njih dati su u prilozima. (author)

  19. Activity of the Service for maintenance of mechanical equipment of the RA reactor - Report, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1979-12-15

    Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

  20. Activity of the Service for maintenance of mechanical structures of the RA reactor - Report for 1980, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA - Izvestaj za 1980. god

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

  1. Operation and maintenance of the RA Reactor in 1985, Part 1, Annex B - Report of the Technology Service; Deo 1 - Pogon i odrzavanje nuklearnog reaktora RA u 1985. godini - Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Vukadin, Z; Stosic, O; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    Technology service is established according to the need of unified technology control of the reactor, based on the organizational structure developed in USA, a part of which was applied at the Krsko NPP. Tasks of this service are: regular control and recording of operating reactor parameters under steady state and accidental conditions; control of chemical state of the reactor core (control of Ph values and electro conductivity of the heavy water and technical water); dosimetry parameters control and recording; safety and optimisation analyses when planning reactor core modifications; (changing the type of fuel, design of new components); cooperation with the reactor users during isotope production, activation analyses, application of neutron beams; participating in research programs; planning refueling. The most important task performed by this service was conversion of the core from 2% to 80% enriched fuel elements. A methodology for optimizing the reactor application was developed. Operation of the heavy water purification system, heavy water parameters, and operation of the gas system were controlled. Radiation and contamination levels in the working environment were measured, individual and collective doses. [Serbo-Croat] Tehnoloska sluzba uspostavljena je u skladu sa ispoljenim potrebama jedinstvene tehnoloske kontrole reaktora, oslanjajajucui se na organizacionu semu koja je razvijena u SAD, a cija je jedna varijanta primenjena na NE Krsko. Zadaci sluzbe su obavljanje sledecih zadataka: redovna kontrola i evidencija radnih parametara reaktora u redovnim i akcidentalnim uslovima; kontrola hemijskog rezima u reaktoru (kontrola PH vrednosti i elektroprovodnosti teske i tehnicke vode); kontrola i evidencija tehnicke dozimetrije; sigurnosne i optimizacione analize prilikom planiranja izmena na reaktoru (promene vrste goriva, izgradnja novih elemenata opreme); saradnja sa korisnicima reaktora prilikom prozivodnje izotopa, aktivacione analize, koriscenja

  2. Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05; Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA, Zad. 2.50.05

    Energy Technology Data Exchange (ETDEWEB)

    Stojic, M; Pavicevic, M

    1964-07-01

    This report contains the following volumes V and VI of the Project 'Independent CO{sub 2} loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels. Ovaj izvestaj sadrzi dva albuma zadatka 'Nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA', Zad. 2.50.05: Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA i Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA.

  3. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-07-01

    This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor. [Serbo-Croat] Ova publikacija obuhvata devet radova, po sledecim naslovima, a odnose se na potrebe i uslove nuklearnih reaktora u Institutu za nuklearne nauke 'Boris Kidric' tokom prethodnih dvadeset godina: radiohemija, hemija vruceg atoma, proizvodnja radioaktivnih izotopa, prerada isluzenog nuklearnog goriva, hemija transuranskih elemenata, obrada radioaktivnih otpadnih voda, preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca, istrazivanje procesa za koncentrovanje deuterijuma i hemijska dozimetrija reaktora RA.

  4. Kopūstinės kandies (Plutella xylostella L.) (Lepidoptera: Plutelidae) skraidymo ir kenkimo intensyvumo dinamika vasarinių rapsų ir gūžinių kopūstų pasėliuose

    OpenAIRE

    Vyšniauskaitė, Sigrida

    2013-01-01

    Magistrantūros studijų baigiamajame darbe pateikiami kopūstinės kandies skraidymo bei kenkimo dinamikos vasarinių rapsų ir gūžinių kopūstų pasėliuose tyrimų rezultatai. Darbo objektas – kopūstinė kandis (Plutella xylostella L.) Darbo metodai – kopūstinės kandies skraidymo dinamika tirta naudojant feromonines “delta” tipo gaudykles, 2012 m. gegužės – rugpjūčio mėnesiais, vasarinių rapsų ir ankstyvųjų bei vėlyvųjų baltagūžių kopūstų pasėliuose. Vasarinių rapsų pasėlyje buvo įrengta 12 ga...

  5. Data about operation and utilization of the RA in 1976 - Report, Annex I; Prilog I - Podaci o radu i iskoriscenosti reaktora RA u 1976. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    , nemogucnost da se predvidi tacno vreme za eksperimente u okviru (uspesno provedenog) programa prevodjenja reaktora RA na novo visokoobogaceno gorivo, posto neki od ovih eksperimenata takodje nikada ranije nije radjen. Sem toga bilo je i nepredvidjenih vecih remontnih radova zbog nepredvidjenih kvarova. Planirano je 6 izmena goriva koje su ostvarene sa zakasnjenjem. Podaci o planiranom i ostvarenom radu reaktora u 1976. godini prikazani su u ovom izvestaju kao i podaci o prekidu rada. Kracih prekida i sigurnosnih zaustavljanja je bilo 12 u ukupnom trajanju od 64 casa. Reaktor je radio na nominalnoj snazi od 6.5 MW. Akcidenata vecih razmera nije bilo, medjutim dva slucaja mogu se opisati kao akcidentalne situacije po nacinu kako su nastali. Prvi je prskanje cevi kod lezaja teskovodne pumpe a drugi kontaminacija hale i hodnika nastala prilikom pripreme masine za izmenu goriva (izlivanje teske vode). Ovaj prilog sadrzi i podatke o koriscenju eksperimentalnog prostora i iskoriscenosti reaktora.

  6. Radiation protection at the RA Reactor in 1989, Part -2, Decontamination, collection of treatment of fluid and solid radioactive waste, Annex 3; Deo 2 - Zastita od zracenja kod reaktora RA u 1989. godini, Dekontaminacija i intervencija, sakupljanje i obrada tecnih i cvrstih radioaktivnih otpadnih materija za potrebe reaktora RA - Prilog 3

    Energy Technology Data Exchange (ETDEWEB)

    Mandic, M; Vukovic, Z; Plecas, I; Knezevic, Lj; Lazic, S; Bacic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

  7. Operating Experience with the BR-5 Reactor; Experience acquise aupres du reacteur BR-5; Opyt ehkspluatatsii reaktora BR-5; Experiencia practica con el reactor BR-5

    Energy Technology Data Exchange (ETDEWEB)

    Lejpunskij, A. I.; Kazachkovskij, O. D.; Pinkhasik, M. S.; Aristarkhov, N. N.; Karpov, A. V.; Larin, E. P.; Efimov, I. A.

    1963-10-15

    remontnykh rabot na radioaktivnom zhidkometallicheskom konture reaktora na bystrykh nejtronakh BR-5. Osveshchayutsya voprosy ehkspluatatsii reaktora posle dostizheniya proektnogo 2%-nogo vygoraniya topliva pri nalichii nekotorogo narusheniya plotnosti otdel'nykh teplovydelyaptsikh ehlementov. Provoditsya opyt po razgruzke aktivnoj zony, issledovaniyu sostoyaniya i germetichnosti teplovydelyaptsikh ehlementov, dezaktivatsii oborudovaniya i truboprovodov I radioaktivnogo kontura posle dostizheniya 5% vygoraniya topliva. (author)

  8. Reactor utilization; Eksploatacija reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel.

  9. Data concerning operation and application of RA reactor in 1975, Annex 1; Prilog 1 - Podaci o radu i iskoriscenosti reaktora RA u 1975. godini

    Energy Technology Data Exchange (ETDEWEB)

    Stanic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    RA reactor was operating according to the plan for 1975 adopted in December of the previous year. It was planned for reactor to be operated at nominal power first 10-20 days each month, three following days were reserved for different power levels according to the users' demand. Four fuel exchanges were planned and fulfilled with minor delay. Data concerning planned and real operation, as well as delays from the plan and shorter interruptions are presented in tables of this Annex. It is shown that all the delays and interruptions which amounted to 104 hours were compensated. [Serbo-Croat] Reaktor RA je radio prema planu rada za 1975. godinu, nacinjenom u decembru prethodne godine. Planirano je da reaktor radi neprekidno prvih 10-20 dana u mesecu na nominalnoj snazi, tri sledeca dana je rezervisano za rad na drugim snagama zavisno od potreba korisnuka. Planirane su i 4 izmene goriva. Podaci o planiranom i ostvarenom radu kao i odstupanjima od plana i kracim prekidima u radu reaktora dati su u tabelama ovog priloga. Vidi se da su sva odstupanja i prekidi u ukupnom trajanju od 104 sata u celini nadoknadjeni.

  10. RA Research reactor Annual report 1981 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA, Deo 1 - Pogon, odrzavanje i eksploatacija reaktora u 1981. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Milosevic, M; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1981-12-15

    biggest difficulty was maintenance of reactor instrumentation. During 1981 the reactor was operated safely, there was no accident nor incident that would affect the safety of reactor personnel or the environment. The testing operation will be continued in 1982,and the experience so far shows that the program would be successfully fulfilled on the whole. [Serbo-Croat] Nuklearni reaktor RA prestao je sa radom nakon martovske kampanje 1979. godine usled pojave talozenja oksihidrata aluminijuma na kosuljicama gorivnih elemenata. Odgovarajucim resenjima Sanitarnog inspektorata Republickog sekretarijata za zdravje i socijalnu politiku SR Srbije i generalnog direktora Instituta za nuklearne nauke 'Boris Kidric', Vinca zabranjen je dalji rad reaktora sve dok se ne utvrde uzroci stvaranja oksihidrata aluminijuma i njihovog talozenja, preduzmu mere za njihovo uklanjanje i ne obezbede potrebni uslovi za normalan nastavak rada reaktora. Do kraja 1979. i tokom 1980. godine, nakon niza izvrsenih analiza i utvrdjivanja uzroka koji su doveli do zaustavljanja rada reaktora, izvrsene su sve neophodne pripreme za ponovno pustanje reaktora u rad. Polazeci od cinjenice da na reaktoru RA ne postoji sistem za hladjenje jezgra u slucaju udesa i da ne postoji adekvatan sistem za filtriranje potencijalno zagadjenog vazduha, a saglasno sa novim propisima o pustanju u rad i probnom radu nuklearnih objekata, Sanitarni inspektorat je doneo privremeno resenje kojim se dozvoljava pustanje reaktora u rad, tj. izvodjenje tzv. 'nultog eksperimenta' uz ogranicenje snage na 1% od vrednosti nominalne snage. Na osnovu dobijene dozvole, reaktor RA je ponovo pusten u rad 21. januara 1981. godine, kada je dostignuta kriticnost sa jezgrom sastavljenim iskljucivo od gorivnih elemenata od 80% obogacenog uranijuma. Eksperiment je zavrsen krajem marta, nakon cega je zatrazena dozvola za probni rad na vecim snagama i potom za rad na punoj snazi. Uzimajuci postojece stanje reaktora RA doneto je resenje kojim se

  11. Study of the absorbers and gaps influence on the reactor reactivity, IZ-061-0071-1961; Ispitivanje uticaja apsorbera i supljina na reaktivnost reaktora, IZ-061-0071-1961

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    It has been foreseen by the contract to study theoretically and experimentally the influence of the absorbers and gaps on the reactivity of the reactor. Within theoretical study it was planned to develop a method and find the approximation methods for calculations of these effects. Experimental part include development of equipment and performing the experiment at the RB reactor. Since it has not been possible to perform the experiment due to lack of heavy water, only the theoretical part of the task was completed with additional theoretical study of the VISA-1 experimental loop. This report includes the following annexes: influence of absorbers and gaps on the reactivity of the reactor, and calculation of flux depression in the VISA-1 loop. [Serbo-Croat] Ugovor predvidja teorijske i eksperimentalne radove u vezi ispitivanja uticaja apsorbera i praznina na reaktivnost reaktora. Za teorijski deo predvidjena je razrada metode i nalazenje aproksimativnih metoda za proracun ovih efekata. Eksperimentalni deo predvidja pripremu uredjaj i izvodjenje eksperimenata na reaktoru RB. S obzirom na nedostatak teske vode i nemogucnost izvodjenja eksperimenata, zadatak je obavljan samo teorijski a dodata mu je i teorijska obrada petlje VISA-1. Zadatak sadrzi sledece priloge: uticaj apsorbera i supljina na reaktivnost reaktora i proracun depresije fluksa u petlji VISA-1.

  12. Opinion about difficulties of RA reactor operation under conditions of high activity of the heavy water system - Annex 2; Prilog 2 - Misljenje o teskocama eksploatacije reaktora RA u uslovima visoke aktivnosti teskovodnog sistema

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    It was concluded that reactor the reactor operation is very dangerous for the reactor installation as well as safety of the staff under conditions of heavy water increased activity. Two fundamental arguments in favour of this conclusion are: insufficient possibility of reactor components inspection during maintenance and operation in the future period; difficulties in prevention of accidents that could occur is equally dangerous for the reactor facility and the environment. Cleaning and decontamination of the complete heavy water system is needed before the reactor operation starts in order to avoid possible failures or accidental events. [Serbo-Croat] Zakljuceno je da je eksploatacija reakora u uslovima postojece aktivnosti teskovodnog sistema veoma opasna po sam reaktor i po personal. Dva osnovna razloga u prilog ovog zakljucka su: nedovoljna mogucnost kontrole ispravnosti svih elemenata reaktora u toku remonta i ekspolatacije u predstojecem periodu; teskoca borbe sa udesima, koji bi se eventualno dogodili podjednako je opasna po instalaciju i okolinu. Pre no sto se nastavi sa daljom ekspolatacijom reaktora potrebno ciscenje, dekontaminacija sistema teske vode kako bi se izbegla moguca ostecenja ili akcidentalne situacije.

  13. Radiation protection at the RA Reactor in 1997, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1997. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, R; Kalinic, S [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1997. Actions in 1997 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. After adopting the procedures, detailed preparations, and purchasing the needed equipment, the first phase of remedial action, the removal of the sludge from the bottom of the spent fuel storage pool was started in September 1997. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni

  14. Radiation protection at the RA Reactor in 1996, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Prilog 1 - Zastita od zracenja kod reaktora RA u 1996. godini - Deo 2 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, R; Kalinic, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1996-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. Previously initiated actions concerning future decision on the status of the RA reactor were continued during 1996. Actions in 1996 were focused to detailed analysis of the conditions of storing the spent fuel in the storage pools and preparing the documentation for decision making about the methods for the improvement of the mentioned conditions. It is stated that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. U 1996. godini nastavljena je akcija zapoceta prethodne

  15. Experimental operation of the RA reactor with 4 fuel channels containing 80% enriched dispersion fuel - Operational Report; Radni izvestaj - Eksperimentalna kampanja reaktora RA sa 4 kanala sa 80% obogacenim disperzionim gorivom

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Milosevic, M; Cupac, S; Kozomara, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    usmerene su na prelazni rezim na bazi parcijalnog uvodjenja novog goriva u reaktor, tj. na reaktorsko jezgro sa dve vrste goriva. Cilj ovih analiza i priprema jeste obezbedjivanje svih uslova za siguran rad reaktora RA u prelaznom rezimu. Ove analize i pripreme su uglavnom kompletirane. Medjutim, nedostaje jos eksperimentalni podatak o utrosku goriva za odredjeni rad reaktora na nominalnoj snazi tj. o dnevnom padu ugradjenog viska reaktivnosti. Ovaj podatak neophodan je kod planiranja izmena goriva (kolicine svezeg goriva i ucestanosti izmena) u prelaznom rezimu. Do ovog podatka moze se doci samo putem normalnog rada reaktora u toku vremena znatno duzeg od vremena u kome se uspostavlja ravnotezno zatrovanje, kao vremena izmedju dva prelivanja D{sub 2}O kondenzata u aktivnu zonu RA. U tom smislu je planirana desetodnevna eksperimentalna kampanja u decembru 1976. U ovom izvestaju izlozeni su oni najznacajniji rezultati sigurnosnih analiza i priprema koji ukazuju na potpunu sigurnost rada reaktora tokom ove eksperimentalne kampanje, sa aspekta postovanja ogranicenja najvaznijih parametara koji uticu na sigurnost reaktora, kao sto su reaktivnost, toplotna i temperaturska ogranicenja za gorivo i za reaktor, itd. Podaci koji budu dobijeni iz ove eksperimentalne kampanje su od znacaja jer ce se na osnovu njih konacno definisati dalji protok svezeg novog goriva, tokom prelaznog rezima (author)

  16. Dosimetry and technical radiation protection at the RA in 1974; Dozimetrija i tehnicka zastita od zracenja kod reaktora RA u 1974. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1975-01-15

    This report include the analysis of the dosimetry and technical radiation protection results collected during 1974. The first part shows the data about the fundamental exposure to radiation and the statistical review of the total number of measurements. The following are included as well: measured values of radioactive gases and aerosol contents in air; contamination level of surfaces, clothes and uncovered parts of the staff bodies. Analysis of the personnel exposure is presented in the second part of the report. It was stated that the maximum individual external dose was 2.13R, and the exposure dose was 1/5 lower than of the annual dose limit for 90% of the exposed personnel. It was estimated that that the internal contamination is negligible compared to the external contamination. This statement was based on the frequency of tasks in the contaminated zones, undertaken control and protection measures, as well as on the evaluation of the expected internal contamination. Comparative evaluation of the occupational exposures is given for the past five years. This showed that the exposure in 1974 was lower than during previous years. The third part of the report covers the numerical data about the quantity of the collected radioactive waste, total size of contaminated and decontaminated surfaces and number of decontaminated objects. A brief analysis of the accidents occurred during this year under regular reactor operating conditions, maintenance and repair is given at the end. It was stated that there has been no accident that would cause exposure higher than the prescribed limits or any significant contamination of the working space or environment. Maximum individual dose was 1.4 R, and contamination of the uncovered parts of the bodies was about 6 MDNK (maximum permissible contamination level) [Serbo-Croat] U ovom radu prikazani su rezultati sakupljeni u toku godine u okviru dozimetrijske kontrole i tehnicke zastite kod reaktora. U prvom delu rada izlozeni su

  17. Dinamika Usaha Pengrajin Reog Ponorogo

    Directory of Open Access Journals (Sweden)

    Naning Kristiyana

    2017-06-01

    Full Text Available The prospect of Reog handicrafts is increasingly encouraging because Reog is now one of the mainstays of national and even international tourism of Ponorogo. This study aims to know the business conditions of Reog Ponorogo’s craftsmen and the problems faced by them. Respondents of this study are Reog Craftsmen in Ponorogo. This research uses quantitative descriptive research method. The sample in this study is the population because the population is less than 100 that is 31 craftsmen. The data were collected by questionnaire. Data analysis in the field using descriptive and quantitative descriptive explorative format. The result of the research shows that the business of reog craft is mostly done downhill. Craftsmen have pioneered the business since about 10-20 years ago. Making reog craft does not require higher education. This is proved by the largest number of artisans have minimum education of elementary school. The total workforce of each craftsman <20 workers. The level of education of the largest number of labor is junior high school. Productions made monthly can achieve sales targets because most of the production based on orders from retailers. The market share of handicrafts reog to foreign countries such as Malaysia, Korea, America, and others. The main problem of the craftsmen is the difficulty in obtaining raw materials such as peacock, tiger skin, cow skin, cow's tail, ponytail and high price of raw materials, capital problem.

  18. DINAMIKA USAHA PENGRAJIN REOG PONOROGO

    Directory of Open Access Journals (Sweden)

    Naning Kristiyana

    2017-05-01

    Full Text Available The prospect of Reog's handicrafts is more exciting because Reog's art is now one of the mainstays of Ponorogo tourism in national and even international scale. This study aims: Knowing the business conditions of craftsmen Reog Ponorogo, and Know the problems faced by the craftsmen Reog Ponorogo. Respondents of this study are Reog Craftsmen in Ponorogo. This research uses Quantitative Descriptive research method. The sample in this study population because the population is less than 100 ie 31 craftsmen. The data were collected by questionnaire. Data analysis in the field using descriptive and quantitative descriptive explorative format. The result of the research is known that the business of reog craft is mostly done downhill. Craftsmen have pioneered the business since about 10-20 years ago. Making a reog craft does not require higher education proved the largest number of artisans have a minimum of elementary education. The total workforce of each craftsman <20 workers. The highest level of labor education is SMP.Productions made monthly can reach the sales target because most of the production is based on orders from retailers. The market share of craft reog to foreign countries such as Malaysia, Korea, America, and others. The main problem of craftsmen is the difficulty in obtaining raw materials such as peacock, tiger skin, cow leather, cow tail, horse tail and high price of raw materials, capital problem.

  19. DINAMIKA DEPRESI PADA PENDERITA AIDS

    Directory of Open Access Journals (Sweden)

    Imadduddin Parhani

    2016-12-01

    Full Text Available Depression is a major mental health problem today. This is very important because people with depression productivity will decrease and this is very bad for a society and a country that is building. There are at least four chronic diseases that allow the depression sufferer, one of which is HIV and AIDS. Given the uncertainty over the fate of people living with HIV and AIDS had the potential to give rise to feelings of anxiety and depression. Someone who is infected with HIV and AIDS will be overcome by a feeling of dying, guilt about the behavior that makes infection, and taste sequestered by others.The cause of depression in people with HIV and AIDS by cognitive approach that is the mindset of people who deviate from the pattern of the logical interpretation or misinterprets an event or events, focusing on the negative situations that happened to him, and hope that pessimistic and negative about the future. Symptoms are raised is their depressed mood, decreased interest or pleasure in absolute terms, average of worthlessness or excessive guilt, thoughts of death. Response or reaction that occurs is refused, angry, and depressed when he learned he was infected with HIV and AIDS, and eventually be able to accept his situation. Efforts are being made to reduce depression are manifold. One is through social support to colleagues who also have HIV and AIDS.

  20. Dinamika Perjuangan Muslim di Palestina

    OpenAIRE

    Rosyid, Moh

    2015-01-01

    Upaya negara Palestina untuk mewujudkan kedaulatannya sebagai negara mendapat tantangan oleh arogansi Israel yang ingin menganeksasinya dengan dalih 'ajaran' dan keyakinannya. Usaha optimal Israel mencaplok wilayah negara Israel dirancang dengan langkah yang rapi, yakni sejak munculnya protokol zionis hingga eksisnya negara Israel. Sejak itu, konflik yang diderita negara Palestina membuat negaranya makin miskin karena energinya tersedot untuk memperjuangkan kedaulatan, di tengah upaya yang ha...

  1. DINAMIKA STUDI ISLAM DI BARAT

    Directory of Open Access Journals (Sweden)

    M Rusydi

    2016-04-01

    Full Text Available The following writing shows the historicity of Islamic studies in the West. It is important to reflect, at least as a comparison for our Islamic studies in Indonesia. Initially, Islamic studies in the West were looked unfairly. Islam was considered a fragment of Jews and Christian tradition. Thus, Islamic studies were positioned as a subunit of Christian studies. At this condition, Islamic studies tended to be colonized by West scholars’ ideology. However, in 1980, Islamic studies began to be looked fairly in the West. Funded by National Endowment for the Humanities, University of Arizona for the first time held an international symposium on Islam and Religious Studies. In this symposium, Islam was considered equally with Christian. Therefore, the research on it was not only about Islam as religion but also as civilization. It was indicated by various approaches to Islam such as philology, social and humanities approaches. Today, Islamic studies develop intensively with the contemporary approaches called post-orientalism which is based on post-colonialism, post-structuralism, multiculturalism, and critical theory.

  2. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1983; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1983. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Raickovic, N; Radivojevic, J; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1983-12-15

    After regular shutdown in November 1982, inspection of the fuel elements from the RA reactor core which was done from December 1982 - February 1983 has shown that there are deposits of aluminium oxides on the surface of the fuel cladding. After restart The RA reactor was operated at power levels from 1.8 - 2 MW, with 80% enriched uranium dioxide fuel elements. It was found that there was no corrosion of the fuel element cladding and that it was not possible to find the cause of surface deposition on the cladding surfaces without further operation. It was decided to purify the heavy water permanently during operation and to increase the heavy water flow by operating two pumps. This procedure was adopted in order to decrease the possibility of corrosion. The Safety committee of the Institute has approved this procedure for operating the RA reactor in 1983. The core was made of 80% enriched fuel, critical experiments were done until June 1983, and after that the operation was continued at power levels up to 2 MW. [Serbo-Croat] Pregledom nuklearnog goriva iz tehnoloskih kanala reaktora RA koji je izvrsen u periodu decembear 1982-feburuar 1983. godine nakon zaustavljanja reaktora po isteku novembarske kampanje 1982. godine, ustanovljeno je da ponovo dolazi do stvaranja taloga u obliku hidratisanih oksida aluminiuma na kosuljicama gorivnih elemenata. Nakon ponovnog pustanja u rad, reaktor je do novembra 1981. godine neprekidno bio u pogonu na snagama 1,8 - 2 MW. Jezgro je bilo formirano iskljucivo sa od gorivnih elemenata sa 80% obogacenim uran dioksidom. Utvrdjeno je da kosuljica gorivnog elementa nije korodirala, i da se bez nastval rada ne moze utvrditi uzrok pojave taloga na povrsini kosuljice. Da bi se mogucnost korozije aluminjumskih komponenti u primarnom kolu raktora svela na sto manju meru odluceno je da se vrsi neprekidno preciscavanje teske vode i da se istovremeno poveca protok teske vode radom dve pumpe, Komitet za sigurnost Instituta odobrio je ovakav nacin

  3. The physics design of EBR-II; Physique du reacteur EBR-II; Fizicheskij raschet ehksperimental'nogo reaktora - razmnozhitelya EVR-II; Aspectos fisicos del reactor EBR-II

    Energy Technology Data Exchange (ETDEWEB)

    Loewenstein, W. B. [Argonne National Laboratory, Argonne, IL (United States)

    1962-03-15

    hexagonal del reactor los datos obtenidos en geometrias simples idealizadas, analiticas o experimentales. Se compara el rendimiento nuclear, incluso el de reproduccion, del reactor real con el del modelo teorico y se describen las variaciones a largo plazo de la reactividad y de la generacion de energia en la envoltura fertil, refiriendolas a los ciclos propuestos para el combustible y la envoltura fertil. La memoria formula consideraciones sobre la seguridad estudiando en particular la introduccion de indices de reactividad normales y anormales y la consecuencia de supuestos efectos de reactividad, que se basan en el comportamiento fisico de la aleacion combustible y de la estructura del reactor, asi como en la extrapolacion al sistema del EBR-II de los experimentos realizados con el conjunto TREAT. Por ultimo, examina el problema de la fusion del cuerpo del reactor EBR-II. (author) [Russian] Vychisleniya statisticheskogo, dinamicheskogo i dlitel'nogo rezhima reaktivnosti ehksperimental'nog o reaktora-razmnozhitel ya EBR-II dayutsya sovmestno s rezul'tatami i analizom ehksperimentov na reaktore EBR-II po dostizheniyu kritichnosti v sukhom sostoyanii i otdel'nykh ehksperimentov na reaktore ZPR-III. Osoboe vnimanie udelyaetsya problemam fizicheskogo rascheta reaktora, kotorye voznikayut posle opredeleniya printsipial'noj skhemy i do sooruzheniya ili vvoda reaktora v ehkspluatatsiyu. Opisyvayutsya analiz bezopasnosti reaktora i soobrazheniya po otsenke opasnostej, a takzheikh vliyanie na raschet reaktora. V doklade opisyvaetsya sposob ispol'zovaniya modeli EBR-II na osnovanii poluchennykh na reaktore ZPR-III dannykh, a takzhe dannykh sukhoj kritichnosti reaktora EBR-II. EHti ehksperimenty, ikh analiz i teoreticheskie vykladki yavlyayutsya osnovoj dlya opredeleniya fizicheskogo povedeniya reaktornoj sistemy. Bolee podrobno issleduyutsya ogranicheniya, prisushchie primeneniyu ehksperimental'nykh dannykh k rassmatrivaemo j ehnergeticheskoj reaktornoj sisteme. Syuda otnosyatsya

  4. Theoretical analysis of nuclear reactors (Phase I), I-V, Part V, Determining the fine flux distribution; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, V Deo, Odredjivanje fine raspodele fluksa

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Mono energetic neutron transport equation was solved by Carlson numerical method in cylindrical geometry. S{sub n} code was developed for the digital computer ZUSE Z23. Neutron flux distribution was determined for the RA reactor cell by applying S{sub 4} approximation. Reactor cell was treated as D{sub 2}O-U-D{sub 2}O system. Time of iteration was 185 s. Resena je transportna monoenergetska jednacina numerickom metodom Carlsona u cilindricnoj geometriji. Razvijanje S{sub n} kod za digitalnu masinu ZUSE-Z 23. Odredjena je raspodela fluksa u celiji reaktora RA S{sub 4} aproksimacijom. Celija je tretirana kao D{sub 2}O-U-D{sub 2}O. Vreme iteracije je 185 sec (author)

  5. Safety analysis for testing operation of the RA reactor in the Boris Kidric Institute, Vinca; Analiza sigurnosti rada reaktora 'RA' za probni rad u Institutu za nuklearne nauke 'Boris Kidric' - Vinca

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-09-15

    This safety report covers detailed description of the RA reactor core, reactor components, coolant system, control system, safety system, reactor building including site characteristics. A separate chapter is devoted to radiation protection and radioactive waste management. Organizational structure od the reactor staff as well as training program are included. The last chapter includes detailed emergency plans for three accidents classified in three categories. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis reaktora RA, sistema za hladjenje, kontolno-sigurnosnog sistema, elektricnog sistema, zgrade sa instalacijama, ukljucujuci karakteristike lokacije. Posebno poglavlje opisuje sistem zastite od zracenja i rukovanje radioaktivnim otpadom. Opisana je organizacija rada i program obuke osoblja. Poslednje poglavlje sadrzi detaljan plan mera za slucaj udesa klasifikovanih u tri kategorije.

  6. Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor - Annex 16; Prilog 16 - Merenje temperature uzoraka reaktorskih materijala ozracivanih u gorivnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M; Djalovic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Reactor materials as graphite, stainless steel, magnox, zirconium alloys, etc. were exposed to fast neutron flux inside the fuel elements specially adapted for this purpose. Samples in the form ampoules were placed in capsules inside the fuel channels and cooled by heavy water which cools the fuel elements. In order to monitor the samples temperature 42 thermocouples were placed in the samples. That was necessary for reactor safety reasons and for further interpretation of measured results. Temperature monitoring was done continuously by multichannel milivoltmeters. This paper describes the technique of introducing the thermocouples, compensation instruments, control of the cold ends and adaptation of the instruments for precision (0.5%) temperature measurement in the range 30 deg - 130 deg C; 30 deg - 280 deg C and 30 deg - 80 deg C. Ozracivanje uzoraka materijala za izgradnju reaktora kao sto su grafit, nerdjajuci celik, magnox, legure cirkonijuma, aluminijuma itd. vrseno je u fluksu brzih neutrona unutar samih gorivnih elemenata koji su specijalno adaptirani za ovu svrhu. Uzorci u vidu ampula smesteni su u kapsulu od aluminijuma i postavljeni unutar kanala gde su hladjeni cirkulacijom teske vode koja hladi same gorivne elemente. U cilju kontrole temperature uzoraka radi bezbednosti samog reaktora, kao i radi kasnije interpretacije rezultata ispitivanja radijacionog ostecenja materijala, ugradjeno je 42 termopara u uzorke. Kontrola temperature je vrsena kontinualno visekanalnim registratorima. U radu je prikazana tehnika izvodjenja termoparova, kompenzacionih vodova, kontrola hladnih krajeva i prilagodjenje instrumentacije za merenje i registraciju temperature sa tacnoscu 0,5% u opsezima 30 deg - 130 deg C; 30 deg - 280 deg C i 30 deg - 80 deg C (author)

  7. Safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. VI; Album VI: Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

    First part of the safety report for the Independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels contains descriptions of the independent CO{sub 2} loop, system for regulation, measurement and control od the loop parameters, description of the dosimetry system, and the plan for testing the experimental device before start-up. Second part of this analysis describes the influence of of the experimental device on the reactor operation under steady state conditions as follows: influence of the head of the independent coolant loop on the reactivity of the reactor core and influence on the reactor temperature coefficient. Third part of the report includes the analysis of possible accidents during operation of the independent CO{sub 2} coolant loop in the reactor. Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA sadrzi u prvom delu: opis nezavisnog kola CO{sub 2}, sistema za regulaciju, merenje i kontrolu parametara nezavisnog kola, sistema dozimetrijske kontrole i plan ispitivanja eksperimentalnih uredjaja pre pustanja u rad. Drugi deo ove analize obuhvata uticaj eksperimentalnog uredjaja na reaktor u normalnom rezimu rada i to: uticaj glave petlje nezavisnog kola CO{sub 2} za hladjenje uzoraka na reaktivnost reaktora i uticaj uredjaja na temperaturni koeficijent reaktora. Treci deo sadrzi analizu mogucih akcidenata u toku rada nezavisnog kola CO{sub 2} u reaktoru.

  8. Power Reactor Design at Zero Power; Etudes de Reacteurs de Puissance, au Moyen de Machines de Puissance Zero; Konstruktsiya ehnergeticheskogo reaktora nulevoj moshchnosti; Diseno de Reactores Generadores con Ayuda de Reactores de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Redman, W. C.; Plumlee, K. E.; Baird, Q. L. [Argonne National Laboratory, Argonne, IL (United States)

    1964-02-15

    revela que el Laboratorio de Argonne ha venido basindose ampliamente en los sistemas exponenciales y criticos para llevar a cabo sus trabajos en materia de estudio de reactores. Los autores sugieren el papel futuro de estos sistemas al resumir brevemente los programas de trabajo, en curso de ejecucion o en proyecto, mediante los reactores de potencia nula que actualmente existen en Argonne y los que ese Laboratorio proyecta construit. (author) [Russian] Rjalis- sledovatel'skih reaktorov dlja central'nyh jelektrostancij, reaktorov v kachestve dvigate- lej, reaktorov dlja proizvodstva izotopov i ispytatel'nyh reaktorov byl issledovan na Argonskih reaktorah nulevoj moshhnosti, a svjazannye jeksponencial'nye i chisto kriticheskie sborki pozvolili poluchit' osnovnye dannye. Dlja togo, chtoby dat' nagljadnoe predstavle- nie o poslednih jeksperimentah i prodemonstrirovat' bol'shoe raznoobrazie dannyh o kon- strukcii reaktora, kotorye mozhno poluchit' v sistemah s maloj plotnost'ju nejtronnogo poto- ka, rassmatrivajutsja sledujushhie jeksperimental'nye programmy: 1. Izuchenie svojstv torievo-uranovogo topliva v tjazheloj vode s osobym uporom na trebova- nija, pred{sup j}avljaemye k konstrukcii vtoroj aktivnoj zony dlja Argonskogo jeksperimental'- nogo kipjashhego reaktora. 2. Maket predpologaemogo issledovatel'skogo reaktora s vysokoj plotnost'ju nejtronnogo potoka dlja podtverzhdenija raschetov konstrukcii, vybora optimal'noj geometrii i ocenki vlijanija vygoranija topliva. 3. Opredelenie harakteristik raspredelenija jenergii i vlijanija na reaktivnost' zatoplenija toplivnogo jelementa dlja kombinirovannyh ispytanij kipjashhego reaktora s peregrevom. 4. Konstrukcija aktivnoj zony proizvodjashhego plutonij reaktora-razmnozhitelja na bystryh nejtronah na urane - 235 s natrievym ohlazhdeniem kak pervoj zagruzki dlja Argonskogo jeksperimental'nogo reaktora-razmnozhitelja II. 5. Issledovanie harakteristik reaktora s vzaimodejstvujushhimi zonami na teplovyh i byst- ryh nejtronah. Pri

  9. Radiation protection at the RA Reactor in 1990, Part -2, Control of the working environment, dosimetry and radiation protection, Annex 1; Deo - 2, Zastita od zracenja kod reaktora RA u 1990. godini, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Raicevic, J; Bjelanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 2.5 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1990 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioaktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 2,5 mSv a da su pojedinacna izlaganja radnog

  10. Radiation protection at the RA Reactor in 1989, Part -2, Annex 1, Control of the working environment, dosimetry and radiation protection; Zastita od zracenja kod reaktora RA u 1989. godini - Deo 2, Prilog 1 - Kontrola radne sredine - dozimetrija i tehnicka zastita kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Glodic, S; Raicevic, J; Pavlovic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. It was found that the individual dose from external exposure during previous ten months was less than 4.0 mSv, and that single exposures of the staff was less than 1/10 of the annual dose limit. Comparison with the data for previous five years shows that the exposures in 1989 were lower than during past five years. It is stated that there has been no accident that would result in significant surface contamination. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. U trecem delu izvestaja navedeni su osnovni podaci o ukupnim kolicinama sakupljenog radioaktivnog materijala, ukupnoj velicini kontaminiranih i dekontaminiranih povrsina i broju dekontaminiranih predmeta. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila manja od 4,0 mSv a da su pojedinacna izlaganja radnog

  11. Radiation protection at the RA reactor in 1987, Part I: Control of the working environment - dosimetry and radiation protection at the RA reactor, Annex 1; Prilog 1, Zastita od zracenja kod reaktora RA u 1987. godini - Deo 1: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Laboratory for radiation and environmental proetecion, Beograd (Serbia and Montenegro)

    1987-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 6.0 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1987 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 6,0 mSv, a da su pojadinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz kojih

  12. Radiation protection at the RA Reactor in 1985, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Zastita od zracenja kod reaktora RA u 1985. godini - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 8.2 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1985. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 8.2 mSv, a da su pojedinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

  13. RA Research reactor, Part 1, Operation and maintenance of the RA nuclear reactor for 1988; Istrazivacki nuklearni reaktor RA, deo 1, pogon i odrzavanje nukleanog reaktora RA u 1988. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    According to the action plan for 1988, operation of the RA reactor should have been restarted in October, but the operating license was not obtained. Control and maintenance of the reactor components was done regularly and efficiently dependent on the availability of the spare parts. The major difficulty was maintenance of the reactor instrumentation. Period of the reactor shutdown was used for repair of the heavy water pumps in the primary coolant loop. With the aim to ensure future safe and reliable reactor operation, action were started concerning renewal of the reactor instrumentation. Design project was done by the soviet company Atomenergoeksport. The contract for constructing this equipment was signed, and it is planned that the equipment will be delivered by the end of 1990. In order to increase the space for storage of the irradiated fuel elements and its more efficient usage, projects were started concerned with reconstruction of the existing fuel handling equipment, increase of the storage space and purification of the water in the fuel storage pools. These projects are scheduled to be finished in mid 1989. This report includes 8 annexes concerning reactor operation, activities of services and financial issues. [Serbo-Croat] Prema planu za 1988. godinu, reaktor RA je trebalo da pusten u rad oktobra meseca, medjutim nije dobio dozvolu za nastavak rada. Kontrola i odrzavanje opreme izvrsavani su redovno i efikasno, u granicama koje su diktirane raspolozivoscu repromaterijala i rezervnih delova. Najvecu poteskocu pricinjavalo je odrzavanje instrumentacije. Period stajanja u 1988. godini iskoriscen je za remont teskovodnih pumpi u primarnom kolu hladjenja. U cilju povecanja pouzdanosti rada reaktora zapoceti su radovi na modernizaciji instrumentacije, projekat je izradjen u sovjetskoj organizaciji Atomenergoeksport, sklopljen je ugovor o izradi ove opreme koja bi trebalo da bude isporucena do kraja 1990. U cilju povecanja prostora za skladistenje ozracenog

  14. Calculated activities of some isotopes in the RA reactor highly enriched fuel significant for possible environmental contamination - Operational report; Radni izvestaj - Proracun aktivnosti nekih izotopa u visokoobogacenom uranskom gorivu reaktora RA, znacajnih sa gledista moguce kontaminacije okoline

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V; Martinc, R; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This report contains calculation basis and obtained results of activities for three groups of isotopes in the RA reactor 80% enriched fuel element. The following isotopes are included: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. It was estimated that the fuel is exposed to mean neutron flux. The periodicity of reactor operation is taken into account. Calculation results are given dependent on the time of exposure. These results are to be used as source data for Ra reactor safety analyses. [Serbo-Croat] Izlozene su osnove i prikazani su rezultati izvedenog proracuna aktivnosti tri grupe izotopa u gorivnom elementu reaktora RA sa 80% obogacenim uranom - 235. Obuhvaceni su: 1) {sup 85m}Kr, {sup 87}Kr, {sup 88}Kr, {sup 131}J, {sup 132}J, {sup 133}J, {sup 134}J, {sup 135}J, {sup 133}Xe, {sup 138}Xe i {sup 138}Cs, zatim, 2) {sup 89}Sr, {sup 90}Sr, {sup 91}Sr, {sup 92}Sr, {sup 95}Zr, {sup 97}Zr, {sup 103}Ru, {sup 105}Ru, {sup 106}Ru, {sup 129m}Te, {sup 134}Cs, {sup 137}Cs, {sup 140}Ba, {sup 144}Ce, kao i 3) {sup 238}Pu, {sup 239}Pu i {sup 240}Pu. Pretpostavljeno je da se gorivo ozracuje na srednjem fluksu neutrona, a periodicnost rada reaktora je uvazavana. Rezultati proracuna, dati u numerickom obliku, sistematizovani su kao funkcija toka vremena ozracivanja goriva. Ovi rezultati bice korisceni kao izvorni podaci kod izrade sigurnosnih analiza za reaktor RA (author)

  15. Nondestructive analysis of RA reactor fuel burnup, Program for burnup calculation base on relative yield of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel; Nedestruktivno odredjivanje izgaranja goriva reaktora RA, Program za izracunavanje izgaranja na osnovu relativne zastupljenosti {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V F [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1971-07-01

    Burnup of low enriched metal uranium fuel of the RA reactor is described by two chain reactions. Energy balance and material changes in the fuel are described by systems of differential equations. Numerical integration of these equations is base on the the reactor operation data. Neutron flux and percent of Uranium-235 or more frequently yield of epithermal neutrons in the neutron flux, is determined by iteration from the measured contents of {sup 106}Ru, {sup 134}Cs and {sup 137}Cs in the irradiated fuel. The computer program was written in FORTRAN-IV. Burnup is calculated by using the measured activities of fission products. Burnup results are absolute values. Sagorevanje maloobogacenog uranskog metalnog goriva reaktora RA je opisano dvema lancanim reakcijama. Energetski bilans i materijalne promene u gorivu su opisane sistemima diferencijalnih jednacina. Numericka integracija jednacina se vrsi na osnovu podataka u dinamici rada reaktora. Fluks reaktorskih neutrona i procenat urana-235 ili ucesce epitermalnih neutrona u fluksu, odredjuje se iterativno na osnovu izmerenog sadrzaja {sup 106}Ru, {sup 134}Cs i {sup 137}Cs u ozracenom gorivu. Program je napisan u FORTRAN-u IV u jednom bloku, bez podprograma. Izracunavanje izgaranja je zasnovano na izmerenim kolicnicima aktivnosti fisionih produkata. Rezultati izgaranja imaju apsolutni karakter (author)

  16. Theoretical analysis of nuclear reactors (Phase II), I-V, Part V, Determining the fine neutron flux distribution by Pn method; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, V Deo, Odredjivanje fine raspodele fluksa Pn metodom

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    Expression for spherical harmonic moments were applied. They were obtained by spherical harmonics expansion of monoenergetic transport equation. This report presents the procedure for calculating the neutron flux distribution in the nine-zone reactor cell of the RA reactor in Vinca. The procedure was modelled for digital computer ZUSE Z-23 by expansion of the diagram of the automated P{sub 3} code, which is adequate for P{sub n} code with minor changes. The needed subroutines were developed. The most important ones were those for modified first and second order Bessel functions of n-th order. Computer Z-23 was operating only 15 hours during three months, and thus only the subroutines for modified Bessel functions could be tested and the obtained results were excellent. For the mentioned reason the neutron flux distribution will be calculated in the forthcoming period. Koriscen je izraz za svernoharmonicne momente koji se dobija razvijanjem monoenergetske transportne jednacine u sverne harmonike. Dat je postupak za odredjivanje raspodele neutronskog fluksa u devet medijalnoj celiji reaktora RA u Vinci. Gornji postupak je logicki organizovan na digitalnoj masini ZUSE Z-23 razvijanjem tekuceg dijagrama automatskog P{sub 3} koda, koji sa malim izmenama odgovara Pn kodu. Razvijene su potrebne osnovne subrutine, medju kojima su najznacajnije one za modificirane Beselove funkcije prve i druge vrste n - tog reda. Masina ZUSE Z-23 bila je u radu svega 15 zasova u toku tri meseca, te sam stigao da testiram samo subrutine za modificirane Beselove funkcije koje su dale odlicne rezultate. Iz ovoga razloga nije se mogla dobiti trazena raspodela fluksa. To ce biti ucinjeno u narednom periodu posto cemo moci koristiti masinu Z-23 (author)

  17. Dinamika Akad dalam Transaksi Ekonomi Syariah

    Directory of Open Access Journals (Sweden)

    Rahmawati Rahmawati

    2016-02-01

    Full Text Available Transaction is one of law products (sharia and jurisprudence that has a lot of development in accordance to human dynamics of the classical period to the present day. In the future, it will always envolve to follow the dynamics of economic system by maintaining the substance in the middle of economical global contentions. Transaction becomes one of Islamic and sharia (revelation product law to ensure human welfare. As a norm, transactions in Islamic finance or Islamic economics can be fused into the world economic system. This can be a filtering and balancing for the economical system that runs stable towards the benefit of all parties.DOI: 10.15408/aiq.v3i1.2207

  18. Menalar Dinamika Konflik Wisata Goa Pindul

    Directory of Open Access Journals (Sweden)

    Laode Machdani Afala

    2017-09-01

    Full Text Available This paper intends to provide an overview of how the drama of the conflict took place in the tourist area of Goa Pindul, Gunungkidul egency. Through the contentious politics approach, this paper oncludes that the dynamics of conflict that occurred in the cinde tour of Pindul have increased escalation of conflict along with the development of Goa Pindul tourism that increasingly famous and bring huge profits. This happens because of the conflictual relationship between the actors, namely the government, Pokdarwis, and local communities in the management of Goa Pindul tourist attraction. The conflict was mainly triggered by the presence of an open opportunity structure of economic structure and land ownership that emerged along with the presence of Goa Pindul tourist attraction. The conflict then expanded and involved many actors through the emergence of claims in their bid for rights over the management of the tourist area.

  19. DINAMIKA RESILIENSI ORANG TUA ANAK AUTIS

    Directory of Open Access Journals (Sweden)

    Siti Mumun Muniroh

    2012-10-01

    Full Text Available This research is meant to know the dynamic of resiliency of the parents who have autism child in Pekalongan City by using phenomenology theory. To collect data it was used in-depth interview and observation. The respondents are the parents who have autism child that goes to extraordinary school for disable persons YRI of Pekalongan City. The result of this research shows that the forming of the parents’ resiliency is influenced by internal and external factors. Cognitively, at the beginning of diagnose, the parents feel worry, stress, and even think to blame on themselves. Affectively, worry, confuse and sad feeling are experienced by them. After adaptation and meaning process, cognitive and affective conditions of them begin to change. They view the problems more positive, and have been able to accept and broad minded the problems faced by them, so that they are motivated to find the solution for their children

  20. DINAMIKA HUKUM DAN ETIKA DALAM PROFESI KEDOKTERAN

    Directory of Open Access Journals (Sweden)

    Ashadi L. Diab

    2017-05-01

    Full Text Available This article reviews the correlation of law and ethics of the medical in performing its duties to provide relief, comfort to patients who want healing. Theory of existence that reinforces the existence of Islamic law in regulating and seeing all the things and phenomena that occur in society and realize the benefit to mankind without knowing the boundaries of time and place. Theory of justice, law as a social order that can be declared fair if it can regulate human actions in a satisfactory way to find happiness, accommodate the general value, but still the fulfillment of a sense of justice and happiness for every individual. In medical action should be done intact. Although from the law is very varied and dynamic in seeing the phenomenon that occurs whether it is civil law, criminal and administrative. Law is actually a means to regulate, discipline, and resolve various problems in the midst of society. The functioning of the law depends a lot and is influenced by other socio-cultural system. In attitudes, behavior, rights, duties. it must be well done in synergy with ethics that is more likely to be meaningful or known by al-adab is mean the proper way, good and corr.

  1. DINAMIKA AKAD DALAM TRANSAKSI EKONOMI SYARIAH

    Directory of Open Access Journals (Sweden)

    Rahmawati Rahmawati

    2016-02-01

    Full Text Available Transaction is one of law product (sharia and jurisprudence that has a lot of development in accordance to human dynamics of the classical period to the present day. In the future, it will always envolve to follow the dynamics of economic system by maintaining the substance in the middle of economical global contentions. Transaction becomes one of Islamic and sharias (revelation product law to ensure human walfare. As a norm, transactions in Islamic finance or Islamic economics can be fused into the world economic system. This can be a filtering and balancing for the economical system that runs stable towards the benefit of all parties.DOI: 10.15408/aiq.v3i1.2494

  2. DINAMIKA PENGELOLAAN WILAYAH PESISIR DI KABUPATEN REMBANG

    Directory of Open Access Journals (Sweden)

    Kismartini Kismartini

    2016-02-01

    Full Text Available Coastal zone management is complex, from the results of the research showed that many stakeholders involved in coastal management. Among them are from government agencies (Department of Marine and Fisheries, Bappeda, Department of Culture, Tourism and Sport, Department of Transportation, Office of Environment, DPRD, Private and Public sector. The key role is in the Department of Marine and Fisheries, while BAPPEDA have a very important role in the coordination between stakeholders. Efforts can be made to involve stakeholders better is through understanding the role of each stakeholder, and then optimize the role of coastal zone management in order to obtain effective and efficient.

  3. Dinamika Pelaksanaan Desentralisasi Birokrasi Pelayanan Kesehatan

    Directory of Open Access Journals (Sweden)

    Ambar Widaningrum

    2007-03-01

    Full Text Available Decentralization represents a good opportunity to improve health services. Specifically, decentralization and related steps can lead to conditions in which district institutions have many discretionary authorities and choices to offer high quality services, and people have the information, financial means, and bargaining power required to elicit appropriate responses. Howeaer, the overall impacts of decentralization on health service depends on its design and institutional arrangements. These need to be supported by appropriate policy instruments and mechanisms.

  4. Partai Islam dalam Dinamika Demokrasi di Indonesia

    Directory of Open Access Journals (Sweden)

    Gonda Yumitro

    2014-05-01

    Full Text Available Some surveys showed that though Islamic parties had significant supports in 1999 and 2004 elections and their existences are in the largest Muslim population in the world, the current development indicates the decline supports of people on them. This paper will analyze various factors which cause such phenomena and predict the Islamic parties position on 2014 election. The result found that Islamic parties will face tough position on next election because of democracy, Indonesian Islamic characteristics and history, the competence of Islamic parties, and other external factors. The democracy causes a lot of problems, like the conflict among Islamic groups in Indonesia, which had dark history as the consequence of the politization of Islam by the elites. Moreover, the involvement of Islamic parties in Indonesian politics has not able to solve the real problems within the society, such as poverty, unemployment, corruption, etc. Unfortunately, the public opinion and education characters in Indonesia also don’t support the Islamic political parties position.

  5. Corak Etnik dan Dinamika Batik Pekalongan

    OpenAIRE

    Irfa'ina Rohana Salma

    2016-01-01

    ABSTRAKBatik Pekalongan mempunyai ciri khas atau karakter yang berbeda dengan batik dari daerah pesisir lainnya. Corak yang berbeda ini karena adanya pengaruh budaya dari etnis-etnis pembuat batik yang berdomisili di Pekalongan, yaitu etnis Jawa, etnis Cina dan etnis Belanda. Tulisan ini bertujuan untuk melakukan tinjauan dan mengkritisi lebih dalam ciri khas atau karakter corak dari batik yang dihasilkan para pembatik dari etnis yang berbeda di Pekalongan. Metode pendekatan yang dipakai yait...

  6. Silicon-lithium nuclear radiation detectors. Kremnii-litievye detektory yadernogo izlucheniya

    Energy Technology Data Exchange (ETDEWEB)

    Azimov, S.A.; Muminov, R.A.; Shamirzaev, S.Kh.; Yafasov, A.Ya.

    1981-01-01

    A presentation is made of the physical principles underlying the design, building, and technology of silicon-lithium detectors and ways of improving them. Criteria of nuclear radiation control and selection and the connection between radiation and detector properties are discussed. A study is made of the effect that various defects have on the process of charge collection and formation of amplitude spectra during the recording of various types of particles. A detailed examination is made of the optimal technological systems for making detectors with high energy and time resolutions, and features of producing high-quality detectors which employ the use of ion-laser and other methods of modern semiconductor technology. 322 references, 102 figures, 2 tables.

  7. Radiation protection at the RA Reactor in 1986, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 20.5 mSV during past 10 months. Individual exposures for 7/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1986. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su i analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radiacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 20,5 mSv, a da su pojadinacna izlaganja vise od 7/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o

  8. Radiation protection at the RA Reactor in 1988, Part -2, Annex 1, Radioactivity control of working environment, dosimetry; Deo 2 - Prilog 1 - Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Bjelanovic, J; Minincic, Z; Glodic, S; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted was less than 0.5 mSv during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the annual permissible exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. During 1988 there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel. [Serbo-Croat] U ovom izvestaju prikazani su analizirani reprezentativni rezultati sakupljeni u okviru kontrole radne sredine i tehnicke zastite od zracenja reaktora RA. U prvom delu izvestaja izlozeni su podaci o osnovnim vidovima izlaganja zracenju i statisticki pregled ukupnog broja radijacionih merenja. Dati su takodje rezultati merenja sadrzaja radioktivnih gasova i aerosola u vazduhu, kao i stepena kontaminacije povrsina, odece i otkrivenih delova tela osoblja. U drugom delu izvestaja izlozeni su rezultati analize ozracivanja radnog osoblja. Utvrdjeno je da je maksimalna individualna doza spoljasnjeg izlaganja u proteklih 10 meseci bila 0,5 mSv, a da su pojedinacna izlaganja vise od 9/10 radnog osoblja bila manja od 1/10 godisnje granicne vrednosti. Dati su takodje uporedni podaci o ozracivanju osoblja u prethodnoj, kao i u pet proteklih godina, iz

  9. Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Vol. V; Album V: Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u VEK reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

    Design project of the dosimetry control system in the independent CO{sub 2} loop for cooling the samples irradiated in the RA reactor vertical experimental channels includes the following: calculations of CO{sub 2} gas activity, design of the dosimetry control system, review of the changes that should be done in the RA reactor building for installing the independent CO{sub 2} loop, specification of the materials with cost estimation, engineering drawings of the system. Predprojekat sistema dozimetrijske kontrole u nezavisnom kolu CO{sub 2} za hladjenje uzoraka ozracivanih u vertikalnim eksperimentalnim kanalima reaktora RA sadrzi: proracun aktivnosti gasa CO{sub 2}, idejno resenje sistema dozimetrijske kontrole, pregled izmena koje bi trebalo izvrsiti u zgradi RA u vezi montaze nezavisnog kola CO{sub 2}, specifikaciju materijala sa cenom kostanja i graficku dokumentaciju predprojekta.

  10. Radiation protection at the RA Reactor in 1986, Part -2, Annex 2a, Radioactivity control of the RA reactor environment (atmospheric precipitations, dust, water, soil, plants, fruit...); Deo 2 - Prilog 2a - Kontrola radioaktivnosti okoline nuklearnog reaktora RA (padavine i slobodno natalozena prasina, vode, zemljiste, rastinje, voce...)

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, N; Martic, M; Jovanovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    Control of radioactivity in the biosphere in the vicinity of the RA reactor is part of the radioactivity control done regularly for the whole territory of the Vinca institute (report by the same authors included in this Annex). During 1986 control was conducted according to the plan until May 1, 1986 when a dramatic increase of the precipitations and all other samples from the biosphere was recorded. According to the measured data no significant changes have been found in the surroundings of the RA reactor, until April 29 1986. Since then more detailed control was conducted, the number of samples was increased, apart from standard measuring procedure of total beta activity measurements, gamma spectrometry of all samples was applied. High activity level of the following nuclides was found: Iodine, cerium,cesium, tellurium, ruthenium, barium, lanthanum, etc. As an example activity of ?1?3?1 I in one sample was 564{+-}5 kBq/m{sup 2}. [Serbo-Croat] Kontrola radioaktivnosti biosfere u okolini reaktora RA je deo kontrole radioaktivnosti koja se redovno vrsi za celokupnu teritoriju Instituta Vinca (izvestaj istih autora ukljucen je u ovaj Prilog). Tokom 1986. kontrola je ostvarivana prema planu do 1. maja 1986, kada je registrovano drasticano povecanje aktivnosti padavina i ostalih uzoraka biosfere. Prema rezultatima merenja, nisu registrovana znacajnija odstupanja u okolini reaktora RA sve do 29. aprila 1986. Od tada se vrse detaljnija merenja, broj uzoraka je uvecan, pored standardno primenjivane metode primenom merenja totalne beta aktivnosti uzoraka, svi uzorci su analizirani gama spektrometrijski. Enormno visoka kontaminacija uzoraka posle gamma spektrometrije pokazala je prisustvo aktivacionih i fisionih radionuklida medju kojima su bili: jod, cerijum, cesijum, rutenijum, barium lantan i drugi. Tako je na primer samo aktivnost I-133 iznosila 564{+-}5 kBq/m{sup 2}.

  11. Operating Experience with the VERA Zero-Energy Fast Reactor; Fonctionnement du Reacteur VERA a Neutrons Rapides, de Puissance Zero; Opyt ehkspluatatsii reaktora VERA na bystrykh nejtronakh nulevoj moshchnosti; Experiencia Adquirida con el Reactor Rapido VERA de Potencia Nula

    Energy Technology Data Exchange (ETDEWEB)

    Weale, J. W.; McTaggart, M. H.; Goodfellow, H.; Paterson, W. J. [Atomic Weapons Research Establishment, Aldermaston (United Kingdom)

    1964-02-15

    , intensidad de la fuente neutronica, empleo de un acelerador para producir neutrones; velocidad de respuesta de los circuitos de seguridad y restricciones subsiguientes en lo que atafle a la velocidad con que se pueden unir las dos mitados; precauciones adicionales necesarias al utilizar plutonio como combustible; notas sobre la precision de las mediciones de reactividad y sobre las limitaciones practicas que afectan a otras mediciones relacionadas con la fisica de los reactores. (author) [Russian] Daetsja kratkoe opisanie konstrukcii reaktora na bystryh nejtronah nule- voj moshhnosti, sostojashhego iz dvuh odinakovyh chastej. Pri jetom osoboe vnimanie udeljaetsja tem chertam, kotorye opredeljajut praktichnost' i obespechivajut tochnost' izmerenij po fizi- ke reaktorov. Obsuzhdajutsja preimushhestva i nedostatki konstrukcii s ssylkoj na dvuhlet- nij opyt jekspluatacii reaktora. Rassmatrivajutsja sledujushhie temy:prisposoblennost' proekta i konstrkcii iz dvuh odinakovyh chastej dlja provedenija jeksperimental'nyh issle- dovanij; razmer i kachestvo obrabotki toplivnyh blokov i tochnost' razmeshhenija toplivnyh jelementov; vlijanie granichnyh neravnomernostej i geterogennosti struktury na tochnost' opredelenija kriticheskoj massy ''ideal'noj'' jekvivalentnoj sborki; vosproizvodimost' kri- ticheskogo uslovija posle demontirovanija sborki ili razdelenija dvuh chastej; izmenenie reak- tivnosti s razdeleniem chastej, v tom chisle vlijanie nesimmetrichnoj zagruzki;chuvstvitel'- nost' razlichnyh schetchikov, moshhnost' istochnika nejtronov, ispol'zovanie istochnika uskorennyh nejtronov; bystrota otvetnoj reakcii konturov avarijnoj zashhity i posledujushhie ogranichenija skorosti sobiranija chastej; dopolnitel'nye predupreditel'nye mery, neobho- dimye pri ispol'zovanii plutonija; primechanija otnositel'no tochnosti izmerenija reaktiv- nosti i otnositel'no prakticheskih ogranichenij, vlijajushhih na razlichnye drugie izmerenija po fizike reaktorov. (author)

  12. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    , ''Rejnish vestfalishes ehlektritsitetsverk und bajernverk'', Kal'-na-Majne, Zapadnaya Germaniya. Rabochaya kharakteristika kipyashchego reaktora atomnoj ehlektrostantsii pri obychnom rezhime raboty v kommunal'noj ehnergosisteme ochen' khoroshaya. Koehffitsient ispol'zovaniya i moshchnosti reaktora i ehlektrostantsii daet tverdoe osnovanie polagat', chto ehlektrostantsii s kipyashchimi reaktorami yavlyayutsya nadezhnymi s tochki zreniya ikh rabochej kharakteristiki. V techenie 1963 goda budut vvedeny v stroj chetyre dopolnitel'nye ehlektrostantsii s kipyashchimi reaktorami: atomnaya ehlektrostantsiya v Big Rok Pojnt, ''Kons'yumers pauehr kompani'', Sharl'vua, Michigan, atomnaya ehnergeticheskaya ustanovka v KHamboldt Bej, ''Pasifik gaz ehnd ehlektrik kompani'', Yurika, Kaliforniya, atomnaya ehlektrostantsiya v Garig'yano, Natsional'noe obshchestvo po atomnoj ehnergii, Skauri, Italiya,i Yaponskij demonstratsionnyj ehnergeticheskij reaktor. Yaponskij nauchno-issledovatel'skij institut po atomnoj ehnergii, Tokai-Mura, Yaponiya. Pusk i pervonachal'naya ehkspluatatsiya ehtikh ehlektrostantsij podtverzhdayut predpolozhenie o nadezhnosti ikh raboty, chto uzhe prodemonstrirovano atomnymi ehlektrostantsiyami v Drezdene, Kale i Vallesitose. Rabochaya kharakteristika atomnykh ehlektrostantsij v Drezdene, Kale i Vallesitose yavlyaetsya naglyadnym dokazatel'stvom stabil'nosti i bezopasnosti kipyashikh reaktorov. Krome togo, urovni radiatsii na samoj ehlektrostantsii i v okruzhayushchej srede znachitel'no nizhe predelov, ustanovlennykh litsenziyami na ehkspluatatsiyu. Podtverdilis' prostota i legkost' ehkspluatatsii kipyashchikh reaktorov. Kharakteristika kontrolya za nagruzkoj u kipyashchego reaktora s dvojnym tsiklom Drezdenskoj ehlektrostantsii okazalas' ochen' khoroshej. Krupnye i nebol'shie raboty po ukhodu i remontu mogut osushchestvlyat'sya obychnymi remontnymi gruppami bez vrednykh posledstvij ili bez limita vremeni, svyazannymi s soobrazheniyami radioaktivnogo oblucheniya. V

  13. Safety report for the independent CO{sub 2} loop for cooling the samples irradiated in the vertical experimental channels of the RA reactor; Izvestaj o sigurnosti za nezavisno kolo CO{sub 2} za hladjenje uzoraka ozracenih u vertikalnim eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, A; Zivkovic, S; Milosevic, M; Strugar, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    Independent CO{sub 2} loop was designed for cooling the samples irradiated in the vertical experimental channels in the region of heavy water or in the graphite reflector. It is considered as a significant improvement of the RA reactor experimental possibilities. Six 'heads' are placed in vertical experimental channels and connected in parallel with the outer loop which contains out-of-reactor equipment. It is planned to irradiate samples in the 'heads' of the loop for the needs of Hot laboratory and Laboratory for reactor materials. Heat generated during sample irradiation is removed by CO{sub 2} circulation. This report contains detailed description of the main loop, auxiliary systems, calculation results of anti reactivity and activation of construction materials of the low-temperature CO{sub 2} loop. A separate chapter is devoted to control and regulation of temperature and pressure. Testing of the fundamental parameters of the coolant loop showed that it could fulfill more demanding tasks than designed by the project. Annex of this report includes results of leak testing for the loop 'heads' in vertical experimental channels VEK-6 and VEK-8 by helium leak detector. [Serbo-Croat] Nezavisno kolo CO{sub 2} namenjeno je za hladjenje uzoraka ozracivanih u VEK reaktora u zoni teske vode i u zoni grafita, i predstavlja znacajan doprinos povecanju eksperimentalnih mogucnosti reaktora RA. Sest 'glava' je postavljeno u vertikalne eksperimentalne kanale i paralelno vezano na spoljno kolo koje sadrzi vanreaktorsku opremu. U glavama petlje se predvidja ozracivanje raznovrsnih uzoraka materijala za potrebe Laboratorije za visoku aktivnost i Laboratorije za reaktorske materijale. Toplota koja se generise prilikom ozracivanja uzoraka odvodi se cirkulacijom CO{sub 2}. Ovaj izvestaj sadrzi detaljan opis: glavnog kola, pomocnih sistema; rezultate proracuna antireaktivnosti i aktivacije konstrukcionih elemenata glave niskotemperaturne petlje CO{sub 2}. Posebno poglavlje posveceno

  14. Performance Characteristics of the Experimental Boiling Water Reactor from 0 to 100 MW(t); Performances de l'EBWR de 0 a 100 MW; Rabochaya kharakteristika ehksperimental'nogo kipyashchego reaktora EBWR pri moshchnosti 0 - 100 mgvt.; Rendimiento del reactor experimental de agua hirviente (EBWR) entre 0 y 100 MW

    Energy Technology Data Exchange (ETDEWEB)

    Iskenderian, A.; Lipinski, W. C.; Petrick, M.; Wimunc, E. A. [Argonne National Laboratory, Argonne, IL (United States)

    1963-10-15

    entonces de comportarse como reactor de agua hirviente de ciclo directo; en cierto modo, funciona como reactor de ciclo doble y circulacion natural. (author) [Russian] 25 maya 1962 goda Argonnskaya natsional'naya laboratoriya poluchila razreshenie KAEH SSHA na ehkspluatatsiyu reaktora EBWR na moshchnosti 100 mgvt. Administrativnoe razreshenie na ehkspluatatsiyu reaktora bylo predostavleno sistemoj garantij. Mezhdunarodnogo agentstva po atomnoj ehnergii 11 iyulya 1961 goda. 15 noyabrya 1962 goda byl dostignut uroven' moshchnosti v 100 mgvt. 6 dekabrya 1962 goda ehksperimental'naya programma byla zakonchena. Odnoj iz osnovnykh tselej ee byla tshchatel'naya proverka reaktora dlya polucheniya dannykh i informatsii rabochej kharakteristiki ehtogo tipa reaktora. Ehta programma byla pervoj programmoj takogo roda i pervoj vypolnennoj programmoj. Dlya polucheniya nuzhnykh dannykh neobkhodimo bylo razrabotat' mnogie novye pribory. TSel' byla dostignuta, polucheno mnogo novykh dannykh o rabochej kharakteristike kipyashchego reaktora s estestvennoj tsirkulyatsiej. Tak,naprimer, poluchena informatsiya otnositel'no skorosti potoka tsirkulyatsii v zamknutom tsikle, predelov separatsii zhidkogo para (vydelenie para v osadok v spusknoj trube i unos zhidkosti ehflu- entom para), nedogreva, lokalizatsii dejstvitel'noj poverkhnosti razdela v reaktore i ee svyazi s urovnem vodnoj kolonki, skorosti razrusheniya para v spusknoj trube, pustotnykh koehffitsientov, reaktivnoj sposobnosti H{sub 3}BO{sub 3}, temperaturnykh koehffitsientov, ispol'zovaniya sterzhnej iz bora dlya tselej kontrolya, ispol'zovaniya svezhikh toplivnykh ehlementov, peredatochnykh funktsij,analiza shuma, nekotorykh izmerenij potoka, stabil'nosti i t.d. Krome togo, byli polucheny dannye o povedenii i tselostnosti nekotorykh reaktornykh komponentov i sistem, takikh, kak bornokislaya kontrol'naya reaktsiya, urovni radiatsii, raspredelenie produktov korrozii, vykhod iz stroya oborudovaniya, toplivo i reguliruyushchie sterzhni i t

  15. RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor; Istrazivacki nuklearni reaktor RA - Deo 1 - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1982. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Kozomara-Maic, S; Cupac, S; Radivojevic, J; Stamenkovic, D; Skoric, M; Miokovic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1982-12-15

    outdated spare parts. Project concerning renewal of the reactor equipment was initiated during the past year according to the contract with the Soviet Atomenergoexport and IAEA which has planned to spend 1 000 000 of rubles for this project. [Serbo-Croat] Probni rad reaktora zapocet septembra 1981. godine na snazi od 2 MW sa 80% obogacenim gorivom nastavljen je u celoj 1982. prema prethodno napravljenom planu. Pocetno jezgro formirano ja sa 44 gorivna kanala sa po deset gorivnih elemenata. Prva polovina godine iskoriscena je za neophodna merenja i ispitivanja radnih parametara rektora i funkcionisanje sistema i opreme u radnim uslovima. U drugoj polovini godine zapocet je program probnog rada na visim snagama. Utvrdjeno je da ugradjeni visak reaktivnosti i kapacitet kontrolnih sipki zadovoljava sigurnosne kriterijume MAAE, ugradjeni visak reaktivnosti moze da omoguci rad na snazi od 4,7 MW u 4 mesecne kampanje sa po 15-20 dana rada, postoje povoljni uslovi za hladjenje jezgra pri pocetnoj konfiguraciji. Izmeren je efekat pocetnog zatrovanja na reaktivnost i raspodelu snage, izmerena je pocetna prostorna raspodela neutronskog fluksa koja iznosi 3,9 10{sup 13} cm{sup -2} s{sup -1} pri znazi od 2 MW. Odredjena je promena kalibracionog koeficijenta u sistemu za automatsko odrzavanje snage. Svi rezultati ukazuju da ce pri nominalnoj snazi od 4,7 Mw biti zadovoljeni svi kriterijum sigurnosti i postovana ogranicenja u odnosu na koriscenje goriva. Po dobijanju dozvole za rad na punoj snazi morace da se izvrsi dopunski probni rad na snagama od 3, 4, i 4,7 MW. Prelaz od pocetne konfiguracije sa 44 gorivna kanala u jezgru vrsice se postupno da bi se dostigla ravnotezna konfiguracija sa 72 gorivna kanala sa po 10 elemenata. Reaktor nije radio u septembu mesecu zbog radova na zameni dela cevovoda koji povezuje pumpnu stanicu na Dunavu sa horizontalnim taloznikom. Kontrola i odrzavanje opreme izvrsavani su redovno u granicama raspolozivosti rezerbinh delova. Teskocu pricinjava

  16. Neutron Tests at the Start-Up of EDF1; Les essais neutroniques au demarrage du reacteur EDF1; Nejtronnye izmereniya pri puske reaktora EDF1; Ensayos neutronicos efectuados durante la puesta en marcha del reactor EDF1

    Energy Technology Data Exchange (ETDEWEB)

    Teste du Bailler, A. [Centre d' Etudes Nucleaires de Saclay (France); Janin, R. [Electricite de France, Paris (France)

    1963-10-15

    ehksperimental'nykh metodov, razrabotannykh na reaktorakh v Markule, byla provedena vo vremya puska reaktora EDF.1. Izmereniya kasalis' glavnym obrazom ehffektivnosti upravlyayushchikh sterzhnej pri razlichnykh p ogruzh eniyakh. Opredelyaetsya skhema pod''ema s terzhnej, kotoraya pozvolyaet poluchat' polnuyu moshchnost' prk soblyudenii opredelennykh ogranichenij v temperature obolochek i gaza. Parallel'no byli provedeny izmereniya potoka pri razlichnykh polozheniyakh kompensiruyushchikh sterzhnej i pri razlichnykh zagruzkakh poglotitelej v opredelennykh kanalakh, v zavisimosti ot predvaritel'nykh raschetov v dvukhraehmernom izmerenii. Ehti izmereniya byli polucheny putem aktivatsii tochechnykh detektorov s primeneniem obychnogo metoda otravleniya vozdukha. Pri nekotorykh urovnyakh temperatury (do 140{sup o}C) byli provedeny izmereniya koehffitsientov reaktivnosti i ehffektivnosti reguliruyushchikh sterzhnej. V to zhe vremya putem aktivatsii sootvetstvuyushchikh detektorov (uran, plutonij, lyutetsij, marganets, indij, zoloto) byli provedeny izmereniya koehffitsientov spektra. Dlya izmereniya ehffektivnosti nekotorykh kompensiruyushchikh sterzhnej byl ispol'zovan ostsillyatsionnyj metod. Nakonets, s tselyakh izucheniya zashchity i povrezhdeniya grafita byli provedeny izmereniya potoka bystrykh nejtronov. (author)

  17. Advanced epithermal thorium reactor (AETR) physics; Physique d'un reacteur au thorium, a neutrons epithermiques, de type perfectionne (AETR); Fizika usovershenstvovannog o nadteplovogo torievogo reaktora; Fisica del reactor epitermico de tipo avanzado, alimentado con torio (AETR)

    Energy Technology Data Exchange (ETDEWEB)

    Campise, A. V. [Atomics International, Canoga Park, CA (United States)

    1962-03-15

    del {sup 233}Pa y de isotopos del uranio sobre el balance neutronico relativo y se evalua la probable razon de reproduccion y las caracteristicas de combustion teniendo en cuenta la imprecision en el conocimiento de las secciones eficaces nucleares. (author) [Russian] Rassmatrivayuts ya printsipy konstruirovani ya usovershenstvovannog o nadteplovogo torievogo reaktora s uchetom sushchestvuyushchej teorii yadernykh parametrov i potentsial'nogo poleznogo ispol'zovaniya nejtronov. Byl izuchen ehffekt rezonansnogo zakhvata toriya v sistemakhs grafitovym zamedlitelem dlya nejtronov s ehnergiyami ot 0,10 do 100 kehv. Ispol'zuyutsya formuly uzkogo rezonansa i shirokogo rezonansa v tselyakh polucheniya zavisimogo ot temperatury ehffektivnogo rezo- nansnogo integrala torievogo sterzhnya, kotoryj vyrazhaetsya v vide ehkvivalentnykh mnogogruppovykh sechenij. Neobkhodimost' v poluchenii yadernykh dannykh v oblasti promezhutochnykh ehnergij privela k sozdaniyu proekta i konstruktsii kriticheskoj sborki. Yadernyj proekt ehtoj sborki podcherkivaet vazhnost' dannykh poperechnykh sechenij i teoreticheskoj interpretatsii ehksperimental'nykh rezul'tatov, imeyushchikh otnoshenie k usovershenstvovannom u nadteplovomu torievomu reaktoru. Tochnost' analiticheskikh metodov byla podtverzhdena pri analize ehksperimental'nykh rezul'tatov, poluchennykh na reaktore nulevoj moshchnosti ZPR-III. Provodyatsya sravneniya trekh konfiguratsij teploperedachi s ispol'zovaniem udvoennogo vremeni v kachestve optimal'nogo parametra. EHffekt proizvodstva izotopa protaktiniya-233 i urana pri otnositel'no poleznom ispol'zovanii nejtronov, vozmozhnye koehffitsienty vosproizvodstva i kharakteristiki vygoraniya otsenivayutsya v svyazi s netochnostyami v yadernykh poperechnykh secheniyakh. (author)

  18. RA Research nuclear reactor, Part 1, RA reactor operation and maintenance in 1993, with comparative review for the period 1991 - 1993, Annex 3; Projekat Istrazivacki nuklearni reaktor RA - 1 Deo Pogon i odrzavanje nuklearnog reaktora RA u 1993. godini, uz uporedni pregled za period 1991 - 1993. - prilog 3

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Mikic, N; Tanaskovic, M [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1993-12-15

    RA reactor was not operated during 1993 because of the complete instrumentation exchange. Although it has been planned to exchange the complete instrumentation until the end of 1993, and to start reactor operation in the first half of 1993 this was not fulfilled because the instrumentation was not delivered until the end of 1993. Main activities during past seven years were related to construction of the emergency cooling system; repair and reconstruction of the system for handling the spent fuel and improvement of spent fuel storage conditions; exchange of the aged instrumentation. Other reactor components and systems, reactor core, primary coolant loop and gas circulation system are in good condition concerning future start-up. [Serbo-Croat] U 1993. godini reaktor nije bio u pogonu zbog zamene njegove celokupne instrumentacije. Iako je bilo planirano da se celokupna instrumentacija zameni do kraja 1993. te da reaktor pocne sa radom u prvoj polovini 1993. Ovo nije ispunjeno jer celokupna oprema nije isporucena ni do kraja 1993. godine. Osnovni zahvati koji su u proteklih sedma godina izvrseni, odnosili su se na izgradnju sistema za udesno hladjenje, rekonstrukciju sistema za rukovanje ozracenim gorivom i poboljsanje uslova za stokiranje ovog goriva, zamenu instrumentacije. Ostali sistemi reaktora, reaktorsko jezgro, primarno kolo hladjenja i sistem za cirkulaciju gasa su u dobrom stanju i mogu se nesmetano koristiti u buducem radu.

  19. Reactor Physics Development for Advanced Gas-Cooled Reactors; Recherches en Physique des Reacteurs, pour des Reacteurs Perfectionnes Refroidis par un Gaz; Razrabotka metodov v oblasti reaktornoj fiziki dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem; Progresos de la Fisica de los Reactores de Tipo Avanzado Refrigerados por Gas

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J. [United Kingdom Atomic Energy Authority (United Kingdom)

    1964-04-15

    metodos de medicion de los efectos de la reactividad en APEX, HERO y AGR, y para determinar los datos relativos a la estructura fina y a la distribucion de la potencia en los conjuntos combustibles complejos. Los trabajos se concentran principalmente en el desarrollo de un metodo capaz de sustituir al 'hetrecontrol' y al 'FTD2' , para los cuerpos de reactor cuando el combustible haya alcanzado un grado de combustion considerable. La finalidad del programa experimental con la instalacion HERO es precisamente comprobar estos metodos con cuerpos complejos, inclusive con combustible que contenga plutonio. La explotacion del reactor AGR y las mediciones fisicas que se realicen con el combustible despues de la irradiacion permitiran obtener datos adicionales sobre el efecto del plutonio. (author) [Russian] Rassmatrivaetsja tshhatel'naja jeksperimental'naja i teoreticheskaja rabota, provedennaja pri konstruirovanii, stroitel'stve i vvode v jekspluataciju Uindskejlskogo usovershenstvovannogo reaktora s gazovym ohlazhdeniem i pri okazanii obshhej pomoshhi pri razrabotke usovershenstvovannogo reaktora s gazovym ohlazhdeniem (AGR) dla proizvodstva jenergii dlja grazhdanskih celej. Daetsja opisanie znachitel'nogo ob{sup e}ma rabot, kotorye byli neobhodimy dlja razrabotki prigodnyh teoreticheskih metodov rascheta: 1) raspredelenija potoka i balansa reaktivnosti v slozhnoj aktivnoj zone reaktora; 2) raspredelenija jenergii v toplive so slozhnoj geometriej i 3) vlijanija obluchenija na toplivnye cikly i raspredelenie jenergii. V kachestve vvedenija delaetsja ssylka na jeksperimental'nye dannye i teoreticheskie metody, poluchennye v rezul'tate rabot nad uranovo-magnoksovymi sistemami, i na jeksperimental'nye dannye, poluchennye v rezul'tate Sovmestnoj jeksperimental'noj programmy Britanskoj promyshlennosti (BICEP), kotorye javilis' otpravnym momentom v razrabotke teoreticheskih metodov, primenimyh k usovershenstvovannym reaktoram s gazovym ohlazhdeniem. Dlja opredelenija parametrov

  20. Initial Operating Experience with the ''NPD'' Reactor; Experience recueillie pendant les premiers mois de fonctionnement du reacteur NPD; Pervyj opyt po ehkspluatatsii reaktora NPD; Experiencia inicial de funcionamiento del reactor NPD

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, L. G. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    raboty na vysokoj moshchnosti v techenie shesti nedel' dal koehffitsient ispol'zovaniya na moshchnost', ravnyj 70% Uluchsheniya, kotorye byli dostignuty, uvelichili bezopasnost', povysili ehkspluatatsionnye kharakteristiki i prodemonstrirovali potentsial'nye metody snizheniya kapital'nykh zatrat dlya budushchikh stantsij. Tak, naprimer, v tselyakh uluchsheniya ehkspluatatsionnykh kachestv byli vidoizmeneny uplotneniya valov na nasosakh okhladitelya pervogo kontura; oborudovanie tipa kholodil'nikov, ispol'zovavsheesya dlya regeneratsii para, bylo zameneno pogloshchayushchimi kolonkami s tsel'yu umen'sheniya poteri para v tyazheloj vode. Ustanavlivayutsya takzhe ogranichiteli potoka vody v liniyakh dlya vzyatiya prob s tsel'yu umen'sheniya poteri tyazheloj vody v sluchayakh neispravnostej v soedineniyakh. V dekabre 1962 goda dve odnovremennye utechki iz mashiny, proizvodyashchej zagruzku topliva, priveli k neobychnomu obstoyatel'stvu, pri kotorom znachitel'noe kolichestvo goryachej tyazheloj vody pod vysokim davleniem popalo v kameru reaktora, gde proizoshlo neznachitel'noe umen'shenie ee izotopnoj chistoty, kotoraya zatem byla prevyshena i reaktor byl vnov' pushchen v kontse mesyatsa. Vo vremya avarii vse ustrojstva po bezopasnosti rabotali tochno i obespechili uderzhanie tyazheloj vody. (author)

  1. New Instruments and Principles for the Dimensional Measurement and Measurement of Spacing of Reactor Components; Nouveaux Instruments et Procedes de Mesure des Dimensions et de l'Espacement des Elements d'un Reacteur; Novye pribory i printsipy izmereniya razmerov i raspolozheniya komponentov reaktora; Nuevos Instrumentos y Principios para Medir las Dimensiones y la Separacion Entre Componentes de Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    vihrevyh tokov dlja izmerenija tolshhiny listov i kontejnerov iz cvetnyh i austenitnyh metallov s pomoshh'ju perehodnyh katushek; b) metod vihrevyh tokov dlja izmerenija tolshhiny stenok trub s pomoshh'ju prohodnyh katushek. Opisyvajutsja prigodnye dlja jetogo pribory i ih primenenie. Izmerenie tolshhiny stenok uzlov reaktora iz cvetnyh metallov po 'metodu magnitnogo sharai . Ob'jasnjaetsja princip jetogo novogo vida izmerenij, oblast' ego primenenija (osobenno dlja tochechnyh izmerenij) i opisyvaetsja primenjaemyj na praktike pribor. Izmerenie materialov nemagnitnyh pokrytij na magnitnoj osnove. Ob'jasnjajutsja principy izmerenij (metody magnitnogo polja postojannogo toka i peremennogo toka) i opisyvajutsja pribory dlja izmerenija nemagnitnyh pokrytij tolshhinoj ot 3 mikron do 20 mm. Osobo rassmatrivaetsja problema otlozhenija stellita na ferritnyh stenkah korpusov reaktorov. Izmerenie pokrytij, neprovodjashhih jelektrichestvo,-na materialah iz cvetnyh metallov. Ob'jasnjaetsja princip takogo izmerenija (vihrevye toki). Opisyvaetsja pribor dlja .takih izmerenij i tipichnye primery izmerenij. Privodjatsja beskontaktnye tehnologicheskie izmerenija fizicheskih razmerov metallicheskih komponentov reaktora. Ob{sup j}asnjajutsja razlichnye metody izmerenija chernyh i cvetnyh metallov (metod magnitnogo polja postojannogo toka i peremennogo toka, metody vihrevyh tokov). Opisyvajutsja pribory i primery distancionnogo izmerenija diametra oval'nosti, iskazhenija i t.d. komponentov reaktora. Opisyvajutsja metody opredelenija raspolozhenija takih komponentov v 'gorjachej' zone reaktora. ' Opisyvaetsja pribor dlja registracii profilja poverhnosti i neposredstvennogo opredelenija haraktera nerovnosti (''Rauhtiefe'', ''Glaettungstiefe'', GLA value i RMS value). Rassmatrivajutsja tipichnye primery ispol'zovanija jetogo pribora opredelenija nerovnostej komponentov reaktora. Osoboe vnimanie udeljaetsja vozmozhnosti ispol'zovanija nebol'shogo universal'nogo datchika v ''gorjachih'' zonah i

  2. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    debido a un control deficiente de los combustibles nucleares y a la falta de precision en las operaciones contables. La administracion de materiales nucleares requiere que los explotadores de los reactores de potencia lleven una contabilidad completa y detallada. No es necesario que los documentos sean complejos si lo que se pretende es que sean completos y adecuados. En realidad, la sencillez es sobremanera conveniente. A pesar de que el combustible nuclear es un combustible nuevo y totalmente distinto de los de tipo tradicional, no hay que rodear su utilizacion de ninguna aureola de misterio. El control de los materiales nucleares no es una simple labor de inventario, sino que constituye la base de muchas otras operaciones inherentes a la explotacion de los reactores de potencia, por ejemplo: el transporte del combustible irradiado, su regeneracion con la correspondiente contabilizacion del combustible recuperado y del material producido durante el funcionamiento del reactor, y, por ultimo, el establecimiento de un sistema de seguros adecuado. (author) [Russian] Otnositel'no novoe i chrezvychajno cennoe toplivo dlja proizvodstva jelektrojenergii, a imenno uran, trebuet ochen' tshhatel'nogo ucheta s momenta, kogda operator reaktora prinimaet na sebja material'nuju otvetstvennost' za jetot material, i do togo momenta, kogda jetot material v vide chastichno otrabotannogo topliva peredaetsja na druguju ustanovku, gde regeneriruetsja ostavshajasja chast' ego pervonachal'noj cennosti. Bol'shaja chast' operatorov jenergeticheskih reaktorov, do pojavlenija v svet jadernoj jenergetiki, rabotala na jelektrostancijah s obychnym iskopaemym toplivom i /zhe davno vyrabotala dostatochno polnye i nadezhnye formy kontrolja za ego rashodovaniem. Operator reaktora dolzhen raspolagat' ne menee nadezhnymi sposobami ucheta jadernyh materialov, ispol'zuemyh na ego ustanovke. Jekspluatacija jenergeticheskih reaktorov ne imeet bol'shoj istorii, i na protjazhenii otnositel'no korotkogo perioda

  3. Measurements at the RA Reactor related to the VISA-2 project - Part 3, calculation of VISA-2 samples influence on the reactor reactivity, on the depression of thermal neutron flux in VK-5 channel and VISA-2 samples; Fizicka merenja na reaktoru RA u vezi projekta VISA-2 - III deo, Proracun uticaja uzoraka VISA-2 na reaktivnost reaktora, na depresiju fluksa termalnih neuntrona u kanalu VK-5 i u uzorcima VISA-2

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-01

    The objective of this task was to determine the thermal neutron flux in the RA reactor cell with VISA-2 samples, the influence of VISA-2 samples on the thermal neutron flux distribution in the vicinity of VK-5 channel and the antireactivity of VISA-2 samples placed in the RA reactor core. This distribution is needed for calculating the mean value of absorption and thermal efficiency factor in the reactor cell with the sample. Thermal neutron flux distribution without the sample was calculated by diffusion theory. Fast neutron flux space distribution was assumed to be constant, i.e. that it is dependent only on the nuclear properties of the materials. Macroscopic thermal neutron flux distribution was determined by two-group diffusion theory using the four factor formula applied for two regions: active RA region, and reactor region with calls containing VISA-2 samples. This calculation enables estimation of the VISA-2 samples influence on the thermal neutron flux distribution in the VK-5 channel. Antireactivity of VISA-2 samples was calculated by neutron diffusion theory applying the perturbation method. [Serbo-Croat] Cilj ovog zadatka je da se odredi raspodela fluksa termalnih neutrona u celiji reaktora RA sa uzorcima VISA-2, uticaj uzoraka VISA-2 na makroskopsku raspodelu termalnih neutrona u blizini uzoraka, tj. u kanalu VK-5, kao i antiraktivnost uzoraka VISA-2 ubacenih u jezgro RA. Poznavanje ove raspodele potrebno je za izracunavanje srednje apsorpcije i faktora termalnog iskoriscenja u celiji reaktora sa uzorkom. Raspodela fluksa termalnih neutrona u celiji RA bez uzorka izracunata je na bazi difuzione teorije. Fluks brzih neutrona uzet je kao konstanta s obzirom na prostorne koordinate, tj. da zavisi samo od nuklearnih karakteristika materijala. Makroskopska raspodela fluksa termalnih neutrona u okolini VISA-2 odredjena je na bazi dvogrupne difuzione teorije preko formule cetiri faktora, primenjene na dve zone: prva aktivna zona RA, i druga reaktorka sredina

  4. ANALISIS DINAMIKA EKSPOR MINYAK NILAM INDONESIA KE AMERIKA SERIKAT

    OpenAIRE

    Sari, Pinjung Nawang; Hartono, Slamet

    2016-01-01

    This study to analyze the Indonesin patchouli oil export to the world main market (USA), beteen 1989-2009 oeriod by analyzing : (1) the export oerformance, (2) the export competitiveness, and (3) the factors influenced to Indonesian patchouly oil export demand to USA. The export performance was measured  by trend of export, Trae Specialization Index (ISP), and Market Penetration Index  (IPP); while the export competitives was measured by Revealed Comparative Advantage (RCA) and Acceleration R...

  5. Dinamika Hubungan Antar Etnis Dan Integrasi Imigran Di Inggris

    OpenAIRE

    Rama, Pundan; Utomo, Tri Cahyo; Windiani, Reni

    2013-01-01

    This paper attempts to describe the dynamics of inter-ethnic relationships, theintegration of ethnic groups in Britain, and how the UK government react to it. Researchdesign that used in this paper is qualitative with descriptive method. The data used in thispaper in the form of secondary data obtained from various sources.Britain as a multicultural country is faced with the challenge of managing inter-ethnicrelations in order to maintain peaceful society. Inter-ethnic relations in the UK exp...

  6. Diskursus Etika Bisnis Islam dalam Dinamika Bisnis Kontemporer

    OpenAIRE

    Ardi, Mulia

    2015-01-01

    Islamic business ethics are universal ideas that are relevant to the business world. The value that is contained in the Islamic business ethics in line with the needs of the conventional business value. Various problems faced by the contemporary business is basically caused by the lack of understanding of human identity. This ignorance leads to negative behavior of businesses in running a business. The essence of business is essentially the fulfllment of human needs. Duties and responsibiliti...

  7. DINAMIKA BISNIS TRAVEL UMROH SE KOTA PASURUAN DI ERA GLOBALISASI

    Directory of Open Access Journals (Sweden)

    Dewi Masitah

    2015-12-01

    Full Text Available This research aims to know how the Ethics and responsibility of  PT TRAVEL Umrah conducts its travel business?. This background research of Various motivations variety PT TRAVEL Umrah in implementing its travel business. Is that motivation is not only a business commodity, so causing a few problems related to that Travel, among others, the cheapness of travel so that the number of Umrah pilgrims displaced and not so depart with many reasons such as the visa is not out or travel unclear. This research is a qualitative research of Phenomenology. The research data obtained through technique of observation, in-depth interviews (in-depth interview, Focus Group Discussion (FGD and documentation with data analysis using a model of Miles and Huberman, which includes three lines of analysis, namely data reduction (data reduction, a data display (presentation data, and conclusion drawing / verification (conclusion. This Research uses the perspective of Petter Beyyer related to a religious commodity for the sake of a capitalist. Business in the name of religion is a commodity.

  8. Dinamika Penanaman Modal Asing (PMA Bidang Pertambangan Umum di Indonesia

    Directory of Open Access Journals (Sweden)

    Ukar Wijaya Soelistijo

    2011-06-01

    Full Text Available During 1967 – 1988, seven generations of Contract of Work (COW were in lieu with foreign  capital  investment in the area of non-coal general mining,  followed by three generations of Coal Contract (CCOW in Indonesia.  An analysis toward details of COW showed that the contract requirements were transformed from time to time. At the first phase, tax holiday was offered. Meanwhile, the later generations reduced such facilities as complained by mining companies.  This research suggests the importance of regulation to manage  Indonesia’s income resulted from windfall profit of oil prices increase. Sepanjang periode 1967 – 1988, Indonesia telah menghasilkan  tujuh generasi Kontrak Kerja dalam investasi modal asing untuk bidang pertambangan umum non batubara, diikuti oleh tiga generasi Kontrak Batubara. Analisis terhadap rincian Kontrak Kerja tersebut memperlihatkan perubahan  persyaratan kontrak  dari waktu ke waktu. Pada fase pertama, Kontrak Kerja menawarkan fasilitas bebas pajak (tax holiday. Hal ini tidak berlaku lagi pada Kontrak Kerja selanjutnya, sebagaimana dikeluhkan perusahaan-perusahaan tambang. Riset ini merekomendasikan pentingnya regulasi untuk mengelola pendapatan Indonesia yang bisa diperoleh dari keuntungan tambahan (windfall profit akibat kenaikan harga minyak.

  9. Dinamika Politik Kaum Muda Indonesia: Dialektika Politik Nasional dan Lokal

    Directory of Open Access Journals (Sweden)

    Syarifuddin Jurdi

    2016-08-01

    Full Text Available The Crusade taking place during two centuries (1095-1291 AD was the beginning oflarge-scale confrontation between Islam and Western Christianity. Although the Crusades ended eight centuries ago, but it still lingers in the mind of Western Christians and some Muslims. The subsequent conflicts between both sides have been always linked to the Crusades. For example, colonialism and imprealism of Western to the East during the 18th, 19th, and20thcentury is considered as acontinuation of the Crusades. In addition, the war against terrorism that the United States campaigned for the post September 11, 2001 propagated as the 2ndCrusades. Similarly, the invasion of the United States and its allies against Iraq and Afghanistan is refering the arrogances of West against Islam. These facts indicate that a huge trauma caused by the Crusades still entrenched in the minds of most of the psycho-historical Western and Muslim. Therefore, to promote a harmonious relationship between the West and Islam, the perceptions and negative images of Islam in the eyes of the West and vice versa, should be neutralized. The history has proven that when peace and truce conducted during the period of the Crusades, both parties could work together in trade and economy. In the current global context, the cooperation must be expanded. Through good cooperation and mutual benefit, suspicion and prejudice to each other will eventually fade.

  10. Dinamika Bisnis Travel Umroh Se Kota Pasuruan Di Era Globalisasi

    OpenAIRE

    Masitah, Dewi

    2015-01-01

    This research aims to know how the Ethics and responsibility of PT TRAVEL Umrah conducts its travel business?. This background research of Various motivations variety PT TRAVEL Umrah in implementing its travel business. Is that motivation is not only a business commodity, so causing a few problems related to that Travel, among others, the cheapness of travel so that the number of Umrah pilgrims displaced and not so depart with many reasons such as the visa is not out or travel unclear. This ...

  11. DINAMIKA BISNIS TRAVEL UMROH SE KOTA PASURUAN DI ERA GLOBALISASI

    OpenAIRE

    Dewi Masitah

    2015-01-01

    This research aims to know how the Ethics and responsibility of  PT TRAVEL Umrah conducts its travel business?. This background research of Various motivations variety PT TRAVEL Umrah in implementing its travel business. Is that motivation is not only a business commodity, so causing a few problems related to that Travel, among others, the cheapness of travel so that the number of Umrah pilgrims displaced and not so depart with many reasons such as the visa is not out or travel unclear. This ...

  12. Dinamika Peran Negara dalam Proses Liberalisasi dan Privatisasi

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    Syamsul Ma'arif

    2015-12-01

    Full Text Available Liberalization and privatization are often associated with global demands for termination of state interference in business. The policy often result in dispute between neoliberalism and socialism. Neoliberalism perceives state interference in economic area as bad, damaging, an inefficient to economic life. State, which conduct the operation in political power logic, is perceived less or even not give the place for the expanding of healthy market structure and competitive. While socialism perceived state as central figure of economic with the centralized planning instrument and the ownership be on the hand of state. As economic system, socialism can be understood as an economic system in which the means of production, distribution, and exchange are publicly owned and operate. Since socialism assumes state as the most representative organization, so the meaning of owned and operated by public means the power of ownership and the mode of operation be on the hand of state. As political ideology, in its connection wit the economic control, socialism believe that the state should develop the economic planning and control on market operation. This paper prove that neoliberalism and the philosophy demands for termination of state role, in the reality, suffer a kind of paradox. On one hand, it trust market excellence so much over state. But on the other hand, it requires the active role of state to return the free market idea.

  13. Dinamika Dan Tantangan Masyarakat Islam Di Era Modernisasi

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    Siti Makhmudah

    2015-09-01

    Full Text Available As believed by many experts, that this world without exception is experiencing the grand process of modernization. According to Islamic teachings, the change is part of the laws and is one of human nature and the universe as a whole. Then an ordinary, if human, community groups and environmental changes. Considering the various problems-problems islam over both intetern and externally we can understand and learn, so that we can respond and seek bagaiamana way we tackle the problem of islam is to be free of things that are not desirable towards the creation of propaganda Islamiyah is good and right that blessed by Allah.These modern times to give an intellectual basis for reform in various fields, including in the field of religion. In Arabic, the update is known by the name Tajdid. As in the term, Tajdid formulated as efforts and activities to transform the lives of the people of the state of ongoing islamdari to the state to be embodied for the sake of welfare efforts, both globally and in the hereafter , at desired by Islam. Said renewal of Islam has the meaning of "modernization", ie the teachings of Islam that is relative and open to change and update.

  14. ULAMA DAN PESANTREN DALAM DINAMIKA POLITIK DAN KULTUR NAHDLATUL ULAMA

    Directory of Open Access Journals (Sweden)

    Wasisto Raharjo Jati

    2013-09-01

    Full Text Available The article endeavors to trace power relationship between muslim religious leaders (ulama and islamic boarding school (pesantren in the political dynamics of Nahdlatul Ulama (NU. Both entity are not only an essential element needed to pressure political and cultural for NU, but also the National Awakening Party (PKB as a political party for nahdliyyin. The existence of organizational conflicts that occurred in the PKB also influence the dynamics of the NU that resulted fragmentation among ulama and pesantren. The implication is there a divergence of politics and culture among ulama and pesantren in the base region of Central Java and East Java.

  15. DINAMIKA PENGANGGURAN TERDIDIK: TANTANGAN MENUJU BONUS DEMOGRAFI DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Sri Maryati

    2015-07-01

    Full Text Available According to the United Nations demographic transition that occurred in recent decades in Indonesia would be an opportunity for Indonesia to reach a demographic dividend in the period 2020-2030 . By the time the productive age population amounted to twice that of the non - productive population . These opportunities should be best utilized as it will only happen once and it can happen if the population of working age have a job and sufficient income . thus this demographic bonus can actually stimulate the economy of Indonesia in the future . But on the other hand, Indonesia is currently facing serious problems of labor that is still large numbers of educated unemployment . The number of unemployed educated annually feared will continue to grow as the number of college graduates also continue to grow , but not all college graduates can be accommodated in the workplace , consequently leads to an increase in the number of educated unemployed . The main purpose of this study is to analyze the dynamics of educated unemployment in Indonesia and the steps that need to be done by the government and people of Indonesia in order to face the era of demographic bonus, so it does not become a wave of mass unemployment, particularly educated unemployment in Indonesia.

  16. Feminisme dalam Sastra Jawa Sebuah Gambaran Dinamika Sosial

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    Sri Widati

    2009-06-01

    Full Text Available Artikel ini bertujuan membahas feminisme dalam sastra Jawa, salah satu sastra etnis di Indonesia yang masih eksis sampai saat ini. Sebelum kemunculan pengarang perempuan, perempuan dalam sastra Jawa ditulis oleh pengarang laki-laki sehingga mereka dideskripsikan sebagai makhluk tak berdaya dan setia pada pria, bukan sebagai sosok atau figur yang kuat. Baru tahun 1917-an, dengan munculnya pengarang perempuan muda dari Yogya dan Surabaya, persepsi feminisme dalam sastra Jawa berubah. Dalam karya-karyanya, mereka mendemonstrasikan solidaritas terhadap perempuan yang menjadi korban ketidaksetaraan gender. Saat ini, sastra Jawa feminis ditulis baik oleh pengarang perempuan maupun laki-laki. Pengarang perempuan menyuguhkan sebuah konsep feminisme yang mengarah pada kesetaraan gender, sementara pengarang laki- laki berusaha untuk membela perempuan tertindas dengan cara laki-laki Abstract: This article is aimed to discuss feminism in Javanese literature, one of the ethnical literatures in Indonesia which still exist up till now. Prior to the emergence of female authors, women in the Javanese literature had been written by male authors so that they had been described as being submissive and loyal to men instead of an image or figure of strong ones. Not until 1917s, by the emergence of young female authors from Yogya and Surabaya, did the perception of feminism in Javanese literature change. In the works, they have demonstrated solidarity to women who became the victims of gender inequality. At the present time, feminist Javanese literatures are written by either female or male author. Female authors present a feminism concept which leads to gender equality, whereas male authors make an effort to defend oppressed women by manly methods. Keywords: feminist, Javanese literature, gender equality, female authors

  17. Dinamika Kelompok Penerima CSR PLN Tarahan Lampung Selatan

    OpenAIRE

    Kusnani, Dedeh Kurniasih; Muljono, Pudji; Saleh, Amiruddin

    2015-01-01

    The study aims to: (1) analyze the level of group dynamics; (2) analyze relation between internal and external characteristics of members and group dynamics. The research uses survey method and was conducted in South Lampung. Numbers of samples are 50 respondents. Descriptive and correlational analysis was used to explain this research. The results of the research show that: (1) the level of group dynamics was low because the group goals are not specific, the structure is not clear, group rol...

  18. Dinamika Kekuasaan dalam Komunitas Jazz Yogyakarta 2002-2010

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    Oki Rahadianto Sutopo

    2010-07-01

    Full Text Available Previous studies about jazz in Indonesia tend to generalize and hold a bias against narration from the mainstream, they do not see the different narration from micro scope. Using Yogyakarta jazz community as an entry point, this study shows that jazz community is not a single entity, rather, it involved various identities including educational as well as social background. This paper also indicates contestation among different jazz community in Yogyakarta wich eventually shape the colour of jazz music in the city.

  19. Dinamika Baru Pemilihan Lokasi Bagi Perusahaan Ritel Sistem Franchise

    OpenAIRE

    Sujadi, Sujadi

    2010-01-01

    For retail companies for expansion of the franchise system is a must to be done. For that companies need an appropriate strategy to support the opening of new outlets. Strategies that can be done in addition to site selection strategy is qualitati1'ely Flexible manufacturing system (FMS, Just-In-Time (JIT) and total quality management ( TQM). Kata Kunci : Perusahaan Ritel, Sistem Franchise, FMS, JIT, TQM

  20. Dinamika Otonomi Tubuh Perempuan: Antara Kuasa dan Negosiasi atas Tubuh

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    Gabriela Devi Benedicta

    2011-07-01

    Full Text Available This paper discusses about sexuality and autonomy of woman’s body through a study of sexy dancers in entertainment industry in Malang, East Java. Entertainment industry, including night club industry is capital manifestation and contest arena of any kind of ideology like capitalism and patriarchy. However, woman still can show her autonomy of her body instead of being a commodity object. She can make her body as a subject. In this case, she, herself, becomes a doer of commodity of her body. The dynamic of woman’s authority of her body is influenced by a certain setting and context. It can be seen in social relation done by sexy dancers with other actors. She can have high bargaining position and negotiation of her body when she relates to a certain actor, but on the other side she may not have an autonomy of her body when she relates to another actor. The autonomy of her body is multi dimension and not absolute.

  1. PERSPEKTIF HUKUM ISLAM TENTANG DINAMIKA HUBUNGAN INDUSTRIAL DI INDONESIA

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    Ismed Batubara

    2013-12-01

    Full Text Available Islamic Law Perspective of the Dynamic of Industrial Relation in Indonesia. The dynamic of industrial relation in Indonesia has undergone very long history since Colonial period to the Reformation era. This essay tries to elucidate relation pattern of labor ideology which seem to be influenced by Liberalism and Communism followed by two extreme economic ideologies vis-à-vis Islamic system. The author asserts that although regulations pertaining to labor have been made available, disputes and disharmony between workers and company or employer still occur repeatedly. Substantially, the regulations encompass delicate problems which are evident form the fact that the government is incapable of handling labor problem efficiently. The author concludes that Islamic concept should become an alternative in dealing with industrial relation which emphasizing equality and just principles and thus it is free from authoritarianism and expoloistation of Capitalistic models as well as from dictatorship of Communism ideology.

  2. The Application of Non-Metallic Core Materials in a High-Temperature Reactor Experiment; Utilisation de materes non metalliques dans le coeur d'un reacteur experimental a haute temperature; Ispol'zovanie nemetallicheskikh materialov dlya aktivnoj zony vysokotemperaturnogo opytnogo reaktora; Empleo de materiales no metalicos en el nucleo de un reactor experimental de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Huddle, R. A.U.; Shepherd, L. R. [Organization for Economic Co-Operation and Development, Dragon Project, Atomic Energy Establishment, Winfrith, Dorset (United Kingdom)

    1963-11-15

    comportamiento de estos materiales en condiciones de funcionamiento normales. Se comunican los resultados de las investigaciones sobre irradiacion, asi como de los trabajos efectuados en los circuitos del reactor. El objetivo principal de este programa es el perfeccionamiento de los reactores de elevada temperatura refrigerados por gas para aplicarlos a la generacion de electricidad en condiciones rentables. (author) [Russian] Proekt vysokotemperaturnogo reaktora (DRAGON)sozdan dlya razrabotki tekhnologii vysokotemperaturnykh reaktorov s gazovym okhladitelem; v nem predusmatrivalos' sooruzhenie i ehkspluatatsiya opytnogo reaktora na 20 mgvt (tepl.). Reaktor, sooruzhenie kotorogo budet vskore zakoncheno, predstavlyaet soboj sistemu, okhlazhdaemuyu geliem; temperatura na vykhode iz aktivnoj zony budet dostigat' 750{sup o}C. V nem budet ispol'zovat'sya U-235 v kachestve goryuchego i torij v kachestve vosproizvodyashchego materiala. Kharakternoj osobennost'yu sistemy yavlyaetsya otsutstvie kakogo-libo metalla v aktivnoj zone. Vvidu togo, chto v reaktore dolzhny razvivat'sya ves'ma vysokie temperatury,' a imenno, 1050{sup o}C na poverkhnosti teplovydelyayushchego ehlementa i do 1500{sup o}C v naibolee sil'no nagrevaemykh tochkakh topliva, dlya ego sooruzheniya ispol'zovany ogneupornye nemetallicheskie materialy. Vse veshchestvo aktivnoj zony sosredotocheno v teplovydelyayushchem ehlemente, blagodarya chemu sootnoshenie mezhdu poverkhnost'yu teploperedachi i ob{sup e}mom aktivnoj zony dostigaet bol'shogo znacheniya, i, sledovatel'no, pozvolyaet dostigat' vysokoj srednej plotnosti ehnergii v sravnitel'no kompaktnoj sisteme. Kazhdyj teplovydelyayushchij ehlement sostoit ieh gruppy grafitovykh trubok, zapolnennykh grafitovymi tabletkami, soderzhashchimi rasshcheplyayushcheesya i vosproizvodyashchee veshchestva v vide karbidov. Gelievyj okhladitel' prokhodit po osi. kazhdogo teplovydelyayushchego sterzhnya i vyvoditsya u ego osnovaniya, okhladitel' zatem napravlyaetsya v ochistitel

  3. New Methods and Facilities for the Measurement of Physical Properties of Reactor Components and Irradiated Materials; Nouveaux Procedes et Instruments de Mesure des Proprietes Physiques des Elements de Reacteur et des Matieres Irradiees; Novye metody i sredstva izmereniya fizicheskikh s vojstv komponentov reaktora i obluchennykh materialov; Nuevos Metodos y Equipos para Medir Propiedades Fisicas de Componentes de Reactor y de Materiales Irradiados

    Energy Technology Data Exchange (ETDEWEB)

    Foerster, F.; Mueller, P. [Institut Dr. Foerster, Reutlingen, Federal Republic of Germany (Germany)

    1965-09-15

    kolebanija ili putem izmerenija polushiriny rezonansnoj krivoj. Privodjatsja primery izmerenij vosstanovlenija posle radiacionnogo.povrezhdenija i posle plasticheskoj deformacii, a takzhe primery stepeni gra- fitizacii. Opisyvajutsja obnaruzhenie defektov i kolebanija plotnosti grafitovyh blokov. Krome togo ob{sup j}asnjaetsja metod issledovanija zakreplenija tabletok iz UO{sub 2} v tonkostennyh austenitnyh trubkah. Opisyvaetsja special'naja pech' dlja izuchenija uprugogo i neuprugogo povedenija ''gorjachih'' obrazcov pri temperaturah ot 20 do 1000 Degree-Sign C. Obsuzhdaetsja kontrol' kachestva cvetnyh metallov putem izmerenija jelektroprovodnosti s pomoshh'ju vihrevyh tokov. Opisyvaetsja pribor dlja beskontaktnogo izmerenija jelektroprovodnosti cvetnyh metallov. Ob'jasnjaetsja sootnoshenie mezhdu jelektroprovodnost'ju i deformaciej pod naprjazheniem cvetnyh metallov i splavov. Osoboe vnimanie obrashhaetsja na izmerenie nebol'shih po razmeru obrazcov. Opisyvaetsja ustrojstvo dlja distancionnyh prjamyh izmerenij v ''gorjachej'' zone reaktora. Rassmatrivaetsja zavisimost' jelektroprovodnosti ot doz obluchenija. Opisyvaetsja pribor dlja izmerenija pronicaemosti, ostatochnoj magnitnoj indukcii i kojercitivnoj sily kak funkcii mehanicheskogo naprjazhenija, uprugoj i plasticheskoj deformacii i doz obluchenija. Opisyvajutsja izmerenija izmenenij magnitnyh svojstv kak funkcii uprugogo naprjazhenija i plasticheskoj deformacii. Rassmatrivaetsja vlijanie obluchenija na pronicaemost' i kojercitivnuju silu. Opisyvaetsja pribor dlja bystrogo izmerenija i neposredstvennogo opredelenija pronicaemosti komponentov iz nerzhavejushhej stali. Ob'jasnjaetsja sootnoshenie mezhdu pronicaemost'ju i soderzhaniem D ferrita. Rassmatrivajutsja rezul'taty izmerenij procentnogo soderzhanija D ferrita v svarnyh shvah trubok iz nerzhavejushhej stali i izmerenij osazhdenija D ferrita kak funkcii plasticheskoj deformacii (svobodnaja kovka toplivnyh jelementov reaktora). (author)

  4. The Problems of Controlling Defects in the Materials Used for the First Czechoslovak Nuclear-Power Station; Problemes de Controle des Defauts dans les Materiaux Utilises a la Premiere Centrale Nucleaire de Tchecoslovaquie; Problemy defektoskopicheskogo kontrolya stroitel'nykh materialov reaktora pervoj chekhoslovatskoj atomnoj ehlektrostantsii; Problemas de Control de Defectos en los Materiales Utilizados en la Primera Central Nuclear de Checoslovaquia

    Energy Technology Data Exchange (ETDEWEB)

    Radislav, Filipp [Zavody Im.V.I. Lenina, Pl' zen, Czechoslovakia (Czech Republic)

    1965-09-15

    . Igualmente, se compensa el efecto de la irregularidad del acoplamiento acustico; el dispositivo envia impulsos al dispositivo del registro a distancia. Las dimensiones del defecto se determinan con ayuda de un atenuador. En la actualidad, se esta montando una instalacion automatica que permitira proceder al control de la superficie de un cilindro vertical. En el caso de las soldaduras, es necesario efectuar el control en la parte exterior a temperatura elevada. Con esa finalidad, en la fabrica 'V.I. Lenin' d e Pilsen se ha construido un dispositivo especial que permite procecer a controles de gran exactitud a altas temperaturas. El control no destructivo de los elementos soldados se efectua igualmente por rayos X. La medicion de pequenosi espesores y del metal base de una soldadura se hace mediante rayos X caracteristicos, utilizando chasis especiales. En la radioscopia de piezas soldadas de gran espesor se recurre a un betatron de procedencia checoslovaca. En la memoria se describe la tecnica de los ensayos, los resultados obtenidos y se comparan las caracteristicas del mencionado betatron de 15 MeV con otro construido por la firma Siemens. (author) [Russian] Daetsja kratkoe opisanie korpusa reaktora pervoj chehoslovackoj atomnoj jelektrostancii. Vysokie tre- bovanija k konstrukcii i tehnologii izgotovlenija korpusa reaktora, vypolnennogo iz nizko- legirovannoj nestarejushhej stali (tolshhina stenok 650 mm), priveli k neobhodimosti razra- botki metoda 'svidetelej' dlja kontrolja prochnosti konstrukcii bez razrushenija osnovnogo materiala i svarnyh soedinenij. Dlja kontrolja kachestva osnovnogo materiala i svarnyh soedinenij v bol'shoj mere is- pol'zuetsja ul'trazvukovoj impul'snyj metod s primeneniem odnogo zonda. Daetsja opisanie metodiki ispytanij i ocenki pokazanij vo vremja issledovanija osnovnogo materiala, a takzhe metodiki ispytanija kachestva jelektroshlakovyh svarnyh soedinenij, svarnyh soedinenij, provedennyh v atmosfere uglekislogo gaza , i ruchnyh dugovyh

  5. RA reactor operation and maintenance; Pogon i odrzavanje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air.

  6. Oscillation characteristics of the reactor 'A'; Oscilatorne karakteristike reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Lolic, B [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1961-07-01

    In addition to good knowledge of reactor physical properties, design of the reactor oscillator demands determining of the oscillator operating points as well as oscillation reactor properties. This paper contains study of the RA reactor power changes due to oscillations in in one of the vertical experimental channels. It has been concluded that the reactor optimum operating conditions are attained when the oscillator operates at optimum points, and other parameters are determined dependent on the sensitivity of the method and reactor stability.

  7. Calibration of RB reactor power; Kalibrisanje snage reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Markovic, H; Ninkovic, M; Strugar, P; Dimitrijevic, Z; Takac, S; Stefanovic, D; Kocic, A; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1976-09-15

    The first and only calibration of RB reactor power was done in 1962, and the obtained calibration ratio was used irrespective of the lattice pitch and core configuration. Since the RB reactor is being prepared for operation at higher power levels it was indispensable to reexamine the calibration ratio, estimate its dependence on the lattice pitch, critical level of heavy water and thickness of the side reflector. It was necessary to verify the reliability of control and dosimetry instruments, and establish neutron and gamma dose dependence on reactor power. Two series of experiments were done in June 1976. First series was devoted to tests of control and dosimetry instrumentation and measurements of radiation in the RB reactor building dependent on reactor power. Second series covered measurement of thermal and epithermal neuron fluxes in the reactor core and calculation of reactor power. Four different reactor cores were chosen for these experiments. Reactor pitches were 8, 8{radical}2, and 16 cm with 40, 52 and 82 fuel channels containing 2% enriched fuel. Obtained results and analysis of these results are presented in this document with conclusions related to reactor safe operation.

  8. Chemical dosimetry at the RA reactor; Hemijska dozimetrija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Gal, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This report presents the results of measurements of absorbed doses axial and radial distribution in the vertical experimental channels of the RA reactor. Measurements were done in channels VK-5, VK-7, VK-9 and GF-36. Results were compared to the results of calorimetry measurements and measured neutron flux values performed by other laboratories. Fricke and oxalate dosemeters were used in addition to the cobalt indicators.

  9. RB reactor noise analysis; Analiza sumova reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Velickovic, Lj; Markovic, V; Jovanovic, S [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed.

  10. Dosimetry system of the RB reactor; Dozimetarski sistem reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Lolic, B; Vukadin, D [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1962-07-01

    Although RB reactor is operated at very low power levels, safety and dosimetry systems have high importance. This paper shows detailed dosimetry system with fundamental typical components. Estimated radiation doses dependent on reactor power are given at some characteristic points in the rooms nearby reactor.

  11. Controlled Nuclear Fusion Research, September 1965: Review Of Experimental Results; Issledovaniya v oblasti upravlyaemogo yadernogo sinteza/sentyabr' 1965 g. obzor rezul'tatov ehksperimentov

    Energy Technology Data Exchange (ETDEWEB)

    Spitzer, Lyman Jr. [Princeton University, Princeton, New Jersey (United States)

    1966-04-15

    To my way of thinking the most significant milestone of the present meeting is the substantial body of evidence that has been presented on the hydromagnetic stabilization of open-ended systems. The success of minimum magnetic-field ('minimum-B') configurations in stabilizing a plasma marks one more area where theory and experiment in the field of plasma physics have been brought together with gratifying results. Let me go back a little into history and discuss the gradual growth of our information on hydromagnetic instabilities generally. Many of you will remember that hydromagnetic theory was applied to the self-pinched discharge in the early years of the controUed fusion programme. The predictions of this theory were very shortly fulfilled by the observations; the effects were so unmistakable that it was not difficult to compare the theory with the observations. On the streak pictures of the linear or toroidal discharges that were obtained in those early years one saw clearly the diffuse plasma column, which first contracted to a narrow filament and then started to distort and kink until finally it hit the wall. Under some conditions the plasma was observed to break up into a series of blobs like a string of sausages. Since the behaviour was exactly what the theory had predicted, it took no very great experimental wisdom to conclude that observations had confirmed theory.

  12. Development of Non-Metallic Fuel Elements for a High-Temperature Gas-Cooled Reactor; Mise au point d'elements combustibles non metalliques pour un reacteur a haute temperature, refroidi par un gaz; Razrabotka nemetallicheskikh teplovydelyashchikh ehlementov dlya vysokotemperaturnogo reaktora s gazovym okhlazhdeniem; Elementos combustibles no metalicos para un reactor de temperatura elevada refrigerado por gas

    Energy Technology Data Exchange (ETDEWEB)

    Liebmann, B.; Schafer, L.; Spener, G. [NUKEM, Nuklear-Chemie und -Metallurgie G.m.b.H., Wolfgang bei Hanau, Federal Republic of Germany (Germany)

    1963-11-15

    destinados al reactor de alta temperatura refrigerado por gas de la Brown-Boveri/Krupp Reaktorbau GmbH, se investigaron y desarrollaron dos conceptos de elemento combustible. El elemento consiste en ambos casos en una esfera de grafito de 6 cm de diametro que encierra una pastilla cilindrica de combustible de unos 20 mm de diametro y 16 mm de altura. La diferencia entre ambos conceptos estriba en el tipo de combustible y en la forma de preparar las esferas de grafito. En el primero, el combustible se prepara mezclando U{sub 3}O{sub 8} y grafito, prensando esta mezcla en pastillas y haciendo que ambos componentes reaccionen en un horno al vacio a 1800{sup o}C. La razon atomica U : C es 1:45. Como este tipo de pastilla combustible no retiene cuantitativamente los productos de fision, fue necesario impregnar la esfera de grafito para hacerla impermeable y mejorar su poder de retencion. De este modo, se lograron permeabilidades del orden de 10{sup -6}cm{sup 2}/s . Con arreglo al segundo concepto, el combustible consiste en una solucion solida de UC en ZrC recubierta de una capa de ZrC. La razon molar UC : ZrC asciende a 1 : 20. La pastilla combustible se preparo del modo siguiente: se mezclaron UO{sub 2}, ZrO{sub 2} y grafito y se prensaron en pastillas que se hicieron reaccionar para obtener los carburos, que a su vez se trituraron en un molino de bolas, para volver a prensarse a 2000{sup o}C. De este modo, se alcanzaron densidades superiores al 95% del valor teorico. La memoria describe en detalle la preparacion y algunas de las propiedades fisicas de las pastillas combustibles. Se espera que este tipo de combustible retenga suficientemente los gases de fision y permita el empleo de esferas de grafito no impregnadas. La memoria examina tambien otras ventajas de esos combustibles. [Russian] V svyazi s rabotami po sovershenstvovaniyu seplovydelyayushchikh ehlementov dlya vysokotemperaturnogo reaktora s gazovym okhlazhdeniem ''Obshchestvom stroitel'stva reaktorov Braun- Boveri

  13. Ultrasonic Water-Gap Measurements in MTR Fuel Elements; Mesure par Ultrasons des Espaces Intercalaires dans les Elements Combustibles des Reacteurs d'Essai de Materiaux; Izmereniya vodyanogo zazora v teplovydelyayushchikh ehlementakh dlya materialovedcheskogo reaktora s pomoshch'yu ul'trazvuka; Medicion Ultrasonica de la Capa de Agua en Elementos Combustibles para Reactores de Ensayo de Materiales

    Energy Technology Data Exchange (ETDEWEB)

    Deknock, R. [Metallurgy Department, S.C.K./C.E.N., Mol (Belgium)

    1965-10-15

    en un convertidor tiempo-tension con circuitos logicos transistorizados. El instrumento permite un ajuste continuo del cero para cualquier espesor-arbitrario de la capa de agua entre 2 y 4 mm, con lo cual posibilita un registro con el cero en el centro de la escala. Ademas, cualquier intervalo deseado de 100 {mu}m puede dar una tension estable de 1 V a la salida para accionar un registrador. Se puede medir facilmente cualquier variacion en el espesor del agua con una precision de 5 {mu}m. Se han medido con este metodo varios elementos combustibles, y los resultados y la reproducibilidad fueron muy satisfactorios. (author) [Russian] Sil'nye potoki teplo- vyh nejtronov, kotorye obychno voznikajut v novejshih reaktorah dlja ispytanija materialov, javljajutsja podhodjashhim s r e d s t v om ravnomernoj teploperedachi i nadezhnogo otvoda tepla, s pomoshh'ju kotorogo mozhno izbezhat' obrazovanija para v bol'shih ob{sup e}mah. Krome togo, v celjah kontrolja nad obshhim raspuhaniem i povedeniem reaktornogo topli- va izmerjajut vodjanoj zazor pri jeksperimentah posle obluchenija s otrabotannymi teplovy- deljajushhimi jelementami. S jetoj cel'ju byl razrabotan zond dlja izmerenija 3 - m m vodjanogo zazora teplovydeljaju- shhego jelementa ispytatel'nogo reaktora BR-2 dlinoj bolee 1 m , v osnovu kotorogo polozhen princip ul'trazvuka. Pri jeksperimentah posle obluchenija izmeritel'nyj zond dolzhen dej- stvovat' v teplovydeljajushhem jelemente, pogruzhennom v bassejn na glubinu ne menee 6 m . Zond mozhet vyderzhat' pogruzhenie v vodu prodolzhitel'nyj period vremeni, i on ne podver- gaetsja vozdejstviju obychnyh doz gamma-obluchenija. Hotja sistema dejstvuet na osnove obychnogo metoda otrazhenija impul'sov, ona pozvo- ljaet razdeljat' ispuskaemye i otrazhennye impul'sy s pomoshh'ju 10 Mgc ferrojelektriches- kogo kristalla, kotoromu svojstvenno bol'shoe rassejanie jenergii. Mozhno ispol'zovat' zapis' pokazanij oscilloskopa, v kotorom vremja registriruetsja na gorizontal'noj osi

  14. Design of the Small Rods Forming the Fuel Element of the First Charge of the EL4 Reactor. Cladding Problems; Etude des crayons constituant l'element combustible du premier jeu d'EL4 - probleme de la gaine; Problema pokrytiya nebol'shikh steeknej, obrazushchikh toplivnyj ehlement pervoj zagruzki reaktora EL.4; Estudio de las barras que constituyen los elementos combustibles de la primera carga del reactor EL4 - el problema de las vainas

    Energy Technology Data Exchange (ETDEWEB)

    Bailly, H.; Ringot, C.; Weisz, M. [Centre d' Etudes Nucleaires de Saclay (France)

    1963-11-15

    ) [Spanish] Las vainas de los elementos combustibles de la primera carga del reactor EL-4 son de acero inoxidable. La eleccion del grado del acero y del espesor de la vaina depende de la resistencia a la corrosion y de la resistencia mecanica que se deseen. Las tensiones y las temperaturas de funcionamiento no permiten concebir una vaina que resista durante toda la vida util del elemento combustible si no se uti liza un grado de acero muy resistente y un espesor,superior a 0,5 mm. Se admite que la vaina se adhiera al combustible por fluencia: la deformacion por juego en sentido diametral puede producir una ovalizacion y un pliegue; el juego longitudinal puede dar lugar a flexiones de la vaina. Se han realizado muchos ensayos con vainas de 0,3 a 0,4 mm de espesor para estudiar el modo de deformacion en funcion de los juegos. Para estar seguros de que no se produciran ovaliza ciones con los espesores previstos, y para mantener lo mas baja posible la temperatura en el interior de la barra es preciso eliminar completamente el juego durante la fabricacion. (author) [Russian] Dlya pervoj nagruzki toplivnogo ehlementa reaktora EL.4 ispol'zuetsya pokrytie iz nerzhaveyushchej stali. Vybor splava i tolshchiny pokrytiya svyazan s korrozionnymi i mekhanicheskimi svojstvami metalla. Rabochie napryakheniya i temperatury ne dast vozmokhnosti sproektirovat' pokrytie, stojkoe v techenie vsego sroka sluzhby toplivnogo ehlementa; dlya dostikheniya takoj tseli neobkhodimo bylo by ispol'zovat' ochen' stojkoe pokrytie tolshchinoj bolee 0,5 mm. Dopuskaetsya, chto pokrytie v protsesse spekaniya soedinyaetsya s toplivom. Diametral'noe izmenenie toplivnykh ehlementov mokhet privesti k obrazovaniyu oval'noj formy i nerovnostej; prodol'noe izmenenie sistemy toplivnykh ehlementov mokhet privesti k prodol'nomu izgibu pokrytiya. Byli provedeny mnogochislennye opyty v otnoshenii tolshchiny pokrytiya v predelakh' 0,3 - 0,4 mm s tem, chtoby vyyasnit' kharakter izmeneniya toplivnykh ehlementov v zavisimosti

  15. Dinamika populasi wereng punggung putih, sogatella furcifera Stål (Hemiptera: Delphacidae di jawa tengah

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    I Nyoman Widiarta

    2017-02-01

    Full Text Available A field study was conducted at paddy fields in Petarukan and Pekalongan regencies of Central Java province during wet season crop 1989/90 and 1990/91 to elucidate population dynamic of whitebacked planthopper, Sogatella furcifera Stål. Seven and three observation fields were set up in 1989/90 and the 1990/91, respectively. Cisadane rice cultivar was transplanted following the usual farmer’s parctices except that no pesticide was applied. The population of the whitebacked planthopper and the brown planthopper, (Nilaparvata lugens Stål were sampled by using an insect suction catcher, a farmcop. Identification of generation was based on thermal constant required by the whitebacked planthopper to complete one generation and mean population density was calculated by graphical method. Two distinct seasonal population growth patterns were identified. The population with short population growth pattern completed four generations in one crop season in which their population density increased consecutively in two generations since immigrant generation, and thereafter decreased. The population with long population growth completed five generations in one crop season in which their population density increased consecutively in three generations, and thereafter decreased. The density of brachiptera adults determined 90% of the total population density. The proportion of brachiptera adults were not correlated with large nymphal density in both vegetative and generative stages of rice. The proportion of brachiptera adults showed significant negative linear regression with population density of the brown planthopper. Therefore, interspesific competition determined the proportion of wingform and population dynamics of the whitebacked planthopper.

  16. DINAMIKA KOALISI PARTAI-PARTAI POLITIK DI INDONESIA MENJELANG DAN SETELAH PEMILIHAN PRESIDEN TAHUN 2014

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    R. Widya Sumadinata

    2016-10-01

    Full Text Available This paper examines the dynamics of a coalition of political parties in Indonesia, especially in the presidential election of 2014 through a Fuzzy approach. The results of this study indicate that the ideology of political parties cannot be used as coalition preferences in absolute terms. The formation of the coalition is heavily based on seeking office interest. In other words, political parties in Indonesia have not been able to gain funding independently but still rely on state resources that obtained through its members in the executive and legislative offices. However, fuzzy logic modeling to the coalition as conducted in this writing is still very simple and need to test rigor of mathematical models that can describe the real condition of the behavior of political parties to form a coalition.

  17. Identifikasi Dinamika Spasial Sumberdaya Mangrove di Wilayah Pesisir Kabupaten Demak Jawa Tengah

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    Septiana Faturrohmah

    2017-04-01

    Full Text Available Sebagai salah satu sumberdaya pesisir, hutan mangrove memiliki fungsi sosial ekonomi, fungsi ekologis, dan fungsi fisik. Namun demikian, sebagian hutan mangrove di pesisir Kabupaten Demak berada pada kondisi rusak. Menurut data dari Dinas Kelautan dan Perikanan Kabupaten Demak, pada tahun 2011 luas ekosistem mangrove di Kabupaten Demak sekitar 8 % dalam kondisi rusak. Sebagai salah satu upaya perlindungan wilayah pesisir di Kabupaten Demak, maka diperlukan revitalisasi hutan mangrove melalui kegiatan konservasi. Kegiatan konservasi dapat berjalan lebih efektif apabila diawali dengan proses perencanaan berdasarkan data-data, inventarisasi, dan pemantauan. Maksud penelitian ini adalah untuk memberikan kontribusi terkait arahan spasial perencanaan konservasi mangrove di wilayah pesisir Kabupaten Demak melalui identifikasi distribusi dan luas tutupan hutan mangrove serta dinamikanya dalam kurun waktu lima tahun terakhir. Analisis yang digunakan adalah analisis deskriptif kualitatif dan kuantitatif sederhana dengan bantuan data citra penginderaan jauh dan Sistem Informasi Geografis. Hasil penelitian menunjukkan bahwa dalam kurun waktu lima tahun terakhir (2010-2015, distribusi spasial dan luasan hutan mangrove di wilayah pesisir Kabupaten Demak secara umum tidak mengalami perubahan yang besar, yaitu hanya mengalami penurunan seluas 68,17 Ha. Akan tetapi, dalam pengamatan yang lebih detail pada lingkup kecamatan dan desa, perubahan distribusi dan luasan terlihat lebih variatif.   As the one of coastal resource, mangrove has socio-economic, and physical functions. Unfortunately, certain extent of the mangrove forests in coastal area of Demak Regency has been degraded over time. Department of Marine and Fisheries of Demak Regency has been informed that at 2011, about 8 % of mangrove area in Demak Regency is in damaged condition. In order to protect the coastal area of Demak Regency, it necessary to revitalize mangrove forest by conservation programme. Conservation can be effective if started by data inventaritation and monitoring-based planning. The aim of this study is to give a contribution on spatial planning of mangrove conservation in coastal area of Demak Regency through mangrove distribution, area, and its dynamics identifications. The dynamics of the mangrove area will be identified for the last five years. The analysis method used in this study is based on qualitative assessment aided by support of remote sensing data and Geographic Information System. The study results show that in the last five years (2010-2015, mangrove forests in Demak Regency didn’t change drastically, instead it is only decreased around 68,17 Hectars. However, observation and analysis on more detailed scale (sub district and village level shows that the dynamics of mangrove area and its distribution varies significantly.

  18. DINAMIKA POPULASI Anopheles Aconitus KAITANYA DENGAN PREVALENSI MALARIA DI KECAMATAN CINEAM, TASIKMALAYA

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    Amrul Munif

    2012-10-01

    Full Text Available A study on the correlation of population dynamik An. aconitus with malaria prevalence was conducted in Cineam sub-district, Tasikmalaya district, West Java from August 1998 to March 2000. In 1996, outbreaks of malaria did not only occur in the coastal areas but was also spread throughout the more remote areas. Malaria transmission can be detected by the presence of infectious gametocyte dan non-immune individuals, as well as by looking at environmental factors (rainfall and also the density of vector population. The intensity of malaria transmission and the degree of malaria prevalence are affected greatly by the last factor.   The intensity is also determined by the degree of contact between the person and the vector. An. aconitus have been suspected as malaria vector in Cineam sub-district, Tasikmalaya district. The observation of the bionomics wich one component of mosquitoes and its relationship with malaria prevalence as well as the determination of Anopheles spp. as malaria vectors in endemic areas should be given attention as an effort in preventing malaria outbreaks. The high density of vector mosquitoes is partly caused by their high diversity. Determination of the prevalence value is based on the Slide positifrate (SPR that was obtained from analyzing blood samples of the  population. There was an examination on passive case detection (PCD, active case detection  (ACD, and mass blood survey (MBS of the population beforehand. Methods used in surveying dan catching the vector mosquitoes include using humans as bait both inside and outside the house, using light trap, by resting, and also spraying. The longitudinal survey methods were used. Each catched mosquito was identified by looking at its morphological features.The transmission of malaria was found to occur all year round with the highest peak found in August 1998 (SPR= 4.9%, but then declined drastically in May (SPR=2.46% and July 1999 (SPR= 2.4% The occurrence of human biting by An. aconitus was the highest in January with a man biting rate (MBR index of 2.3, while that of An. barbirostris was the highest in October with a MBR index of 6.75.  There is no significant difference between biting occurrence inside dan outside the house (P< 0.05. In contrast, the population density of An. aconitus was not found all year round, especially in August, September, October, dan December 1998, as well as in February and September 1999, but managed to show the highest parity in June 1999 (33. On the other hand, as the malaria prevalence increased, the population of An. aconitus also increased. This relationship shows is not significant correlation with regression equation Y= -0.0042 X+ 1,51, R = 0.044, p>0.05.

  19. Dinamika Migrasi Desa Kota di Indonesia: Karakteristik dan Kehidupan Migran Baru di Tangerang, Propinsi Banten

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    Fina Itriyati

    2016-09-01

    Full Text Available This paper attempts to examine the dynamics of recent migration in Tangerang city, the major industrial city on the outskirts of Jakarta. In this paper we fist deal with migration patterns associated with economic and social change in Indonesia, both historically and in more recent times especially in Tangerang city. The fild research conducted both in Tangerang city and Tangerang district in 2008 and as part of collaborative research on rural urban migration in Indonesia. Using data gathered from household urban survey, this focuses on the general fiures, characteristics of recent migrants (those moving to the city in the past fie years, compare to lifetime migrants (those living in the city for fie years or more and non migrants in Tangerang. The paper also provide overview how recent migrants make adjusments on urban environments and also how recent migration has strong relationship with adolescents’ life, youth migration and empowerment.

  20. DINAMIKA PLIVAČKIH REZULTATA U CRNOJ GORI U PERIODU 1997-2004 GODINE

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    Branislav Radulović

    2005-04-01

    Full Text Available Social environment imposes parameters, later excepted as strict criteria, in swimming. These parameters are expresses in specific time for a specific swimming discipline. It means that the success in swimming is measured with time results. Proper measure for comparison of different swimming results is based on the best world results comparative tables. The most used tables today are LEN (at European level and FINA (at world level. These are applied at official competitions of highest rang. However, having in mind nature of his work, the author decided to use British point tables. British point tables, full of additional parameters, give more objective and more precise differences between achieved results. The author’s work comprises the best swimming achievements for each year with regard to different age groups. Each result was placed into a specially designed program and ascribed to corresponding age, sex and discipline. Consequently, he got the graphic chart showing the dynamics of the best results` development in Montenegro. They were compared according to set criteria as well as to global trends. The outcomes of the research are following conclusions: the results are getting worse with time, there are huge oscillations within the same age groups and, according to the global analyses, the best results are products of few swimmers. All this leads to the conclusion that it is absolutely necessary to work toward enlargement of the swimming potential.

  1. DINAMIKA ISLAM KULTURAL: Studi atas Dialektika Islam dan Budaya Lokal Madura

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    Paisun Paisun

    2010-08-01

    Full Text Available Throughout the history, it is well-known that the ingress and the progress of Islam in Indonesia, especially in Java and Madura, were held almost without any tension and conflict. Even in the societies with some former belief systems such as Animism and Buddhism, Islam was easily accepted as a religion that brings peace within its teachings. During periods, Islam and local cultures perform a dialectical relationship and give rise to local variances of Islam, such as Javanese Islam, Madurese Islam, Sasak Islam, Sundanese Islam, etc. Those variances of Islam are the result of an acculturation process between Islam with the local cultures. In other word, this process is also called as “inculturation”. These local variances of Islam, further termed as the “cultural Islam” in this paper, have become a characteristics of Indonesian Islamic societies phenomenon which are different from Middle-East’s Islamic society and European Islamic society. This paper discusses about the Madurese Islam, one of these cultural Islam’s variances. Dialectical process between Islam and the local culture of Madura in turn generates a unique Madurese Islam, which is distinctive and esoteric. In its further developments, Islam and Madurese tradition are seen as unity and inseparatable, though people can still distinguish one another. This study seeks to uncover and expose the Islamic cultural dynamics that exist and grow in Madura: how big is the change that occurred, in which part, and what factors underlie these changes. This study provides benefit in enriching our scientific study about Indonesian cultural heritage, especially about the dialectical relationship between Islam and Madurese local culture.

  2. UPAYA MENINGKATKAN EMPATI DALAM BERINTERAKSI SOSIAL MELALUI DINAMIKA KELOMPOK PENDEKATAN EXPERIENTIAL LEARNING

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    Septi Wulandari

    2012-12-01

    Full Text Available This study was conducted based on the phenomenon that is in junior high school of state 9 Semarang which shows that the students who have empathy in social interactions is low. The purpose of this study to determine the efforts and success in increasing empathy in the social interaction of students through experiential learning approach to group dynamics. This research is action research guidance and counseling. Subjects were 10 students who had low empathy in social interaction. Data collection methods used were psychological scales and observation. Wilcoxon test results obtained thitung 55.0 > 8.0 TTable or imply Ha accepted and Ho rejected. These results demonstrate empathy in students' social interaction can be improved after getting the group dynamic experiential learning approach. Empathy in the social interaction of students before gaining experiential learning group dynamics approach to the low category 51.19%. After obtaining the dynamics of group experiential learning approach with 81.96% higher category. After the I cyclus increased empathy in social interactions by 14.93% from the initial conditions. After the II cyclus of empathy in social interactions increased by 15.84% of cyclus I. In addition, students progressing better behavior seen from the increasing indicators sensitive to others, trust, understanding, awareness of others, openness, social contacts, and social communication.

  3. Upaya Meningkatkan Empati Dalam Berinteraksi Sosial Melalui Dinamika Kelompok Pendekatan Experiential Learning

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    Septi Wulandari

    2012-12-01

    Full Text Available This study was conducted based on the phenomenon that is in junior high school of state 9 Semarang which shows that the students who have empathy in social interactions is low. The purpose of this study to determine the efforts and success in increasing empathy in the social interaction of students through experiential learning approach to group dynamics. This research is action research guidance and counseling. Subjects were 10 students who had low empathy in social interaction. Data collection methods used were psychological scales and observation. Wilcoxon test results obtained thitung 55.0 > 8.0 TTable or imply Ha accepted and Ho rejected. These results demonstrate empathy in students' social interaction can be improved after getting the group dynamic experiential learning approach. Empathy in the social interaction of students before gaining experiential learning group dynamics approach to the low category 51.19%. After obtaining the dynamics of group experiential learning approach with 81.96% higher category. After the I cyclus increased empathy in social interactions by 14.93% from the initial conditions. After the II cyclus of empathy in social interactions increased by 15.84% of cyclus I. In addition, students progressing better behavior seen from the increasing indicators sensitive to others, trust, understanding, awareness of others, openness, social contacts, and social communication.

  4. Dinamika Pendidikan Masyarakat Nelayan Di Desa Pandangan Wetan Kecamatan Kragan Kabupaten Rembang

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    Moh. Saiful Fatwa

    2017-03-01

    Full Text Available Public of education level affects the mindset and perceptions about the important role of education for their children. The purpose of this study was to determine the social conditions of fishermen, Fishermen's commitment to education and family know the child's behavior in the  Fishermen families Desa Kragan Pandangan wetanRembang. The method used is qualitative, and data collection techniques is using interviews, observation and document study. The data analysis technique used in this study is an interactive model with step data collection , data reduction , data presentation and conclusion. The validity of the data is done by means of triangulation of methods and sources.Results showed (1 in general and most of the views of parents/fishing Pandega to education is low, (2 Fishermen Family Commitment to education children affected fishermen families where parenting in general and most of the families of fishermen inthe village of view Wetan District of Kragan is authoritarian parenting and permissive parenting, because many parents in the Desa Kragan Pandangan Wetan Rembang is overbearing in certain fields such as educatio, (3 in general, and most forms of social behavior of children, including good. Any violation by the respondent is still in reasonable category. Based on the observations by researchers in the environment where he lives, the children of fishermen Pandega majority being nice , hardworking and obedient to his parents .

  5. ANALISIS DINAMIKA SEBARAN SPASIAL SEDIMENTASI MUARA SUNGAI CANTUNG MENGGUNAKAN CITRA LANDSAT MULTITEMPORAL

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    Zulaiha Zulaiha

    2017-01-01

    Full Text Available ABSTRACT: Given the pivotal role played by the Cantung River for the supervision and management of the public good becomes important. Incoming sediment load can damage the uncontrolled flow conditions of the Cantung river and estuary. Observations of suspended sediment can take advantage of multitemporal Landsat imagery. This study uses Landsat satellite image data corrected 5TM March 5, 1992 data acquisition path/row 117/62, Landsat data acquisition 5TM 22 May 1997 path/row 117/62, Landsat data acquisition 5TM March 27, 2000 the path/row 117/62. Several stages in processing the image, that is the conversion of DN to reflectance values, cropping, water-not water secession, and the class divide sediment concentration by density slicing technique. Spatial distribution of suspended sediment in the estuary of the Cantung River Landsat image processing results 5TM March 5, 1992, Landsat 5TM May 22, 1997, and March 27, 2000 Landsat 5TM show distribution patterns of suspended sediment from the River Cantung the same direction, that is northeast. Sediment concentrations were detected in the Landsat image processing 5TM March 5, 1992 the largest-value 27,564096 mg/l and the smallest 14,886048 mg/l. Sediment concentrations were detected in the Landsat image processing 5TM May 22, 1997 the largest-value 121,476776 mg/l and the smallest 12,647415 mg/l. Sediment concentrations were detected in the Landsat image processing 5TM March 27, 2000 most valuable 159,256704 mg/l and the smallest 10,584161 mg/l. Getting away from the effect Cantung River estuary sediment concentration of river flow Cantung tends to get smaller. Changes in the distribution area of the sediments of March 5, 1992 until March 27, 2000 amounted to 450 m2/year.   Keywords: Remote Sensing, Sedimentation, Landsat, Cantung River

  6. Penerapan Dinamika Fluida dalam Perhitungan Kecepatan Aliran dan Perolehan Minyak di Reservoir

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    Dwi Listriana Kusumastuti

    2014-12-01

    Full Text Available Water, oil and gas inside the earth are stored in the pores of the reservoir rock. In the world of petroleum industry, calculation of volume of the oil that can be recovered from the reservoir is something important to do. This calculation involves the calculation of the velocity of fluid flow by utilizing the principles and formulas provided by the Fluid Dynamics. The formula is usually applied to the fluid flow passing through a well defined control volume, for example: cylinder, curved pipe, straight pipes with different diameters at the input and output, and so forth. However, because of reservoir rock, as the fluid flow medium, has a wide variety of possible forms of the control volumes, hence, calculation of the velocity of the fluid flow is becoming difficult as it would involve calculations of fluid flow velocity for each control volume. This difficulties is mainly caused by the fact that these control volumes, that existed in the rock, cannot be well defined. This paper will describe a method for calculating this fluid flow velocity of the control volume, which consists of a combination of laboratory measurements and the use of some theories in the Fluid Dynamics. This method has been proofed can be used for calculating fluid flow velocity as well as oil recovery in reservoir rocks, with fairly good accuration.

  7. DINAMIKA POPULASI MONYET EKOR PANJANG (MACACA FASCICULARIS DI HUTAN WISATA ALAS KEDATON TABANAN

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    I Gede Soma

    2012-11-01

    Full Text Available Overall population dynamic were observed in identified individuals between August andOctober 2008, in large group of long failed macaques in the AlasKedaton, Bali. Totalpopulation was 364 monkeys consisted of 54 (14,8% adult males, 104 (28,6% adultfemales, 164 (45,1% juvenile and 42 (11,5% infant. They were divided into 4 differentsmall social groups i.e., Parking area group, North area group, Centre area group and Southarea group. Ratio of adult male and adult female was 1: 2.Population densitiesof Macaca fascicularisin Alas Kedaton were 30 monkeys / Ha andpopulation natalities were 11, 5%.

  8. DINAMIKA EKOLOGI LAUT SULAWESI (WPP 716 SEBAGAI DAYA DUKUNG TERHADAP PERIKANAN MALALUGIS (Decapterus macarellus Cuvier, 1833

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    Puji Rahmadi

    2015-06-01

    Full Text Available Ikan Malalugis adalah ikan pelagis kecil yang merupakan hasil tangkapan utama nelayan di perairan Laut Sulawesi. Pada tahun 2012 dilaporkan bahwa perikanan pelagis kecil menjadi salah satu hasil perikanan yang penting, dan hasil tangkapan yang dominan dari perikanan pelagis kecil tersebut adalah ikan malalugis biru (Decapterus macarellus. Jenis ikan malalugis memiliki sifat bermigrasi dan membentuk gerombolan kecil yang mana sangat dipengaruhi oleh kondisi lingkungannya. Tipe arus pasut di Teluk Manado (Laut Sulawesi merupakan arus pasut bolak balik (reversing current. Banyaknya arus yang begitu aktif merupakan salah satu faktor yang mendukung habitat ikan malalugis. Diduga kekhasan sifat distribusi arus di daerah laut Sulawesi ini yang membuat kelimpahan ikan malalugis relatif tinggi di perairan Sulawesi Utara dibandingkan dengan daerah perairan lainnya di Indonesia. Kelimpahan ikan malalugis yang tinggi mendorong ikan ini menjadi komoditas penting dalam sektor perikanan di Laut Sulawesi. Meski demikian pada tahun 2012 dilaporkan bahwa tingkat produksi ikan malalugis mengalami penurunan. Hal ini diduga karena terlalu tingginya tingkat eksploitasi atau diakibatkan oleh adanya perubahan dalam kondisi ekosistem ikan tersebut di Laut Sulawesi. Oleh karena itu studi ini dilakukan untuk mengkaji tingkat daya dukung lingkungan terhadap keberlangsungan sumberdaya perikanan malalugis di wilayah perairan Laut Sulawesi. Malalugis fish is a small pelagic fish that constitute the main catch of fishermen in the waters of North Celebes Sea. In 2012 it was reported that small pelagic fishery became one of the important fishery products and it was dominated by the species of Malalugis (Decapterus macarellus. This species has a typical behavior which was highly mobility and forming fish schooling and strongly influenced by environmental conditions. The type of tidal current in North Sulawesi coast is reversing current. This kind of current could make a very active current in the water which is suitable for the habitat of Malalugis. This distinctiveness of current was considered as a trigger for relatively high abundance of Malalugis in this area compared to its abundance in other water body of Indonesian territory. In 2012, total catch of this species has been reported to be decreased; thismay caused by either high level of exploitation nor changing on its habitat or even both. This study was conducted to investigate the capability of ecosystem and habitat of Malalugis to support its sustainability.

  9. Dinamika Hubungan Islam dan Agama Lokal di Indonesia: Pengalaman Towani Tolotang di Sulawesi Selatan

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    Hasse J

    2016-08-01

    Full Text Available This study focuses on the relation between Islam and local religion in Indonesia. The common relation pattern occurred in each encounter between Islam and local religion; is that fulfilled by the compromise and the conflict at the same time. In the case at South Sulawesi, the cultural accommodation of Towani Tolotang was able to perform it   on a good situation that brought them to be accepted by the Muslims majority without relinquishing their former believes. In certain condition, despite the underlying differences between the two, both Islam and Towani Tolotang can hardly be socially separated from one another. Although the state admitted six religions only, but practically we found various types of religions others. Their adherents strive doing any efforts to keep their existence and continuity for their future. The result of this study shows that Towani Tolotang in its encounter with Islam emerged some types of conflicts and compromises on its dynamics.  

  10. Dinamika Tata Kelola Kebijakan Industri Penyiaran dan Telekomunikasi Indonesia Menuju Konvergensi

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    Vience Mutiara Rumata

    2016-03-01

    Full Text Available Abstrak Konvergensi antara penyiaran dan telekomunikasi di Indonesia tidak terhindarkan seiring dengan perkembangan teknologi informasi dan komunikasi (TIK serta ketatnya persaingan dalam industri keduanya. Kedua industri telah mengintegrasi TIK sebagai nilai tambah dari layanan ataupun produk yang ditawarkannya. Meski demikian, tata kelola kedua industri ini masih terpisah yakni melalui UU Penyiaran tahun 2002 dan UU Telekomunikasi tahun 1999. Di saat RUU konvergensi telematika belum menemukan titik terang, regulator berupaya merevisi kedua UU tersebut. Studi ini bertujuan untuk memahami relasi kekuasaan serta pandangan para pemangku kebijakan dalam mengatur industri penyiaran dan telekomunikasi di era konvergensi. Teknik pengumpulan data dilakukan dengan cara wawancara mendalam kepada narasumber yang dipilih secara purposif yakni Kemkominfo, KPI, BRTI, dan DPR, selama Januari-Februari 2015. Setiap institusi memiliki path dependence yang berbeda antar satu dengan yang lain, sehingga membentuk pola distribusi kekuasan berbeda dalam prosedur pembuatan kebijakan. Proposal revisi UU baik dari Kemkominfo dan KPI tidak mengatur hal-hal yang berkaitan dengan konvergensi. Akan tetapi, perebutan otoritas antar kedua institusi tersebut justru menjadi fokus dalam proposal tersebut. Kemkominfo, sebagai inisiator UU Telekomunikasi, berencana untuk mengubah revisi UU tersebut menjadi UU konvergensi.     Abstract The convergence between broadcasting and telecommunication in Indonesia is inevitable as the growing information and communication technology and competition within both industries. Nevertheless, the policy governance of these industries remains distinctively separated under the 2002 Broadcasting Law and the 1999 Telecommunication Law. Whilst the regulators failed to enact the convergence bill, the only way is to synergize the revision of both laws.. This study aims to understand the point of views as well as power relation among regulators in regulating the broadcasting and telecommunication towards convergence. The primary data tool is in-depth interview with respondents who are officials of four institutions: the Kemkominfo, KPI, BRTI, and DPR, within January-February 2015. The path dependence of these institutions is differ one to another which determine the power contribution in the policy processes. The emerging proposals of the Broadcasting Law revision are not regulating convergence in detail. Instead, the KPI and Kemkominfo dispute over the authority of broadcasting industry. Kemkominfo is planning to turn the revision of the Telecommunication law into convergence law.

  11. DINAMIKA AGROFORESTRY TEGALAN DI PERBUKITAN MENOREH, KULON PROGO, DAERAH ISTIMEWA YOGYAKARTA

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    Aditya Hani

    2014-09-01

    Full Text Available Land management in agroforestry systems requires species selection and proper silviculture. Selection of species and silvicultural treatments aimed at maintaining competition in obtaining a light, water and nutrients. Farmers choose the species based on the economical factor. This study aims to determine the composition of plant species in dry land agroforestry in Menoreh Hill, Kulon Progo District. Research done by survey method. Plot observation was divided into three level of light intensity: : a early agroforestry (light intensity >50%, b middle agroforestry, (light intensity 30-50%, c further agroforestry (light intensity <30%. Four planting plots were made as repetition, so that there were 12 plots observation. Observations and measurements of vegetation are done with census (100%. The Result show five important value index in early Agroforestry,: sengon (77.84, coconut (50.04, and cacao (25.47, tree density was 482 trees/hectare and basal area 5.48 m2/ha, in middle agroforestry were: sengon (88.15, mahogany (49.51, and clove (45.03, with tree density was 595 trees/ha, and basal area was 6.70 m2/ha, further agroforestry were: clove (72.37%, sengon (50.61, and coconut (37.02, tree density was 650 trees/ha, basal area was 6.78 m2/ha.Keywords: Composition of plant species, dry land agroforestry, Menoreh Hill

  12. Dinamika Islam Politik Pasca Orde baru: Kajian Psikoanalisi Lacanian atas Hubungan KAMMI dan PKS

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    Ahmad Rizky Mardhatillah Umar

    2014-07-01

    Full Text Available This article aims at analyzing the relations between student movement andpolitical party in post-reform era of Indonesia. KAMMI, a prominent Islamiststudent movement in Indonesia, often associated with PKS (Prosperous JusticeParty in terms of identity and political practices. It has created ‘independencedilemma’ for KAMMI because since its first Congress in 1998, this studentorganization has declared ‘independent from all political forces’. This article,using Lacanian psychoanalytical tradition, exposes the forms of KAMMI’ssubjectivity and PKS interpellation that enable this political party to dominateKAMMI’s articulatory practices. The interpellation process is supported withthe projection of fantacy, emotion, and mirror in the development of KAMMIsince 1998 until present. It leads to PKS creating the KAMMI identity andthus made KAMMI’s articulatory practices identical with this party. However,there were several attempts to dislocate the hegemony through several internalreform movements. These attempts, although made contribution to internaldynamics within KAMMI, were unable to create alternative discourse dueto several limits of those movements. The case of KAMMI can be a model toexplain how other student movements develop and relate to political parties inIndonesian post-reform.

  13. Dinamika Seroprevalensi Virus Avian Influenza H5 pada Itik di Pasar Unggas Beringkit dan Galiran

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    I Gusti Ngurah Narendra Putra

    2013-11-01

    Full Text Available Normal 0 false false false EN-US X-NONE X-NONE Live Bird Market (LBM has a high potential for spreading Avian Influenza Virus (AIV between fowls or from fowl to human. Up to now, a dinamic of avian flue incidents at many LBMs in Bali has not been reported. This research aimed to reveal a dynamic of seroprevalences of avian influenza in ducks at Beringkit (Badung and Galiran (Kelungkung LBMs. A total of 35 duck blood samples was collected from each of LBMs. Sampling was conducted monthly from March to August, 2012 . AIV antibody of duck serum was measured using Rapid Hemagglutination Inhibition (Rapid HI test. Seroprevalence differences were analyzes with Chi-square (?2 Nonparametric statistical test. The results showed that seroprevalences of AIV H5 in ducks at Beringkit and Galiran LBMs were very high, ranged from 68.6% to 100% and 65.7% to 97.1% respectively. A Dynamic of AIV H5 seroprevalences in ducks at Beringkit and Galiran LBM had a similar pattern, except in July 2012. This indicates that VAI H5 has been circulating for a long time and has been to be an endemic virus infection in ducks at LBMs in Bali. It can be suggested that an Avian Influenza Virus monitoring should be done continuously over a long period. /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Table Normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-priority:99; mso-style-qformat:yes; mso-style-parent:""; mso-padding-alt:0in 5.4pt 0in 5.4pt; mso-para-margin:0in; mso-para-margin-bottom:.0001pt; text-align:justify; line-height:150%; mso-pagination:widow-orphan; font-size:11.0pt; font-family:"Calibri","sans-serif"; mso-ascii-font-family:Calibri; mso-ascii-theme-font:minor-latin; mso-fareast-font-family:"Times New Roman"; mso-fareast-theme-font:minor-fareast; mso-hansi-font-family:Calibri; mso-hansi-theme-font:minor-latin;}

  14. Kurikulum Pendidikan Islam dan Tantangan Dinamika Peradaban Global (Sebuah Pendekatan Paradigmatik

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    Imam Mawardi

    2017-01-01

    Full Text Available Curriculum of Islamic education is the prominent alternative in addressing the various issues arising along with the dynamic change of global civilization. This is due to the common ground of the problem of Islamic education and the needs in facing civilization challenge, in which each concept will evolve to adjust global logic that tends to be pragmatic. Through Islamic education curriculum, in depth study about how the scientific structure should be reconstructed and well developed can be done to meet the needs of the community. The first, the role of curriculum in the clash between the ideas and the pragmatic needs can be divided into three roles are integrated, the conservative role, the role of the creative, and critical roles/ evaluative. Second, the meaning of universal values and disciplines of Islamic education is required to play its role in a dynamic and proactive through the process of transformation of moral values in the access to fortify themselves from the negative globalization. Third, the paradigm of Islamic education curriculum in addressing the problems and future-oriented global civilization, namely the rebuilding spirit curriculum with the basic values of Islam, either in the form of a written curriculum and of the hidden curriculum. Therefore, it is necessary to pay attention to the major issues in designing the curriculum, namely how to set a strong foundation of curriculum (religious, philosophical, psychological, sosio-cultural, and development of science and technology; how to formulate the objectives; how to define the instructional procedure based on the learning materials studied with the appropriate methods and media; how to implement the curriculum in teaching and learning process; and how the curriculum evaluation be done comprehensively.

  15. Krisis Kapitalisme 2008 Dan Bangkitnya Gerakan Kiri Studi Dinamika Gerakan Partai Syriza Di Yunani

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    Novianto, Arif; Kurniawan, Lukman; Wibawa, Samodra

    2016-01-01

    The economic crisis which hit Greece was in 2008 helped to flow into a political crisis. The old political oligarchy that since 1974 up to 2010 alternately dominate the Greece that is PASOK party and the New Democracy party suffered shocks that lead to new political dynamics. Austerity policies and neoliberal reforms under the moderation of the troika (Europaen Central Bank, European Union, and International Monetary Fund) have created a decrease in the level of welfare and the economic crisi...

  16. PENGARUH MEDIA PEMBELAJARAN BERBASIS AUGMENTED REALITY TERHADAP HASIL BELAJAR SISWA KELAS X PADA KONSEP DINAMIKA PARTIKEL

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    Iwan Permana Suwarna

    2016-02-01

    Full Text Available Abstract: This research aims to determine the effect of learning media based on Augmented Reality to learning outcome of students 10th grade on the concept particle dynamics. This research was done in 10th grade science class: 2 and 4 in SMA 67 Jakarta. The research was done in October-November 2013. The research method is a quasi experimental with a noneqiuvalent control group design and the sampling technique is purposive. Instruments of the research are test (multiple choices and non test(questionnaire. Data were analyzed quantitatively using the t test, questionare analyzed qualitatively. The conclution : there is the influence of augmented reality-based instructional media on learning outcome of students grade 10th on the concept particle dynamics. Average learning outcome experiment group is higher than control group. The experimental group superior on cognitive level (C1-C4. Carrying capacity of the media Augmented Reality on the learning process had teacher done is excellent category (83.24 %. DOI: 10.15408/tjems.v1i1.1111

  17. DINAMIKA KOMUNIKASI ORGANISASI MASYARAKAT MARJINAL (Studi Pada Komunitas Perempuan Pekerja Seks Yogyakarta

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    ERWIN RASYID

    2018-03-01

    Full Text Available ABSTRACTProstitution is sexual service for gaining cash. For someone who works in sexual service named as aprostitute or in Bahasa called as Pekerja Seks Komersial (PSK.  Nowaday PSK term constructed bypeople to discriminate the sex labor. Sometimes Perempuan pekerja seks (PPS obtain the negativestreotype from society, because they know as a moral offender in social culture. The term commercialsex worker or “PSK” in Indonesia is one example of a form of community discrimination born of discourse formed by the mass media to women who work as a sex worker. In Special Region of Yogyakarta (DIY there are some areas that are often the place where sex workers peddle. Namely PasarKembang area or better known as sarkem, the Tugu railway station (Ngebong and in the GiwangansTerminal. In the three areas there are three communities that become a forum for organizing PPS,among others Bunga Seroja community in Sarkem, Arum Dalu Sehat community in Ngebong and SurtiBerdaya community in Giwangan. The three communities are under the umbrella of an organizationcalled Perhimpunan Perempuan Pekerja Seks Yogyakarta (P3SY in Indonesia. This paper aims toanalyze what kind of development communication system that attempted to be constructed by female sexworkers in Yogyakarta. The method used is descriptive qualitative. Keywords: Dynamics, Organization Communication and Female Sex Worker

  18. Analisis Segmentasi, Targeting Dan Positioning Pembiayaan Mobil Pada PT. Adira Dinamika Multifinance Tbk Cabang Manado

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    Soegoto, Agus Supandi; Mananeke, Lisbeth; Kembuan, Precylia Cyndi

    2014-01-01

    Persaingan yang semakin ketat saat ini, menuntut adanya keunggulan bersaing yang harus dimiliki oleh setiap Perusahaan, dan membutuhkan strategi pemasaran yang tepat. Jumlah pesaing yang semakin banyak membuat konsumen memiliki alternatif pilihan yang banyak untuk mendapatkan produk yang sesuai dengan harapannya. Untuk memenangkan persaingan tidak hanya sebatas menyusun bauran pemasaran sebagai taktik namun lebih dari itu juga untuk menyusun strategi segmenting, targeting marketing, dan posit...

  19. DINAMIKA KEMISKINAN DI JAWA-MADURA MENURUT KABUPATEN/KOTA TAHUN 2002-2007

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    Ade Ermasari

    2016-10-01

    Full Text Available ABSTRAK Penelitian ini bertujuan untuk memperoleh gambaran pada variasi dan pengembangan kemiskinan (angka kemiskinan di Jawa-Madura berbasis pada kabupaten / kota tahun 2002 hingga 2007, dan untuk mengetahui faktor-faktor yang dapat menjelaskan perubahan kemiskinan. Penelitian ini makro, dengan skala analisis adalah pulau Jawa-Madura secara keseluruhan.  Metode penelitian yang digunakan adalah analisis data sekunder. Sumber data utama diambil dari Data Dan Informasi Kemiskinan, Tahun 2002 2005/2006, dan 2007  Buku 2: Kabupaten / Kota diterbitkan oleh BPS. Analisis data dalam penelitian ini adalah berbagai seperti tabulasi silang, Chi Square, grafik, peta, dan analisis regresi linier ganda disediakan oleh analisis kuadran. Hasil penelitian menunjukkan bahwa sebagian besar kabupaten / kota di Jawa-Madura dari tahun 2002 hingga 2007 tingkat kemiskinan berfluktuasi terutama di pusat dan timur Jawa. Selain itu, ada perbedaan nyata antara tingkat kemiskinan di kabupaten dan kotamadya. Kabupaten cenderung dominan dalam kemiskinan kelas menengah dan kotamadya yang dominan dalam kemiskinan kelas rendah. Walaupun PDRB per kapita secara signifikan faktor berpengaruh terhadap tingkat kemiskinan di Jawa-Madura khususnya di kabupaten tahun 2002-2007, mempengaruhi relatif tidak signifikan (R2 selalu di bawah 20 persen. Faktor yang paling berpengaruh adalah persentase orang yang bekerja di sektor informal dengan nilai R2 yang selalu di atas 40 persen pada tahun 2002-2007. Untuk alasan bahwa tingkat pengangguran masalah di Jawa-Madura cukup tinggi, faktor tenaga kerja lebih berpengaruh terhadap tingkat kemiskinan di Jawa-Madura pada tahun 2002-2007 (R2 selalu di atas 35 persen dibandingkan faktor-faktor sosio-ekonomi lainnya , terutama di kabupaten. Sementara itu di kota, faktor ekonomi secara signifikan berpengaruh terhadap tingkat kemiskinan pada tahun 2007 saja dan memiliki pengaruh yang paling dalam periode 2005 sampai dengan 2007 (nilai R2 adalah sebesar 7,5 Dan 11,6 persen.  Implikasi kebijakan yang dapat diambil adalah memiliki program program penanganan kemiskinan di Jawa-Madura yang lebih dari tenaga kerja dan bidang ekonomi, terutama dalam mengatasi masalah pengangguran. Selain itu, juga perlu ada peningkatan anggaran untuk pendidikan, kesehatan, dan tenaga kerja karena persentase pengeluaran pembangunan di tiga bidang ini masih tidak signifikan.    ABSTRACT The research is aimed at obtaining a description on the variation and the development of poverty (the poverty rate in Java-Madura based on regencies/municipalities year 2002 to 2007, and to find out the factors that may explain the change of the poverty. The research is macro, with the analysis scale is the entire Java-Madura island. The research method used is secondary data analysis. The main data source is taken from Data dan Informasi Kemiskinan Tahun 2002, 2005/2006, and 2007 Buku 2: Kabupaten/Kota published by BPS. The data analysis in the research is various such as cross tabulations, Chi Square, graphics, maps, linier and double regression analysis provided by quadrant analysis. The result of the research shows that the majority of regencies/municipalities in Java-Madura from year 2002 to 2007 has the fluctuated poverty rate especially in the central and the east of Java. Besides, there is a tangible difference between the poverty rate in regencies and in municipalities. Regencies tend to be dominant in the middle class poverty and municipalities are dominant in the low class poverty. Although GDRP per capita is significantly the influential factor to the poverty rate in Java-Madura especially in regencies year 2002-2007, the influence is relatively insignificant (R2  is always below 20 percent. The most influential factor is the percentage of people working in the informal sector with the R2  value is always above 40 percent in year 2002-2007. For the reason that the unemployment rate problem in Java-Madura is quite high, the manpower factor is more influential to the poverty rate in Java-Madura in year 2002-2007 (R2 is always above 35 percent than the other socio-economic factors, especially in regencies. Meanwhile in municipalities, the economic factor significantly influences to the poverty rate in 2007 only and has the most influence in the period of 2005 to 2007 (R2 value are 7.5 dan 11.6 percent. The  implication  of  the  policy  that  can  be  taken  is  having  programs  on poverty handling in Java-Madura which is more of manpower and economic field, especially  in  coping  with  unemployment  problem.  Aside  from  that,  it  is also necessary to have the budget increase on education, health, and manpower because the percentage on developmental expenditure in the three fields is still insignificant.

  20. DINAMIKA ARAH KEPASTIAN HUKUM DI TENGAH TRANSFORMASI SOSIAL-BUDAYA DALAM PERSPEKTIF PEMIKIRAN MAZHAB SOCIOLOGICAL JURISPRUDENCE

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    B. Wibowo Suliantoro

    2017-03-01

    Full Text Available The simultaneous process of social-culture transformation emerges a complex problematic in the sector of law; especially it is related with the law certainty. The clash of values occurred intensively and extensively fixes a polemic whether the law must be stable or is always in changing. The law that is always in changing will leave a certainty as an essential character of law. On the contrary, the law that stable in its nature will turn up a problem, it will not accommodate the internal dynamic. The sect of Sociological Jurisprudence, in its effort tries to formulate a harmonious synthesis by positing the significant meaning of customary law and the written constitution as a tool of social live arrangement in order to manage it better. The certainty of law will be achieved throughout continuous dialog process between rationality and experience, between fact that happen in the social life and the ideal normative of juridical values those are formulated in constitution. The certainty of law can be approached properly if it is supported by professional lawyer apparatus that has high moral integrity. The task of judge is not only to be speaker of constitution but also to enforce the justice. Therefore, the law enforcer should has sensitive feeling in understanding the phenomena of social justice that is desired by society, formulating the social justice in the constitution, and implementing the constitution wisely.

  1. Analisis Teori Offense-Defense Pada Reformasi Kebijakan Pertahanan Jepang Dalam Dinamika Keamanan Di Asia Timur

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    Fadhil Alghifari

    2016-05-01

    Full Text Available This paper will seek to demonstrate how the use of Offense-Defense Theory can best explain the Japan’s new defense reform legislation that enables the country to play a more comprehensive global security role commensurate with its capabilities, resources, national interests, and international responsibilities. Through this offense-defense lens, it will be argued that Japan’s new defense reform legislation is a response to the growing dominance of ‘offensive’ behaviour by the neighbouring countries in East Asia. This paper will then elaborate more about the elements that are used in the offense-defense theory to analyze the ‘offense’ dominance that prompts East Asian states behave aggressively and defensively including Japan. Furthermore, this paper will explain why Japan is currently playing the ‘defensive’ role to counter the growing dominance of ‘offense’ in East Asia through the four variables of offense-defense balance; military doctrine and technology, geographical considerations, social and political order, and diplomatic arrangements. Thus, we will see that Japan holds the key to the offense-defense and security balance in the increasingly hostile environment in East Asia.

  2. DINAMIKA PEMAHAMAN ULAMA TENTANG HADIS DAJJAL (Dari Interpretasi Tekstual Ke Interpretasi Kontekstual

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    Pipin Armita

    2017-12-01

    Full Text Available Artikel ini bermaksud menggambarkan figur Dajjal yang disebutkan di beberapa hadis dalam kutub al-sittah dan menjelaskan bagaimana interpretasi tekstual dan kontekstual tentang hadis-hadis yang berbicara tentang masa lalu. Dalam beberapa hadis, Dajjal itu digambarkan sebagai fitnah besar yang Allah datang pada akhir masa, tetapi dia juga merupakan simbol dari wahyu yang akan datang. Dengan demikian manusia mengetahui bagaimana ciri-ciri akhir zaman, dan mengetahui tanda-tanda kedatangannya adalah suatu hal yang penting. Pada artikel ini penulis akan menjelaskan dan melakukan pelacakan terhadap hadis yang membahas secara spesifik tentang figur Dajjal secara tematik dengan metode deskriptif-analitis; dengan melakukan pelacakan tentang tradisi, takhrij al-hadis, analisis sanad, analisis muru’ah, syarah hadis secara tekstual dan kontekstual sebagai objek dari analisis yang dilakukan oleh penulis. Berdasarkan analisa penulis ada beberapa periwayat dari jalur Bukhari, terdapat wahyu dari Allah yang mengatakan Dajjal adalah seseorang yang gemuk bertubuh kemerahan, rambut keriting, salah satu matanya buta dan matanya seperti buah anggur yang matang (tidak bercahaya. Pemahaman secara tekstual tentang figur Dajjal itu adalah sesuai dengan apa yang digambarkan oleh hadis. Secara kontekstual, para ulama memahami kharakteristik seperti mata yang disebut dalam hadis merupakan sebuah simbol/metafora untuk menjelaskan kontrol terhadap apa yang terjadi hari ini, dan sebagai sebuah konspirasi untuk menguasai dunia, dan sebagai sebuah yang terkait dengan budaya Barat dan Yahudi yang penuh tipu daya, pemimpin yang salah, dan pemikiran yang cenderung duniawi

  3. Dinamika Tata Kelola Kebijakan Industri Penyiaran dan Telekomunikasi Indonesia Menuju Konvergensi: Sebuah Studi Paradigma Interpretatif

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    Vience Mutiara Rumata

    2017-03-01

    Konvergensi antara penyiaran dan telekomunikasi di Indonesia tidak terhindarkan seiring dengan perkembangan teknologi informasi dan komunikasi (TIK serta ketatnya persaingan dalam industri keduanya. Kedua industri telah mengintegrasi TIK sebagai nilai tambah dari layanan ataupun produk yang ditawarkannya. Meski demikian, tata kelola kedua industri ini masih terpisah yakni melalui UU Penyiaran tahun 2002 dan UU Telekomunikasi tahun 1999. Di saat RUU konvergensi telematika belum menemukan titik terang, regulator berupaya merevisi kedua UU tersebut. Studi ini merupakan penelitian deskriptif kualitatif dengan kerangka paradigma interpretatif dengan berlandaskan teori neo-institusionalisme, yakni historical institutionalism. Studi ini bertujuan untuk memahami relasi kekuasaan serta pandangan para pemangku kebijakan dalam mengatur industri penyiaran dan telekomunikasi di era konvergensi. Teknik pengumpulan data dilakukan dengan cara wawancara mendalam kepada narasumber yang dipilih secara purposif yakni Kemkominfo, KPI, BRTI, dan DPR, selama Januari-Februari 2015. Setiap institusi memiliki path dependence yang berbeda antar satu dengan yang lain, sehingga membentuk pola distribusi kekuasan berbeda dalam prosedur pembuatan kebijakan. Proposal revisi UU baik dari Kemkominfo dan KPI tidak mengatur hal-hal yang berkaitan dengan konvergensi. Akan tetapi, perebutan otoritas antar kedua institusi tersebut justru menjadi fokus dalam proposal tersebut. Kemkominfo, sebagai inisiator UU Telekomunikasi, berencana untuk mengubah revisi UU tersebut menjadi UU konvergensi. Fokus utama revisi tersebut adalah upaya untuk memfasilitasi interkoneksi dan internetworking dalam infrastruktur digital sebagai fondasi ekosistem konvergensi.     Abstract The convergence between broadcasting and telecommunication in Indonesia is envitable as the growing information and communication technology and the growing competition in both industries. These industries have integrated ICT as part of their value added services in their business. Nevertheless, the policy governance of these industries is remains distinctively separated under two main laws: the 2002 Broadcasting Law and the 1999 Telecommunication Law. Whilst the regulators failed to meet the agreement to enact the convergence bill, the only way is to synergize the revision of both laws to regulate the convergence. This study is descriptive-qualitative study with interpretative paradigm and base on New Institutionalism theoretical framework. This study aims to understand the power relation as well as point of views of the regulators in regulating the broadcasting and telecommunication in convergent era. The primary data tool is in depth interview to purposively sampled respondents who are from four institutions: the Kemkominfo, KPI, BRTI, and DPR, within January-february 2015. The path dependence of these institutions is differ one to another which determine the power contribution in shaping the policy outcome. The emerging proposals of the Broadcasting Law revision are not regulating convergence in detail. Instead, the dispute of authoritical power between KPI and Kemkominfo was reflected in the proposals. Kemkominfo, which was the initiator of the Telecommunication Law, is planning to turn the revision of the law into convergence law. The main focus is to facilitate the interconnection and internetworking of digital infrastructure between telecommunication and internet.

  4. DINAMIKA HUKUM DAN HAK ASASI MANUSIA DI NEGARA-NEGARA MUSLIM

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    Muhammad Hafiz

    2013-10-01

    Full Text Available Muslim countries often stuck in a dilemmatic situation between be exclusively with retaining the Islamic principles of human rights through Islamic law or follow the principles of human rights which is regulated internationally through Universal Declaration of Human Rights (UDHR. The existence of Independent Permanent Commission of Human Rights (IPHRC as one of the core institutions of organization of the Islamic Cooperation (OIC intended to be a mediator for the occurrence of constructive dialogue between human rights discourse on one side with Islamic law on the other side. This is the way to reduce dichotomous view that impact on gaps and conflict. The equivalent dialogue continuously between two entities, Islamic law and human rights must always be attempts to open opportunities in more widely shared understanding and in turn will facilitate the achievement of progress and the protection of human rights in Muslim countries. This dialogue also important to remove the negative stigma against Islamic law that is often accused of violating human rights. and also to open space of interpretation to Islamic law that relevance with contemporary life.

  5. KRITIK BERBASIS TEORI DINAMIKA SPIRAL ATAS TIPOLOGI KONSEP SISTEM PENGENDALIAN MANAJEMEN

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    Abdul Kahar

    2014-04-01

    Full Text Available Abstract: Spiral Dynamics Theory-Based Criticism Typology Management Control Systems Concepts. This study aims to construct a typology model of management control systems. Post-positivism paradigm was used to find the meaning of management control system on PT Hadji Kalla (HK. The result shows the adaptation, internalization, and convergence between HK’s and Toyota’s values in the practices. The values of local Bugis-Makassar wisdom such as sipakatau, Getteng, mappakalabbi', assamaturu, sipatuo-sipatokkong can be found in the HK’s values, while the Japanese’s wisdom like: kaizen, jidoka, heijunka, hoshin, genchi gembutsi can be identified as Toyota’s. Internalizing the values of siri na pesse wisdom into the management control system concept become a holistic management control system construction.

  6. DINAMIKA POPULASI IKAN GABUS (Channa striata DI RAWA DANAU PANGGANG, KALIMANTAN SELATAN

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    Dini Sofarini

    2018-04-01

    Full Text Available The province of South Kalimantan has the largest peat swamp that is named Danau Panggang Swamp with an area of 5,390.7 Ha. This swamp has ecological, economic and potential functions of a large fishery resource. The purposes of this study are to evaluate the exploitation rate of Snake Head Fish (Channa striata in Danau Panggang Swamp, by population dynamic analysis using FISAT program of Von Bertalanffy method.  The results showed that the growth pattern of Snake Head Fish (Channa striata has the tendency to grow negative allometric with 63.4 cm of long infifer (L¥, growth rate (k 0.15 per year, theoretical age at the time of the fish is equal to 0 (t0 is -1.48257 years. While the natural mortality rate (M was 0.43, the mortality rate due to catch (F of 0.69/year and the total mortality rate  (Z of 1.12/year, and the rate of exploitation value E = 0.62.  These results indicated that the exploitation rate of Head Snake Fish (Channa striata in Danau Panggang swamp has a tendency to overfishing.

  7. DINAMIKA SPASIAL PEMANFAATAN LAHAN OLEH MASYARAKAT DAERAH ALIRAN SUNGAI (DAS KREO

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    Dewi Liesnoor Setyowati

    2011-12-01

    Full Text Available Landuse dynamics of Kreo watershed from the result of interpretation of satellite image landsat (the year 1994 and image SPOT-5 (the year 2006 in the form of degradation of open farm wide of 67,07%, coppice 9,61%, forest 6,69%, and rice feld 4,64%; improvement of plantation wide 24,42%, setlement 21,68%, and mixture garden with a width of 1,05%. Forest wide and plantation of DAS Kreo only with a width of 17,19% had not pursuant to ideal wide of minimum forest of 30% at one particular in watershed (PP number 33  the year 1970. Wide area of setlement  in Kreo watershed with a width of 12,21%  is including category has exceeded ideal boundary of setlement area at one particular in watershed, maximum boundary (threshold in the form of area of waterproof equal to 6%-10% in  watershed.Keywords: Landuse spatial dynamic, landuse trend.

  8. Eksistensi dan Dinamika Kosa Kata Bahasa Jawa Kuna pada Masyarakat Bali Masa Kini

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    Ni Ketut Ratna Erawati

    2015-06-01

    Full Text Available Abstract Historically, Bali had experienced two processes, namely“Javanisation” on the one side and “Balinisation” on theother side. The melting process of them can implicate for thedevelopment of culture and Balinese language. Acculturationand language may not be inevitable. The phenomenon canbe proven through a number of Old Javanese linguisticdata used by Balinese people. Based on the data obtainedturned out to use the vocabulary Old Javanese still existby following system or Balinese rules. It can be seen in thewritten realm and verbal realm. In the written realm, the useof Old Javanese often found in literary works, inscriptions(chronicle, awig-awig (traditional law, the person’s name,the name of the area or place, and name of organization orsocial group. In the verbal realm, the Old Javanese usage canbe encountered in activities, such as performing arts, customsand religious ceremonies, mabebasan (textual singing,advice, Balinese language speech contest or in seminars. Theuses of Old Javanese vocabulary in the realm of languagegive the impression of authority, more archaic, and moreaesthetically pleasing.

  9. Dinamika haji Indonesia sejak era kolonial dan problematika calon haji ilegal

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    Moh. Rosyid

    2017-12-01

    Full Text Available The number of Indonesian pilgrims every year is increasing. On the other hand, the allocation of the number of pilgrims to be dispatched is limited by the quota. This triggers the waiting list and the share of various hajj efforts despite the violation of the law. However, not pilgrims know that pilgrimage using other country’s passport is a violation of Law No. 12 of 2006 on Citizenship and possible losing of one's nationality. From historical perspective, Muslims’ pilgrim dated back from the 16th century. At that time, there was strong suspicion that upon returning from pilgrimage, Muslims tend to be “rebellious” and initiated movement against the Dutch colonial government. Thus, the Dutch made a strict regulation concerning the Hajj and scrutinized Muslims before pilgrimage, while staying in Mecca and after their return. Among the movement against the Dutch led by Muslim upon returning the Hajj was the Padri movement. Nowadays, the number of Muslims who intend to go Hajj is rising significantly, and the waiting list goes for 15 to 20 years. The long list caused some people to find a way to go for Hajj including manipulation of citizenship documents, such as using passport of other countries. In respond to this situation, the government tries to negotiate with the Saudi government to increase the Hajj quota for Indonesians. Another effort is borrowing the remaining quota of neighboring countries. There is also suggestion to close the Hajj registration for some time and the need to revise the Hajj Law.

  10. Dinamika populasi Collembola pada tanaman kelapa sawit di perkebunan Cikasungka Kabupaten Bogor

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    Erwinda Erwinda

    2017-03-01

    Full Text Available Collembola is one of the dominant microarthopods in almost all soils types. They have important function in food webs soil ecosystem. This research was done at Cikasungka oil palm plantation for six months (April until September 2014. The aim of the research was to collect the information of diversity abundance and population fluctuations of Collembola, and their linkages between environmental factors. Collembolans were collected based on four points of soil sample from five trees of oil palm which has similar criteria. Distance of 0, 120, 240 cm from the trees, and compost lane were used to collect the samples. Results showed 37 species from 10.438 individuals with a density of 544 individu/m2. The species belongs to  4 orders and 13 families. Result also showed that are fluctuations in the abundance at the sample sites. The highest abundance of Collembolans was found in base tree zone (920 individu/m2 and compost lane (763 individu/m2. During six months, total populations of Isotomid sp. 5 (Isotomidae was higher than the others species of Collembolans. Based on the correlation analysis, various species of Collembolans are positively correlated with rainfall and soil pH.

  11. Die dinamika van die beperkte drie-deeltjie-probleem in sterrekunde

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    Keegan D. Anderson

    2011-09-01

    Full Text Available Die beperkte drie-deeltjie-probleem is een van die oudste probleme in klassieke fisika en is alvir ongeveer die afgelope honderd jaar bestudeer. Die probleem is nie oplosbaar op ‘n geslote analitiese wyse nie, alhoewel ’n oneindige reeks oplossing bestaan.

  12. Film Animasi sebagai Medium Dokumentasi Kekayaan Alam, Intelektual, Budaya, dan Dinamika Sosial Politik

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    Ardiyansah Ardiyansah

    2012-10-01

    Full Text Available Animation is a medium that has the ability to represent a visual phenomenon as a whole. Animation is not just a work of image-driven, but the work depicted motion, as expressed by Norman McLaren, Canadian animator Academy Award winner. As the interpretation of the motion, the animation is not subject to the laws of nature, so there is no limitation including movements that cannot be done in the real world or recorded in the live-action movie. So is the characterization or characterizations in the animation can be so free and open more opportunities for exploration. This advantage makes the animation a favorite medium to draw the attention of the audience, especially in the growing era of digital animation technology. Animation is now not only used for entertainment purposes, but has penetrated other fields such as education, tourism, health care, and so on. As a cultural product, animation, as well as films and works of art of human culture in general, is a historical marker that describes the spirit of an era that functions inherent in the animated film documentation of socio-political dynamics of a nation in a given period. This paper describes the process of documentation of natural, intellectual, cultural and socio-political dynamics in countries that intensively utilize the medium of animation.  

  13. Lattice Dynamics of Magnesium; Dynamique de Reseau du Magnesium; Dinamika reshetki magniya; Dinamica Reticular del Magnesio

    Energy Technology Data Exchange (ETDEWEB)

    Iyengar, P. K.; Venkataraman, G.; Vuayaraghavan, P. R.; Roy, A. P. [Atomic Energy Establishment Trombay, Bombay (India)

    1965-04-15

    A group theoretical analysis of modes of vibrations in hexagonal close-packed lattices has been made. The results have been used to classify the phonons at some special points in the Brillouin zone and factorized the secular determinant. Dispersion relations for phonons in magnesium along the two symmetry directions [0001] and [0110] have been measured (at room temperature) more accurately than reported earlier. The measurements have been made using a triple-axis spectrometer and a ''window filter'' spectrometer, both operated in the ''constant-Q'' mode. The results are compared with calculations based on three- and four-neighbour axially symmetric models. It is observed that the four-neighbour model gives a reasonably good description of the data. Even better agreement is obtained with a four-neighbour tensor force model. The force constants derived from the experiment have been used to compute the frequency distribution. (author) [French] Les auteurs ont procede a une analyse theorique par groupe des niodes de vibration dans les reseaux a structure hexagonale compacte. Ils ont utilise les resultats pour classer les phonons en des points particuliers de la zone de Brillouin et analyser mathematiquement le determinant seculaire. Afin d'etablir les relations de dispersion pour les phonons du magnesium dans les deux directions de symetrie [0001] et [0110] (a la temperature ambiante), ils ont fait des mesures plus precises que celles qui ont ete signalees jusqu'a present. A cet effet, ils ont utilise un spectrometre triaxial et un spectrometre avec 'filtre a fenetre', l'un et l'autre dans le mode de 'Q constant'. Ils ont compare les resultats aux calculs fondes sur des modeles a symetrie axiale faisant intervenir les troisieme et quatrieme voisins. Ils ont constate que le deuxieme de ces modeles fournit une assez bonne description des donnees. Un modele de forces tensorielles englobant le quatrieme voisin assure une concordance encore meilleure. Les auteurs ont utilise les constantes de force deduites de l'experience pour calculer la distribution de frequence. (author) [Spanish] Los modos de vibracion de las redes hexagonales compactas se han analizado sobre la base de la teoria de los grupos. Los resultados se han utilizado para clasificar los fonones de algunos puntos especiales de la zona de Brillouin y para factorizar el determinante secular. Se han medido, con mayor precision que la alcanzada hasta el presente, las relaciones de dispersion de los fonones en el magnesio en dos direcciones de simetria [0001] y [0110], a la temperatura ambiente. Las mediciones se han efectuado utilizando un espectrometro triaxial y un espectrometro con 'filtro de ventana', funcionando ambos segun el modo de 'Q constante'. Los resultados se comparan con calculos basados en modelos axialmente simetricos que abarcan hasta el tercer o el cuarto atomo vecino. Se ha comprobado que este ultimo modelo se ajusta adecuadamente a los datos obtenidos. Con un modelo de fuerzas tensoriales que alcanzan hasta el cuarto atomo, se obtiene una concordancia aun mas satisfactoria. Para calcular la distribucion de frecuencias se han utilizado las constantes de fuerza deducidas del experimento. (author) [Russian] Byl proizveden gruppovoj teoreticheskij analiz vidov kolebanij v geksagonal'noj reshetke s plotnoj upakovkoj. Rezul'taty byli ispol'zovany dlja klassifikacii fononov v nekotoryh special'nyh tochkah zony Brillouina i razlozhenija vekovogo determinanta. Dispersionnye sootnoshenija dlja fononov v magnii v dvuh simmetrichnyh napralenijah [0001] i [0110] byli izmereny (pri komnatnoj temperature) bolee tochno, chem soobshhalos' ranee. Izmerenija byli proizvedeny s pomoshh'ju trehosnogo spektrometra i spektrometra s ''okonnym fil'trom''. Oba jeti spektrometra rabotali pri kolebanii s ''postojannym''. Rezul'taty izmerenij sopostavljajutsja s rezul'tatami raschetov, osnovannyh na treh- i chetyrehchlennyh aksial'no simmetrichnyh modeljah. Ustanovleno, chto chetyrehchlennaja model' daet dovol'no horoshee opisanie jetih dannyh. Eshhe bolee horoshee soglasie polucheno s chetyrehchlennoj model'ju tenzornoj sily. Konstanty sily, poluchennye v rezul'tate jeksperimentov, byli ispol'zovany dlja vychislenija raspredelenija chastot. (author)

  14. Dinamika i perspektivy torgovo-jekonomicheskogo i investicionnogo sotrudnichestva Rossii i Jestonii v uslovijah krizisa

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    Nevskaya A.

    2015-05-01

    Full Text Available The article deals with the development in Russian-Estonian relations during the crises of 2007 and 2014, taking into consideration the balance between political and economic factors in the decision-making by Estonian government. A number of special aspects, trends and problems in trade and investment ties are detected. The aim of the study is to uncover key motivation behind the actions of both Russia and Estonia, to identify the drivers for economic and political development in the region, and to work out recommendations to adjust them. The questions put forward by the authors of this article could not be more topical at the time, when Russian economic situation is obviously getting worse and capital flight (to the neighboring EU Member States is likely to increase. The method of the study is comparative analysis of the impact on economic ties made by Russian-Estonian crisis of 2007 and the current international tension around Ukraine. The regional fossil fuel market and the possibilities of Gazprom involvement in its development are also analyzed. It is concluded that political motives are still important for Estonian decisionmaking, though they are balanced out by measures of business support (despite some of these measures being taken by the EU bodies. The role of political factor for the Russian side is increasing. It is acknowledged that there is a growing number of missed economic opportunities in the Russian Northwest.

  15. ANATOMI GERAKAN SOSIAL DI RIAU: Refleksi Atas Dinamika Perlawanan Masyarakat Riau terhadap Negara 1998 – 2001

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    Hasanudin Hasanudin

    2016-08-01

    Full Text Available A social movement is a collective opposing way established by plenty of communitiesl which have the same goals and aspirations in terms with a continuity interaction with the state. A social movement is a way considered effective in gaining the goal by mobilizing the supports and the resources, both economic or political resources. The success of a social movement is supported by a leadership factor in that movement and movement organisation by determining effective ways to get the collective goals. A social movement in a society is a manifestation from unsatisfaction toward the central goverment and natural resources exploitation or the economy of Riau people without taking notice of the existention and the continuity of Riau local people

  16. Dinamika Perkembangan Pariwisata Pusaka: Tinjauan dari Sisi Penawaran dan Permintaan di Kota Bandung

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    Teguh Amor Patria

    2015-08-01

    Full Text Available Tourism is one of the largest industries in the world today, and heritage tourism is one tourism segment that has shown a rapid growth. Heritage tourism in Indonesia only began to grow in the beginning of this millennium, marked by emergence of heritage tourism organizations in a number of major cities. In the city of Bandung, heritage tourism activities were initially organized in 2003 following the birth of Bandung Trails. The organization has been active in organizing heritage tours annually. Identification of heritage tourism development, both from demand and supply side, is the goal of a research that became the basis for this paper. The type of the research is qualitatiive and the population taken was the participants of tours organized by the Bandung Trails between 2003 and 2007. Samples were chosen randomly involving around 750 respondents who were given questionnaires from which primary data of profiles and demand patterns were generated. Aside from that, secondary data from literatures were used to identify the conditions of heritage tourism products at the supply side. Heritage tourism is a new phenomenon in Bandung that began to develop in the early millennium and pioneered by grassroots communities in heritage conservation. Findings of this research include, from the supply side, some challenges in the development of heritage tourism in Bandung, such as weak law enforcement, limited economic condition of local communities, and lack of attachment between the communities and heritage objects. From the demand side, heritage tourists in Bandung was domnated by young people aged 19-30 (78% and it is assumed that there is a connection between level of education and interest in heritage tourism.

  17. DAMPAK TRANSFORMASI PERAN WANITA DALAM PEMBANGUNAN TERHADAP DINAMIKA SISTEM KEPENDUDUKAN INDONESIA

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    Ahmad Basuki

    2002-01-01

    The change of social pattern from traditional agrarian into modern industry has impact in woman transformation role. The previously woman role in the ‘back side’ or ‘under the man shadow’ begins to start into questions. Egalitarianism motto becomes familiar together with the extension of woman role. Anyhow, such change should be responded with a clear and specific policy. Accordingly, law as a tool of social engineering should be able to accommodate them, as well as gives the guarantee for th...

  18. DAMPAK TRANSFORMASI PERAN WANITA DALAM PEMBANGUNAN TERHADAP DINAMIKA SISTEM KEPENDUDUKAN INDONESIA

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    Ahmad Basuki

    2002-01-01

    Full Text Available The change of social pattern from traditional agrarian into modern industry has impact in woman transformation role. The previously woman role in the ‘back side’ or ‘under the man shadow’ begins to start into questions. Egalitarianism motto becomes familiar together with the extension of woman role. Anyhow, such change should be responded with a clear and specific policy. Accordingly, law as a tool of social engineering should be able to accommodate them, as well as gives the guarantee for the extension of woman role that has been once pushed in a corner by feudalism tradition.

  19. PENGARUH E-SCAFFOLDING DALAM THINK PAIR SHARE TERHADAP KEMAMPUAN BERPIKIR TINGKAT TINGGI DINAMIKA PARTIKEL

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    Akhmad Fauzul Albab

    2016-01-01

    Full Text Available Abstract: This study aimed to examine the effect of e-learning based Think Pair Share cooperative learning model toward higher order thinking skills of students. This study was conducted at SMAN 1 Jember for X grade students and used factorial design. Two experimental groups (TPS with E-Scaffolding and TPS with scaffolding were compared with a control group (TPS. This research was carried out to 180 students. The results showed that there is a difference in high-order thinking skills among groups of students who take the e-scaffolding in the TPS, scaffolding in TPS, and TPS learning; there is a difference in high-order thinking skills among groups of students with different prior knowledge levels; and there is no interactional effect among e-scaffolding in TPS, scaffolding in TPS and TPS strategy and the student’s prior knowledge on high order thinking skills. Key words: e-scaffolding, think pair share, high order thinking, prior knowledge.                                                                                     Abstrak: Penelitian ini bertujuan untuk menguji pengaruh pembelajaran berbasis e-learning yang terintegrasi dalam model pembelajaran kooperatif Think Pair Share (TPS dalam bentuk E-Scaffolding terhadap kemampuan berpikir tingkat tinggi siswa. Penelitian dilaksanakan di SMA Negeri 1 Jember untuk siswa kelas X ini dengan menggunakan rancangan faktorial. Dua kelompok eksperimen (TPS dengan E-Scaffolding dan TPS dengan Scaffolding dibandingkan dengan sebuah kelompok kontrol (TPS. Penelitian dilaksanakan terhadap sampel sebanyak 180 siswa yang dipilih secara acak kelompok. Hasil penelitian menunjukkan bahwa terdapat perbedaan kemampuan berpikir tingkat tinggi antara kelompok siswa yang mengikuti pembelajaran e-scaffolding dalam TPS dengan pembelajaran scaffolding dalam TPS maupun siswa dengan pembelajaran TPS; terdapat perbedaan kemampuan berpikir tingkat tinggi antara kelompok siswa yang mempunyai tingkat kemampuan awal berbeda; dan tidak terdapat pengaruh interaksi antara strategi e-scaffolding dalam TPS, scaffolding dalam TPS, dan TPS dan kemampuan awal siswa terhadap kemampuan berpikir tingkat tinggi. Kata kunci: e-scaffolding, think pair share, kemampuan berpikir tingkat tinggi, kemampuan awal.

  20. Dinamika Populasi Diaphorina citri Kuwayama (Homoptera: Psyllidae dan Deteksi CVPD dengan Teknik PCR

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    I NYOMAN WIJAYA

    2015-09-01

    Full Text Available The research was conducted in the field of Taro village Gianyar regency and Katung village Bangli regency and at the Laboratory of Biotechnology Faculty of Agricultural Udayana University. The purpose of the research were to investigate population dynamic of Diaphorina citri Kuwayama and other insects that were assosiated with citrus cv. siam; and molecular detection of CVPD patogen in its vector, other phytophagous insects on citrus cv.siam and kemuning [Murraya paniculata (L. Jack.] The result of this study showed that in six month period there was one peak of D. citri population which was associated with the flushing period of citrus at Taro as well Katung villages. The peak of D. citri population of Taro village was higher than that of Katung village. Two species of parasitoids and four spesies of predators were found in the field and may contribute in the suppression of D. citri population. The parasitoids identified were Tamarixia radiata Wat. and Diaphorencyrtus alligharensi Shaffe, whereas the predators were Curinus coeruleus Mulsant, Phiddipus sp., Menochilus sexmaculatus Fabricius and Oxyopes javanus Thorell. T. radiata has been proven to be an effective nymph parasitoid that could suppress the population development of D. citri in citrus orchads. The research revealed that kemuning could serve as a source of infection because it is also a host of CVPD disease as well as of D. citri. Toxoptera citricidus Kirkaldy and Maleuterpes dentipes Hell. were not proven to contain CVPD disease.

  1. APLIKASI DATA CITRA SATELIT LANDSAT UNTUK PEMANTAUAN DINAMIKA PESISIR MUARA DAS BARITO DAN SEKITARNYA

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    Abdur Rahman

    2016-06-01

    Full Text Available Telah terjadi terjadi kerusakan habitat lingkungan mangrove, abrasi dan akresi yang menyebabkan semakin tingginya muka air  di sepanjang DAS Sungai Barito (DAS Martapura, DAS Alalak dan DAS Kuin, sebab erjadinya proses abrasi dan akresi  yang terjadi di sepanjang garis pantai, terutama DAS Martapura, DAS Alalak dan DAS Kuin. Klasifikasi pemanfaatan lahan dan konversinya serta perubahan pesisir berupa akresi dan abrasi di sepanjang pantai area penelitian di analisis dengan memanfaatkan informasi dari data citra satelit Landsat multi temporal yang di peroleh pada tanggal 29 Juni tahun 1985, dan 03 September 2006. Dominasi pemanfaatan lahan berupa HPH, pertambangan dan pemukiman dengan konversi lahan pada hutan untuk pemanfaatan lain memberikan dampak erosi yang cukup besar dengan ditunjukannya wilayah pesisir yang mengalami peningkatan akresi terutama pada bagian muara sungai (delta. Tren perubahan yang terlihat pada kawasan pesisir di area penelitian selama 21 tahun adalah abrasi sebesar 294,55 m2 di daerah Muara S. Martapura, 75,53 m2 di sekitar muara S. Alalak. Dan perubahan Abrasi sebesar 177,42 m2 , dan akresi sebesar 610,86 m2 di sekitar Muara S. Barito/Kuin. Have happened happened damage of environmental habitat of mangrove, and abrasi of akresi causing its excelsior of face irrigate alongside DAS River of Barito (DAS Martapura, DAS Alalak and of DAS Kuin, because the happening of process of abrasi and of akresi that happened alongside coastline, especially DAS Martapura, DAS Alalak and  DAS Kuin. Classification exploiting of farm and its conversion and also change of coastal area in the form of and akresi of abrasi alongside research area coast in analysis by exploiting information of satellite image data of Landsat temporal multi which in obtaining on 29 June year 1985, and 03 September 2006. Domination exploiting of farm in the form of HPH, settlement and mining with farm conversion at forest for other exploiting give big enough erosion impact with  regional and natural coastal area that make-up of akresi especially  part of river estuary    (delta.  Seen Change Tren at coastal area in research area during 21 year was abrasi equal to 294,55 m2 in Estuary area S. Martapura, 75,53 m2 around estuary S. Alalak. And change of Abrasi equal to 177,42 m2 , and akresi equal to 610,86 m2 around Estuary S. Barito / kuin.

  2. Dinamika Ekonomi dan Peluang Kerja Rumah Tangga Perkebunan Rakyat di Kabupaten Tanjung Jabung Barat

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    Amril Amril

    2015-07-01

    Full Text Available This study aimed to analyze: (1 to analyze the economic dynamics of the household smallholder plantation  in Tanjung Jabung Barat which include changes in household assets, expenditure and consumption patterns of the household; (2 to analyze the dynamics of domestic employment opportunities household smallholder plantation  in Tanjung Jabung Barat which includes changes in working hours and employment status both of head or household members. The main data used in this study is raw data SUSENAS Year 2010 and 2014. Descriptive data were analyzed quantitatively using a single frequency tables. The research found that: 1 During the period from year 2010 to 2014, the general economic welfare of households smallholder plantations in Tanjung Jabung Barat has shown. This can be seen from the aspect of increasing ownership and quality of housing and the ownership of productive assets and other household assets. In addition, the increase in prosperity is also evident from the increase in household expenditures and changes in food consumption patterns and non-food; 2 In terms of working hours devoted a good show that a relatively large proportion of heads of households and household members who work above the normal working hours. Allocation of long working hours is one of the survival strategies of households smallholder plantations in Tanjung Jabung Barat; 3 From the job status shows most heads of households trying to temporary laborers/workers are not paid. These unpaid workers generally are members of the household

  3. Dinamika Ovarium pada Kuda Hasil Persilangan Pejantan Thoroughbred dengan Induk Lokal Indonesia

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    Muhammad Danang Eko Yulianto

    2016-11-01

    Full Text Available The development of horse breeding industry in Indonesia was commenced through horse racing events held all over the country. It were accelerated by the development of Thoroughbred-Indonesian local Crossbred horses. There are many broodmares injured during their racing time and retired from the racetracks. They may still has a reproductive vigor to continue on producing offsprings. Very little information has been reported on the monitoring the reproductive capacity of the mares. The objective of this study was to explore ultrasonography imaging of the ovarian dynamics, correlated with the estrus behavior of the Thoroughbred-Indonesian local crossbred mares. Three Thoroughbred-Indonesian local crossbred mares with 6.25-12.5% of local genetics aged 12-20 years old were used in this study. Estrus and ovulation were synchronized by 10 mg PGF2α i.m. at luteal phase and 1,500 IU hCG i.m. injection when the dominant follicle reach ≥30 mm in diameter. Ultrasonography examination was done every morning at approximately at the same time. Estrus behavior was observed by using teaser stallions following a standard method. Results of the experiment indicated that onset of the estrus was reached 1.33±0.58 days after the hCG injection, with the average duration of 4.00±1.00 days. The ovulations were done at 5.33±1.15 days after PGF2α treatment and 66.67±10.07 hours after hCG treatment. Maximum follicle diameter was identified to reach 4.50±0.52 cm at one day before ovulation. The mares performed 25.4±3.38 days length of estrus cycle with 2-3 follicular  waves. It had been identified that the estrus duration  was  6.8±1.92  days  in mares with the age of 12-20 years. The average of maximum diameter of the largest follicle before ovulation was 4.2±1.24 cm. In conclusion, to improve the efficiency of breeding, several information are needed i.e. the optimal time of ovulation, relevan parameters related to follicular development.

  4. DINAMIKA INTERAKSI ANTARETNIK DALAM MEWUJUDKAN KESERASIAN SOSIAL DI WILAYAH PERBATASAN NEGARA INDONESIA – MALAYSIA

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    Agus Sikwan

    2017-11-01

    Full Text Available The research reveals the dynamics of interaction between the three major ethnic groups (ethnic Dayak, Malay and Chinese living in Entikong Subdistrict. These interactions are manifested in social relationships, ie relationships as relatives, as friends. Through qualitative analysis, the relationship is still strong in primordial loyalty among ethnic groups. It is characterized by a tendency to choose individuals from their own ethnic groups to serve as relatives. The results also show that there are two forms of ethnic group settlements in Entikong Subdistrict, namely: Mixed pattern, ie settlement area in which consists of various ethnic groups, in which there is more intensive inter-ethnic social contact that can encourage the realization of harmony social; Separate pattern, ie settlement area which consists of one ethnic group of the same kind, generally inhabited by Chinese ethnic groups. The change of settlement pattern indirectly caused by the expansion of subdistricts and population growth

  5. DINAMIKA WACANA FORMALISASI SYARIAT DALAM POLITIK: IKHTIAR MENEMUKAN RELEVANSI RELASI AGAMA DAN NEGARA PERSPEKTIF INDONESIA

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    Mahathir Muhammad Iqbal

    2014-06-01

    Penelitian ini merupakan ikhtiar untuk menemukan relevansi hubungan agama dan negara yang ideal. Sebab Isu formalisasi syariat Islam dalam politik menjadi kajian menarik dalam wacana relasi agama dan negara. Dengan menggunakan pendekatan pustaka, artikel ini menganalisis keterlibatan negara dalam mengatur warga negara untuk mengimplementasikan syariat Islam di Indonesia. Adanya netralitas negara menjadi kunci dalam menemukan relasi keduanya. Secara teoritis, studi ini memberikan penjelasan bahwa netralitas tidak hanya dipahami sebagai pengabdian negara untuk memberikan hak-hak warga negara untuk berdoa berdasarkan iman, tetapi juga untuk membatasi warga negara. Sebab dalam pelaksanaan syariat akan dapat mapan dan berjalan dengan baik, manakala negara memiliki netralitas. Sehingga negara tidak menarik syariat Islam menjadi sebuah kebijakan resmi atau peraturan negara (formalisasi syariat. Dengan begitu seorang Muslim dapat membawa agama ke dalam lingkaran politik, tetapi hanya dalam tingkat etika politik.

  6. Problems of the agriculture radiology and radiobiology at the environment contamination by the young mixture of the nuclear fission products; Problemy sel'skokhozyajstvennoj radioehkologii i radiobiologii pri zagryaznenii okruzhayushchej sredy molodoj smes'yu produktov yadernogo deleniya

    Energy Technology Data Exchange (ETDEWEB)

    Prister, B S

    2008-07-01

    The basic problem on population radiation safety and the farm production at the environment contamination by the young mixture of the nuclear fission products are considered. In the field experiments, the conformities of the out of root plant contamination, kinetics of the irradiation absorbed doses and the biological effect of the NFP on the plants during the different ontogenesis phases are investigated. The kinetics of the nuclear fission product accumulation and drawing out from the cattle organisms of the most movable radionuclides in the biological systems; the distribution and kinetics of the absorbed irradiation doses formation and the nuclear fission products biological effect on the cattle organism is studied. The comparative quantitative assessment of the meaning of the basic formation factors of the radiation situation is produced.

  7. Regulations and instructions for RB reactor operation; Propisi i uputstva za rad reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-07-01

    This document includes regulations for reactor RB operation, behaviour and presence of staff in the reactor building; regulations for performing experiments at the RB reactor, regulations and int ructions for the reactor operators and other staff on duty. A chapter is devoted to instruction for reactor operation with the operating documentation and special duties of the operators. Regulations and instruction concerned with accidents are described with classification of accidents and evacuation plan. Annexes to this document include: the present status of the reactor; program for training the reactor operators; forms which are obligatory to be signed for any operating activity, and the certificate of the RB reactor lattice.

  8. Design characteristics of zero power fast reactor Lasta; Osnovne karakteristike brzog reaktora nulte snage Lasta

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Stefanovic, D; Pesic, M; Popovic, D; Nikolic, D; Antic, D; Zavaljevski, N [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1987-07-01

    The concept, purpose and preliminary design of a zero power fast reactor LASTA are described. The methods of computing the reactor core parameters and reactor kinetics are presented with the basic calculated results and analysis for one selected LASTA configuration. The nominal parameters are determined according to the selected reactor safety criteria and results of calculations. Important aspects related to the overall safety are examined in detail. (author)

  9. RA reactor exploitation, task 3.08/01; Zadatak 3.08/01 - Eksploatacija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report.

  10. Operation and maintenance of the RA reactor; Pogon i odrzavanje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, M; Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    During 1961 the RA reactor was used for irradiation of samples for 258 users ( from which 188 from the Institute) and for 34 experiments, this means productions of 5958 MWh. The production was almost four times bigger than during previous year due to the demand of the Laboratories of the Institute. Burnup of the fuel from the first batch was about 30%. This means that the operation time could be much higher. Number of safety shut-downs was 11. The reasons were related to electrical faults, 9 occurrences, failure of the instrument for reactor period measurement, once, and failure of the pump once. This report covers state and operation data of the reactor components, control instruments, devices for reactor protection, dosimetry, heavy water system, helium system, mechanical and electrical equipment. Problems related to training of the staff and lack of personnel are mentioned as well.

  11. RB research reactor safety report; Izvestaj o sigurnsti istrazivackog reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Pesic, M; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1979-04-15

    This new version of the safety report is a revision of the safety report written in 1962 when the RB reactor started operation after reconstruction. The new safety report was needed because reactor systems and components have been improved and the administrative procedures were changed. the most important improvements and changes were concerned with the use of highly enriched fuel (80% enriched), construction of reactor converter outside the reactor vessel, improved control system by two measuring start-up channels, construction of system for heavy water leak detection, new inter phone connection between control room and other reactor rooms. This report includes description of reactor building with installations, rector vessel, reactor core, heavy water system, control system, safety system, dosimetry and alarm systems, experimental channels, neutron converter, reactor operation. Safety aspects contain analyses of accident reasons, method for preventing reactivity insertions, analyses of maximum hypothetical accidents for cores with natural uranium, 2% enriched and 80% enriched fuel elements. Influence of seismic events on the reactor safety and well as coupling between reactor and the converter are parts of this document.

  12. Measurement of neutrons in the RA reactor cell; Merenje neutrona u elementarnoj celiji reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Bosevski, T [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    A special experimental device was constructed for measuring the neutron flux distribution in the RA reactor cell. This device simulated the reactor cell in order to avoid disturbance in the reactor core. It was made of an aluminium cylindrical vessel having outer diameter same as the vertical experimental channel and contained three fuel slugs. Hole was made in through the center of the fuel slugs and a copper wire was placed in the hole for measuring the thermal neutron flux distribution. It was placed in the experimental channel VK-5 in the location of highest neutron flux. Handling of samples for irradiation was quite simple.

  13. Maximum neutron flux in thermal reactors; Maksimum neutronskog fluksa kod termalnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1968-07-01

    Direct approach to the problem is to calculate spatial distribution of fuel concentration if the reactor core directly using the condition of maximum neutron flux and comply with thermal limitations. This paper proved that the problem can be solved by applying the variational calculus, i.e. by using the maximum principle of Pontryagin. Mathematical model of reactor core is based on the two-group neutron diffusion theory with some simplifications which make it appropriate from maximum principle point of view. Here applied theory of maximum principle are suitable for application. The solution of optimum distribution of fuel concentration in the reactor core is obtained in explicit analytical form. The reactor critical dimensions are roots of a system of nonlinear equations and verification of optimum conditions can be done only for specific examples.

  14. HETERO code, heterogeneous procedure for reactor calculation; Program Hetero, heterogeni postupak proracuna reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Jovanovic, S M; Raisic, N M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1966-11-15

    This report describes the procedure for calculating the parameters of heterogeneous reactor system taking into account the interaction between fuel elements related to established geometry. First part contains the analysis of single fuel element in a diffusion medium, and criticality condition of the reactor system described by superposition of elements interactions. the possibility of performing such analysis by determination of heterogeneous system lattice is described in the second part. Computer code HETERO with the code KETAP (calculation of criticality factor {eta}{sub n} and flux distribution) is part of this report together with the example of RB reactor square lattice.

  15. Temperature reactivity coefficient of the RA reactor; Temperaturni koeficijenat reaktivnosti reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Strugar, P; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Temperature reactivity coefficient of the RA reactor was determined as follows. Stabilization of moderator temperature and graphite reflector was achieved in the reactor operated at power levels of 20, 100, 500, 1000, 3000 and 5000 kW. Temperature change of the moderator was achieved by changing the water flow rate in the secondary cooling system. The fuel temperature was changed simultaneously. During the measurement at each power level the temperature change was between 30 - 50 deg C. Changing the position of the automated regulator is registered during moderator temperature change, and these changes were used for determining the total reactivity change by using the calibration curves for the automated regulator. In the measured temperature range the the reactivity change was linear and it was possible to determine the total temperature coefficient.

  16. Dinamika Konflik Dan Integrasi Antara Etnis Dayak Dan Etnis Madura (Studi Kasus Di YOGYAKARTA Malang Dan Sampit)

    OpenAIRE

    Bashori, Khoiruddin; Majid, Abd; Tago, Mahli Zainuddin

    2012-01-01

    Indonesia is one of the most pluralistic societies in the world consisting of various social groups, ethnics, tribes, languages and religious diversities. However, the social, political, and cultural diversities among people have frequently been resulting conflicts or tensions. Using conflict and integration approach, therefore, this article observes the dynamics relation between ethnic groups, Madura and Dayak ethnic in particular, in certain plural regions in term of ethnic diversities; tho...

  17. Verification of Dinamika-5 code on experimental data of water level behaviour in PGV-440 under dynamic conditions

    Energy Technology Data Exchange (ETDEWEB)

    Beljaev, Y.V.; Zaitsev, S.I.; Tarankov, G.A. [OKB Gidropress (Russian Federation)

    1995-12-31

    Comparison of the results of calculational analysis with experimental data on water level behaviour in horizontal steam generator (PGV-440) under the conditions with cessation of feedwater supply is presented in the report. Calculational analysis is performed using DIMANIKA-5 code, experimental data are obtained at Kola NPP-4. (orig.). 2 refs.

  18. Dinamika Politik Islam Semenanjung Arab 1800-1930 M dan Pengaruh Berdirinya Kerajaan Arab Saudi Modern terhadap Praktik Keagamaan

    Directory of Open Access Journals (Sweden)

    Ihwan Agustono

    2016-11-01

    Full Text Available The article examines the dynamics of political Islam of the Arabian Peninsula in 1800-1930 and their influence to the foundation of the Modern Saudi Arabia Kingdom and their impact to religious practices in the Holy Land. The study is considered important due to the changing phenomenon of religious under-standing in the Holy Land. A new orthodox ideology has been able to change the well-established traditional understanding and become a dominant school until nowadays. The study concludes that: 1 Socio-political constellation of Hijaz before 19th century had been marked by the decrease of political supremacy of Hijaz along with far migration of the Islamic governmental center from Madinah; 2 One of the culminations of political dynamics of the Arabian Peninsula between 1800 and 1930 was the establishment of the Modern Saudi Arabia Kingdom; 3 Such political dynamics have subsequently resulted in the purification of Islamic sharî‘ah in accordance with the Wahabi’s doctrines, obliteration of the tradition of four maqâmât in Masjid al-H{arâm, conformation of Islamic education with the Wahabi’s dogmas, and the increase of orthodoxy and the decrease of popular Sufi’s credo.

  19. Dažu Ziemeļrietumvidzemes aizgūto leksēmu dinamika

    Directory of Open Access Journals (Sweden)

    Elga Kagaine

    2011-11-01

    Full Text Available DYNAMIK EINIGER ENTLEHNTER LEXEME IN DEN MUNDARTEN NORDWESTLIVLANDSZusammenfassungIn diesem Beitrag werden einige in Nordwestlivland vorkommende entlehnte Lexeme finnougrischer Herkunft sowie ihre Semantik unter dem Aspekt des historischen Wandels behandelt. In der 2. Hälfte des 20. Jh. bietet sich durch die Erweiterung von mundartlichen Materialsammlungen die Möglichkeit, die in ME, EH und sonstigen Forschungen vorhandene Information sowohl zur Verbreitung, Stabilität und Wandel dieser Wörter als auch zu ihrer Herkunft, Semantik und den Gebrauchseigenschaften zu ergānzen.Unter dem Aspekt der Gebrauchsdynamik von Entlehnungen im Laufe des 20. Jh. lässt sich feststellen, dass ein Teil der lokalen entlehnten Lexeme zu historischen Relikten geworden ist (z.B. aķis ‘Getreidehocke’, sāris, zāris ‘Insel; Hilgel’, ķiris ‘schwarzer Ochse mit weiflem Streifen überm Rücken’; ein anderer Teil mit relativ weitem bzw. engem Gebrauch setzt sein Funktionieren vorwiegend in der gesprochenen Sprache der älteren Generation fort (z.B. kãbaka, kābaks ‘armer, ärmlicher Mensch’; ‘geiziger, habgieriger Mensch’, paîkât ‘flicken’; ein weiterer Teil hingegen kommt auch heutzutage ziemlich oft in der gesprochenen Sprache verschiedener Generationen vor (z.B. roida ‘Schutt, Kehricht, Abfālle’, peksēt ‘schlagen; prugeln’, kunna ‘Wiesenfrosch’ u.a..Nach der Erweiterung von Materialsammlungen bietet sich die Möglichkeit, die bisherigen Herkunftsdeutungen der Wörter zu ergänzen und einige Hypothesen über die Relation mehrerer dialektaler Wörter Nordwestlivlands zum Estnischen bzw. Livischen aufzustellen.ķil̂ts; der Vergleich kâ ķilts wird bei der Charakteristik eines abgemagerten Menschen oder Tieres gebraucht. Es kommt unter Ortsnamen vor (siehe Endzelīns LVV II 221; ohne Herkunftsangabe. Es wäre wohl auf das bei WiedWb 281–282 erwähnte kilt (= kild 2; kild ‘abgesprungenes, abgetheiltes Stuck, Splitter’ zu beziehen. Semantisch ist izdilis kâ ķil̃ts mit der analogen Konstruktion (tievs, izdilis kâ skals zu vergleichen.porumi, puromi; das Wort ist mit der Grundbedeutung ‘Schutt, Kehricht; Krümchen; Spreu’ aufgezeichnet worden, resp. auf etwas Kleines, Feines, Zerkleinertes u.dgl. zu beziehen. Dies lässt vermuten, dass nordwestlivländisches porumi, puromi mit estn. puru (siehe M ä g i s t e VII 2244 II puru ‘Krümchen, Staubkorn, Stäubchen’, ‘Schutt, Mull’ und puruma ‘zerbrechen, zerkleinern’ in Verbindung stehen könnte.ķilputra, kilputra ‘aus dem Brotteig gekochter Brei’; ‘Grütze aus Roggenmehl’; siehe M ä g i s t e III 824 II kile ‘saurer Haferbrei’ + putra ‘Brei’.Bei einem Teil der entlehnten Lexeme kann die Herkunft mit der Kontamination Zusammenhängen: siehe narcaka, narcaks + grabažas > narkažas, narbažas ‘alte, abgetragene Sachen, abgenutzte Gegenstände; Lappen’; porumi, puromi + -akas (lancakas, poncakas ’alte, abgetragene Kleider, Kleidungsstücke, Fetzen’ > porakas ‘Schutt, Splitter, Reisig, Kehricht’.

  20. Analisa Pengaruh Penerapan Teknologi Informasi untuk Perbaikan Kinerja Rantai Pasok Sistem Produksi-Distribusi dengan Menggunakan Dinamika Sistem

    OpenAIRE

    Setijadi, Setijadi; Pramestari, Diah; Ane, Bernadetta Kwintiana

    2009-01-01

    Kinerja suatu rantai pasok sistem produksi-distribusi dipengaruhi oleh beberapapenggerak (drivers), yaitu persediaan, transportasi, fasilitas, dan informasi. Secarapotensial, informasi merupakan penggerak terbesar terhadap kinerja rantai pasok, karenasecara langsung mempengaruhi penggerak lainnya. Informasi membuka peluang untukmembuat rantai pasok lebih responsif dan efisien.Pada sisi lain, pengaturan tingkat produksi dalam suatu sistem produksi-distribusimenjadi suatu masalah sulit karena a...

  1. Analisa Pengaruh Penerapan Teknologi Informasi Untuk Perbaikan Kinerja Rantai Pasok Sistem Produksi-Distribusi Dengan Menggunakan Dinamika Sistem

    OpenAIRE

    Setijadi, Setijadi; Pramestari, Diah; Ane, Bernadetta Kwintiana

    2004-01-01

    Kinerja suatu rantai pasok sistem produksi-distribusi dipengaruhi oleh beberapapenggerak (drivers), yaitu persediaan, transportasi, fasilitas, dan informasi. Secarapotensial, informasi merupakan penggerak terbesar terhadap kinerja rantai pasok, karenasecara langsung mempengaruhi penggerak lainnya. Informasi membuka peluang untukmembuat rantai pasok lebih responsif dan efisien.Pada sisi lain, pengaturan tingkat produksi dalam suatu sistem produksi-distribusimenjadi suatu masalah sulit karena a...

  2. Verification of Dinamika-5 code on experimental data of water level behaviour in PGV-440 under dynamic conditions

    Energy Technology Data Exchange (ETDEWEB)

    Beljaev, Y V; Zaitsev, S I; Tarankov, G A [OKB Gidropress (Russian Federation)

    1996-12-31

    Comparison of the results of calculational analysis with experimental data on water level behaviour in horizontal steam generator (PGV-440) under the conditions with cessation of feedwater supply is presented in the report. Calculational analysis is performed using DIMANIKA-5 code, experimental data are obtained at Kola NPP-4. (orig.). 2 refs.

  3. Dinamika klyuchevykh mediatorov insulinorezistentnosti u bol'nykh sakharnym diabetom 2 tipa pri primenenii metformina (Formin Pliva?

    Directory of Open Access Journals (Sweden)

    Mikhail Ivanovich Balabolkin

    2004-12-01

    Full Text Available Цель. Изучение влияния формина (метформина не только на состояние углеводного, но и липидного обмена, динамику содержания лептина, его растворимого рецептора и альфа-фактора некроза опухолей (альфа-ФНО в сыворотке крови у больных СД 2. Материалы и методы. Обследовано 262 больных. Общий анализ крови и мочи проводили через каждый месяц наблюдения, а биохимический анализ крови, включая содержание общего ХС, ТГ, ХС ЛПНП и ЛПОНП и ХС ЛПВП, мочевины, креатинина, печеночных ферментов, проводили на 1-м и 4-м визитах. Лечение формином проводилось в течение не менее 12 нед. и изучалось при этом его влияние на состояние углеводного и липидного обмена у больных СД 2. Из общего числа обследованных у 26 больных на фоне терапии формином изучалось содержание лептина, растворимого рецептора к лептину и альфа-ФНО. Результаты. На фоне лечения формином у больных отмечалось улучшение углеводного обмена, которое сопровождалось статистически достоверным снижением гликемии натощак. Компенсация углеводного обмена у больных также сопровождалась статистически достоверным уменьшением индекса мас? сы тела с 34,02+0,33 кг/м2 до 32,73+0,33 кг/м2. У больных на фоне лечения формином наблюдается недостоверное снижение содержания лептина, растворимого рецептора к лептину и статистически достоверное снижение альфа-ФНО в сыворотке крови. Выводы. проведенные исследования показывают, что формин обладает выраженным антигипергликемическим эффектом, способствует улучшению компенсации углеводного обмена, что сопровождается статистически достоверным снижением гликемии и уровня гликозилированного гемоглобина в сыворотке крови. Наряду с этим на фоне терапии формином отмечается снижение уровня холестерина ЛПНП и повышение содержания холестерина ЛПВП, при практически неизмененных показателях содержания общего холестерина в сыворотке крови. Кроме того, лечение формином способствует статистически достоверному снижению содержания альфа-ФНО и умеренному понижению уровня лептина и его растворимого рецептора в сыворотке крови.

  4. DINAMIKA UPAYA MELAKUKAN SINERGI ANTARA HUKUM PERDAGANGAN INTERNASIONAL DAN HUKUM LINGKUNGAN / INTERNATIONAL TRADE LAW AND ENVIRONMENTAL LAW SINERGY

    Directory of Open Access Journals (Sweden)

    Endra Wijaya

    2017-11-01

    Full Text Available Dalam aktivitas perdagangan internasional, kehadiran hukum menjadi suatu hal yang penting untuk mengatur dan membuat berjalannya unsur-unsur dalam perdagangan internasional menjadi efektif, efisien, dan berkeadilan. Secara perlahan-lahan, sistem perdagangan internasional mulai memasukkan isu hukum lingkungan hidup. Masuknya isu hukum lingkungan ke dalam sistem perdagangan internasional sudah dimulai sejak adanya kesadaran perlunya lingkungan hidup dijaga kelestariannya agar dapat menunjang pembangunan secara keseluruhan. Saat ini, isu hukum lingkungan tersebut memang sudah menjadi syarat penting bagi setiap hubungan perdagangan yang akan atau sedang dilakukan oleh para subjek hukum dalam perdagangan internasional. Fokus pembahasan makalah ini tertuju kepada persoalan bagaimana masuknya dan bersinerginya isu hukum lingkungan ke dalam sistem perdagangan internasional. Metode penelitian yang digunakan dalam melakukan pembahasan ialah metode kajian normatif, dengan menggunakan data sekunder yang diperoleh melalui penelusuran kepustakaan. In international trade activity, the law exists and becomes one of the important components to ensure the trading activity runs effectively, efficiently, and fair. Gradually, international trade system has started to embed environmental law issue to become its part of the system, and this process has begun since people realized that environment should be protected in order to support the sustainable development process. Currently, environmental law issue becomes an important condition for most of the international trade relations which are being done or will be done by subjects of the international trade. This paper focuses on how environmental law is being synergized within international trade system. The library research method will be used to explore that topic.

  5. DINAMIKA RESISTENSI PETANI TERHADAP EKSPANSI KAPITALISME DI JAWA (Studi atas Perlawanan Petani Terhadap Pertambangan Pasir Besi di Karangwuni Kulon Progo

    Directory of Open Access Journals (Sweden)

    Suliadi Suliadi

    2016-09-01

    Full Text Available This thesis is aimed to analyze the peasant resistance against the iron sand mining that occurred in Kulon Progo. As its starting point, this study is based on the change in political attitude of peasants, who were initially against it turned into approving to the iron sand mining. Through an approach of James C. Scott’s “moral economy of peasant” and Samuel L. Popkin’s “political economy”, this research is reviewed in descriptive analysis of how the change in political attitude of peasants eventually happen. With that analysis, this study shows that the changes in political attitudes of peasants in response to the expansion of mining capitalism is nothing more than a political compromise by the peasants in response to the expansion of mining capitalism. What is actually going to be refused is the ways of investors / companies and countries in expansion which is capitalist bias, which only creates a farming community becomes eliminated to access the available resources.

  6. Dinamika Proses Perumusan Kebijakan Perubahan Status Desa menjadi Kelurahan (Studi Kasus di Desa Pakkat Hauagong Kecamatan Pakkat Kabupaten Humbang Hsundutan

    Directory of Open Access Journals (Sweden)

    Hanaya C Simamora

    2012-11-01

    Full Text Available This study examines the dynamics of the policy process in which changes the "desa" into "kelurahan". The Consequence of the government village honorably discharged from office and position. Thus, the change is not infrequently receive rejection and defiance of them. Hauagong Pakkat Village, in Subdistrict Pakkat Humbang Hasundutan, selected as locus because the village is willing to accept and initiate change. This study examines some of the issue related to the process of policy formulation "desa" to "kelurahan" status changes, particularly regarding the importance of the village government and the regional development banks, the dynamics of the policy formulation process and considerations that drive and inhibit that they are willing to accept the policy.

  7. Pendugaan Dinamika Struktur Tegakan Hutan Alam Bekas Tebangan (Estimation of Stand Structure Dynamics of Logged-over Natural Forests

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    Muhdin .

    2011-07-01

    Full Text Available Dynamics of stand structure (DST, which could indicate the growth performance of logged-over forests, mayvary depending on various factors, e.g. stand density, initial stand structure, species composition, time afterlogging, and environmental factors (rainfall, elevation, etc..  The variations of such factors could result in thevariations of DST’s components (e.g. proportion of trees upgrowth and staying. However, this study, which used75 permanent sample plots data of lowland and dryland natural forests in Kalimantan, showed that the proportionof trees upgrowth and staying could not be predicted satisfactorily using the number of trees, stand basal area,time after logging, and elevation as independent variables in multiple linear regression models. The regressionmodels produced unrealistic projections of stand structures.  In contrast, the projection of stand structures usingthe DST’s components that were calculated using arithmetic mean was better than that of the regression models.Keywords: stand structure projection, upgrowth, natural forest, logged-over area

  8. The First Two Years of Operating Experience of the Kahl Nuclear Power Station; Experience acquise pendant les deux premieres annees de fonctionnement de la centrale nucleaire de Kahl; Opyt pervykh dvukh let ehkspluatatsii atomnoj ehlektrostantsii v Kale; Experiencia adquirida en los primeros cuatro anos de funcionamiento de la central nucleoelectrica de Kahl

    Energy Technology Data Exchange (ETDEWEB)

    Bruchner, H. J. [Aeg-Kernenergieanlagen, Frankfurt-am-Main (Germany); Weckesser, A. [Versuchs-Atomkraftwerk Kahl Gmbh, Kahl (Germany)

    1963-10-15

    , une boucle experimentale destinee a l'etude de la surchauffe nucleaire. (author) [Spanish] La central de Kahl constituye la primera central nucleoelectrica europea de propiedad privada, y funciona en carga desde junio de 1961. Esta equipada con un reactor de agua hi que trabaja en ciclo indirecto por circulacion natural. Su capacidad electrica neta asciende a 15 MW y hasta febrero de 1963 habia producido 140 millones de kWh. La memoria revisara la experiencia adquirida durante su funcionamiento, ante todo con el extenso programa de ensayos sobre el comportamiento transitorio y la exploracion gamma. Presentara datos acerca del resultado que han dado en funcionamiento ciertas partes de la central, tales como el dispositivo de accionamiento de las barras de control, el sistema de purificacion de los gases de escape y la turbina. Una vez terminado el programa de ensayos, la planta se exploto en carga basica durante algun tiempo a fin de reunir datos sobre el rendimiento del combustible en la ptactica. Una vez completada esta fase, se instalara en el reactor de Kahl un circuito experimental de sobrecalentamiento nuclear. (author) [Russian] Atomnaya ehlektrostantsiya v Kale, pervaya v Evrope chastnaya atomnaya ehlektrostantsiya, ehkspluatiruetsya pod nagruzkoj s iyunya 1961 goda. Na ehlektrostantsii ustanovlen reaktor s kipyashchej vodoj, kosvennym tsiklom i estestvennoj tsirkulyatsiej. Chistaya ehlektricheskaya moshchnost' reaktora sostavlyaet 15 mgvt. Do fevralya 1963 goda kolichestvo poluchennoj ehnergii sostavilo 140 mln. kvt.ch. Rassmotren opyt ehkspluatatsii, v chastnosti rasshirennaya programma ispytanij: naprimer,povedenie reaktora pri perekhodnom protsesse i kontrol' gamma-izlucheniya. Budut predstavleny rezul'taty izucheniya ehkspluatatsionnoj kharakteristiki nekotorykh komponentov ustanovki, naprimer sistemy privoda reguliruptsikh sterzhnej, sistemy udaleniya gaza i turbiny. Posle osushchestvleniya ehtoj programmy ispytanij ustanovka v techenie nekotorogo vremeni

  9. Safety analysis of RA reactor operation, I-III, Part III - Environmental effect of the maximum credible accident; Analiza sigurnosti rada reaktora RA - I-III, III deo - Posledica maksimalno moguceg akcidenta na okolinu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    Maximum credible accident at the RA reactor would consider release of fission products into the environment. This would result from fuel elements failure or meltdown due to loss of coolant. The analysis presented in this report assumes that the reactor was operating at nominal power at the moment of maximum possible accident. The report includes calculations of fission products activity at the moment of accident, total activity release during the accident, concentration of radioactive material in the air in the reactor neighbourhood, and the analysis of accident environmental effects.

  10. RA Reactor operation and maintenance (I-IX), part VII, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VII Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume covers the following reports concerned with the maintenance and repair work of the RA reactor: repair of the technical water system; maintenance of the transportation equipment; vacuuming and drying during refurbishment; repair and decontamination of the distillation device; and the report on participation of the operational dosimetry division in the RA reactor refurbishment activities.

  11. RA Research reactor, Part I: Technical and operational properties of the RA reactor; Analiza sigurnosti rada Reaktora RA I-III, Deo I: Tehnicke i pogonske karakteristike reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Zecevic, V; Nikolic, M; Popovic, B; Milosevic, M; Milic, M; Strugar, P; Pesic, M; Nikolic, V; Rajic, M; Radivojevic, J; Jankovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    RA reactor is a research reactor with rather high power density. Apart from research it is used for isotope production and industrial applications due to high reactivity excess (about 11%). It is a thermal reactor, heavy water moderated, cooled by D{sub 2}O, and H{sub 2}O, with a graphite reflector. Nominal power is 6.5 MW. Fuel is 2% enriched metal uranium, reactor core height is 1220 mm, and diameter is 1405 mm. Reactor lattice is square with lattice pitch 130 mm. There is 6 horizontal experimental channels and a graphite column. There is a total of 84 fuel channels and 45 experimental channels in the core. Maximum thermal neutron flux is 5.5 10{sup 13} n/cm{sup 2} s at nominal power level.

  12. Theoretical analysis of nuclear reactors (Phase III), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, III Deo, Zatrovanje reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Report on calculation of poisoning in experimental and power reactor includes four parts. Part one describes the influence of poisoning on the physical parameters of a reactor. part two includes transformation of differential equations for iodine and xenon. It was needed for easier solution of of differential equation using the analog computer. This calculation was done for RA reactor operating at 5 MW power. The RA reactor was used an example of calculation by the proposed method. Part four shows the application of the method for calculating the Calder Hall power reactor.

  13. RA reactor safety analysis I-III, Part III - Environmental effect of the maximum credible accident; Analiza sigurnosti rada Reaktora RA I-III, III deo - Posledica maksimalno moguceg akcidenta na okolinu reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    The objective of the maximum credible accident analysis was to determine the integral radiation doses in the vicinity of the reactor and in the environment. In case of RA reactor the maximum credible accident, meaning release of the fission products, would be caused by fuel elements meltdown. This analysis includes the following calculation results: activity of the fission products, volatility of the fission products, concentration of radioactive materials in the air, analysis of the accident environmental effects.

  14. Safety analysis of RA reactor operation, I-II, Part I - RA reactor technical and operation characteristics; Analiza sigurnosti rada reaktora RA - I-III, I deo - Tehnicke i pogonske karakteristike reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    RA research reactor is a thermal, heavy water moderated system with graphite reflector having nominal power 6.5 MW. The 2% enriched metal uranium fuel in the reactor core produces mean thermal neutron flux of 2.9 10{sup 13} neutrons/cm{sup 2} s, and maximum neutron flux 5.5 10{sup 13} neutrons/cm{sup 2} s. main components of the reactor described in this report are: rector core, reflector, biological shield, heavy water cooling system, ordinary water cooling system, helium system, reactor control system, reactor safety system, dosimetry system, power supply system, and fuel transport system. Detailed reactor properties and engineering drawings of all the system are part of this volume.

  15. RA Reactor operation and maintenance (I-IX), part VIII, Task 3.08/05, Decontamination of the reactor; Pogon i odrzavanje reaktora (I-IX), VIII Deo, Zadatak 3.08/05 Dekontaminacija reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Permanent increase of radiation in the heavy water system was noticed during first three year of the RA reactor operation, even when the reactor was shutdown. It was found that there was no failure of the fuel element cladding. Radioactive cobalt was found in the heavy water which was rather strange. During repair of the heavy water system, it has been found that stellite was used for coating the heavy water pumps. Since stellite is a cobalt alloy, this could have been the source of radioactive cobalt in the heavy water. The stellite coating was damaged due to friction and particle of cobalt appeared in the coolant, they were activated since they were in the core. decontamination of the heavy water and the heavy water coolant loop was a must . Beside the detailed report on the contamination and decontamination of the heavy water system this volume includes 14 annexes describing the investigation of the event and the whole procedure of decontamination.

  16. RA Reactor operation and maintenance (I-IX), Part IV, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora RA (I-IX), IV Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume contains reports describing maintenance and repair work of the RA reactor instrumentation, equipment of the reactor dosimetry control system, and equipment for regulation and control systems.

  17. Theoretical analysis of nuclear reactors (Phase I), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, III Deo, Zatrovanje reaktora, I faza

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Method was developed for calculation of Xe{sup 135} static effect and kinetic effects of Xe{sup 135} and Sm{sup 149} with separate treatment of iodine effect and influence of reactor poisoning during power increase. Mentioned effects are treated first for uranium fuel and then the basic formulae were generalized for a mixture of fissile material. The annex contains a table with data needed for calculations and the Xe{sup 135} microscopic capture cross section dependent on temperature. Razradjen je metod proracuna statickog efekta Xe{sup 135} zatim kinetickog efekta Xe{sup 135} i Sm{sup 149} sa posebnim tretiranjem jodne jame i promene zatrovanja pri prelazu sa jedne snage na drugu. Navedeni efekti su tretirani prvo za uransko gorivo, a zatim su glavni obrasci uopsteni za smesu fisibilnih materijala. U prilogu su dati u vidu tabele, podaci potrebni za proracun i grafik zavisnosti mikroskopskog preseka zahvata Xe{sup 135} od temperature.

  18. Theoretical analysis of nuclear reactors (Phase II), I-V, Part III, Reactor poisoning; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, III Deo, Zatrovanje reaktora, II faza

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This phase is dealing with influence of all the fission products except Xe{sup 135} on the reactivity of a reactor, usually named as reactor poisoning. The first part of the report is a review of methods for calculation of reactor poisoning. The second part shows the most frequently used method for calculation of cross sections and yields of pseudo products (for thermal neutrons). The system of equations was adopted dependent on the conditions of the available computer system. It is described in part three. Detailed method for their application is described in part four and results obtained are presented in part five.

  19. RA Reactor operation and maintenance (I-IX), part VI, Task 3.08/04, Refurbishment of the RA reactor; Pogon i odrzavanje reaktora (I-IX), VI Deo, Zadatak 3.08/04 Remont reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During the period planned for maintenance and refurbishment of the RA reactor the gas reactor system including the ventilation system was inspected and tested, the components were cleaned. This report describes detailed instructions and actions concerning repair and decontamination of the gas and ventilation systems components.

  20. Study of power reactor dynamics by stochastic reactor oscillator method; Proucavanje dinamike reaktora snage metodom stohastickog reaktorskog oscilatora

    Energy Technology Data Exchange (ETDEWEB)

    Velickovic, Lj; Petrovic, M [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1968-12-15

    Stochastic reactor oscillator and cross correlation method were used for determining reactor dynamics characteristics. Experimental equipment, fast reactor oscillator (BOR-1) was activated by random pulses from the GBS-16 generator. Tape recorder AMPEX-SF-300 and data acquisition tool registered reactor response to perturbations having different frequencies. Reactor response and activation signals were cross correlated by digital computer for different positions of stochastic oscillator and ionization chamber.

  1. Study of heterogeneous nuclear reactor lattice properties in multizone systems; Ispitivanje karakteristika resetke heterogenih nuklearnih reaktora u visezonim sistemima

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Described analysis of substitution experiments and its comparison with the classic procedures showed that it could be successfully applied for processing the experimental results. This method shows some advantages and some deficiencies compared to classic methods. Precision of the method is considered sufficient for design of nuclear facilities. Routine standards used in design of nuclear facilities demand following precision of nuclear parameters: about 5% during feasibility study and design of heavy water facility with natural uranium; 2 - 3% in the phase of parameters optimisation and preparing the main project; 1% during optimization of operation. Accuracy of core parameters obtained by analysis of substitution experiments show that they could be successfully used in the phase of reactor parameters optimisation. It is possible to increase the precision of critical parameters and thus apply the proposed method for analysis of reactor parameters needed in the phase of operation optimization.

  2. Operation and maintenance of the RA reactor in 1965; Pogon i odrzavanje reaktora RA. Izvestaj o radu u 1965. godini

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-01-15

    It has been planned for 1965 that the RA reactor would be operated each month for 20 days at nominal power of 6.5 MW, at lower power for 5 days, meaning production of 27 400 MWh. The plan was fulfilled since reactor produced 28809 MWh, i.e. 5% more than planned. Reactor was used for irradiation in the vertical experimental channels according to the demand of 1264 users from the Institute and 191 external users. Two groups of experiments done: at nominal power simultaneously with isotope production and experiments which demanded particular power levels and temperatures. Three fuel exchanges were done during this year, meaning that 40 fuel channels were changed in total. Vertical experimental channels VEK-1 and VEK-9 having diameter 100 mm were changed by channels having diameter 50 mm and shortened by 435 mm. Channel VEK-5 with diameter 110 mm was changed shortened by 430 mm. This enabled better fuel economy, the burnup was increased from 4500 MWd/t to 5000 MWd/t. This report contains the action plan for 1966.

  3. RA Reactor operation and maintenance (I-IX), Part I; Pogon i odrzavanje reaktora RA (I-IX), I Deo

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    The report on RA reactor operation and maintenance for year 1963 is divided in six tasks. This volume contains the introductory report, and three tasks of the final report, namely reactor exploitation, reactivity changes of the RA reactor before repair, planning of refuelling.

  4. Accident analysis of RB reactor dependent on the lattice pitch; Akcidentalna analiza reaktora ''RB'' pri promeni koraka resetke

    Energy Technology Data Exchange (ETDEWEB)

    Lolic, B; Lazarevic, B [Boris Kidric Institute of nuclear sciences, Vinca, Belgrade (Yugoslavia)

    1963-07-01

    This analysis was concerned with reactor core with 52-56 fuel rods, lattice pitch being, 8, 10, 12, 16, 18, and 20 cm. Measured values of excess reactivity above critical level of 3.85 cm, total anti reactivity of regulating rod, reactivity changes caused by pumping heavy water and reactivity variations due to movement of control rod were used. Three types of accidents were analyzed: movement of regulating rod to the position of zero reactivity worths, increase of heavy water level at rate of 2.5 cm/min, combination of two previous accidents.

  5. Epithermal neutron flux in the experimental channels of the RA reactor; Fluks epitermalnih neutrona u eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Epithermal neutron flux was determined by measuring the cadmium ratio from activation analysis of gold and indium foils. Irradiation was done in experimental channels VK-5, VK-2, VK-7, VK-0, VK-HS next to the core, and next to the fuels elements. Activation of bare foils and foils covered by 0.8 and 1.0 mm thick cadmium foils was done simultaneously. Activity was measured by GM counter. Corrections were done for resonant neutrons self-absorption since the foils used were too thick concerning most important resonances of gold and indium. Final results were presented as spectrum factor r for their direct use in determining the effective neutron cross sections.

  6. Neutron measurements inside reactors with semiconductor counters; Apsolutno merenje neutronskih flukseva u jezgru reaktora RA visokim snagama

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, V; Lalovic, B; Barucija, M; Petrovic, B [Institute of Nuclear Sciences Boris Kidric, Laboratorija za fiziku i dinamiku reaktora, Vinca, Beograd (Serbia and Montenegro)

    1964-06-15

    A method of absolute in-core measurement of high neutron fluxes inside reactors operating in the megawatt region is described. In this method a semiconductor counter observes particles coming from neutron induced reactions in a target placed inside the reactor core through a long evacuated aluminum tube. The paper deals with factors which influence the accuracy of the method. Possible use of the long- tube method for neutron flux measurements in advanced reactors with neutron flux of 10{sup 15}-10{sup 16} n/cm{sup 2} sec is also discussed. The possibility of using the Li{sup 6} semiconductor counter spectrometer for measuring fast neutron spectra inside the zero power reactor at Vinca has been investigated. Great difficulties associated with the high interference of thermal neutrons have been encountered. The thermal neutron interference is almost completely suppressed by a new detector-target arrangement, in which only those products of the Li{sup 6} (n,alpha)T reactions whose mutual angle of emission is different from 180 deg are detected in coincidence. Resolution of the spectrometer as a function of the reactor power and correction factors of the spectrometer efficiency for various neutron energies are presented (author)

  7. Operation of the RA research nuclear reactor under forced regime; Rad istrazivackog nuklearnog reaktora RA u forsiranom rezimu

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Ra reactor was designed for operation at nominal power of 6.5 MW and under forced regime. From the start of operation in 1959 until the general refurbishment in 1963 it was not operated under forced regime. At reactor power of 10 MW the mean thermal neutron flux increases from 3 to 4.6 10{sup 13} n cm{sup -2} sec{sup -1}, the maximum neutron flux increases from 6 to 9.3 10{sup 13} n cm{sup -2} sec{sup -1}, and at the exit of the experimental channel it increases from 5 to 7.7 10{sup 9} n cm{sup -2} sec{sup -1}. In order to achieve safer and more suitable operating conditions, winter period of 1963 was chosen for the first increase of reactor power level, because of low temperatures in the secondary coolant loop. This paper contains the most relevant data concerned with the reactor operation at increased power.

  8. Nuclear Reactor RA Safety Report, Vol. 9, Radiation protection; Izvestaj o sigurnosti nuklearnog reaktora RA, Knjiga 9, Zastita od zracenja

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

    Instrumentation for Radiation protection existing at the RA reactor is dating mostly from the period 1957-1959 when the reactor has been built. With some minor exception it was produced in USSR. Radiation protection system was constructed based on specific design project, somewhat modified original USSR project which has been indispensable because of some modification of the building design. During the past 27 years no renewal of the instrumentation was done, only maintenance was performed. Instrumentation consists of old electronic devices which caused difficulties and even prevented regular maintenance because of lack of spare parts. Instrumentation for radiation protection at the RA reactor is classified as follows: centralized dosimetry system; stationary dosimetry instrumentation, movable and personal dosimetry systems. Apart from the scheme of dosimetry instrumentation this volume includes description of radiation protection procedures; protection devices; radiation doses and dose limit data; program for environmental radioactivity control; medical control procedures. [Serbo-Croat] Instrumentacija za zastitu od zracenja koja danas postoji na reaktoru RA najvecim delom potice iz perioda 1957-1959 kada je reaktor gradjen. Sa malim izuzetcima instrumentacija je proizvedena u SSSR. Sistem za zastitu izveden je na osnovu posebnog projekta koji predstavlja modifikaciju originalnog projekta koja je bila neophodna usled modifikovanog gradjevinskog projekta. U proteklom periodu od 27 godina instrumentacija nije obnavljana vec je vrseno samo odrzavanje. Instrumentacija je izradjena u danas prevazidjenoh tehnoligiji (elektronske cevi) sto je otezavalo i skoro onemogucavalo normalno odrzavanje. Instrumentacija za zastitu od zracenja na reaktoru RA moze se podeliti na tri dela: centralizovani dozimetrijski sistem; stacionarna dozimetrijska instrumentacija; prenosna i licna dozimetrijska instrumentacija. Pored seme sistema dozimetrijske kontrole ova knjiga sadrzi opis postupaka zastite od zracenja; zastitne opreme; podatke o dozama zracenja i granicne vrednosti; program kontrole radioaktivnosti okoline; mere medicinske kontrole.

  9. Response to local reactivity perturbation of thermal multizone reactors; Odziv termalnih multizonih reaktora na lokalnu perturbaciju reaktivnosti

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Jevtovic, V [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper describes application of the mode analysis, spatial eigenfunction expansion for solving the time dependent diffusion equation in two-group approximation, for the case of time dependent absorption cross section in the thermal region. Transfer functions for radially multi zone and homogeneous reactor systems were obtained as results of solving the time-dependent diffusion equation. Some numerical results obtained by applying this method are given as well. U radu je primenjena modalna analiza, razvoj po prostornim svojstvenim funkcijama, za resavanje vremenski zavisne difuzione jednacine u dvogrupnoj aproksimaciji, kada je presek za apsorpciju u termalnoj grupi funkcija vremena. Kao rezultat resavanja vremenski zavisne difuzione jednacine dobijeni su izrazi za prenosne funkcije radijalno multizonih reaktorskih sistema i homogenih reaktorskih sistema. Dati su i neki numericki rezultati primene ove metode (author)

  10. Response of thermal multi zone reactors to local perturbation of reactivity; Odziv termalnih multizonih reaktora na lokalnu perturbaciju reaktivnosti

    Energy Technology Data Exchange (ETDEWEB)

    Obradovic, D; Jevtovic, V [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1967-01-15

    A modal analysis method, spatial eigenfunctions expansion, was applied for solving the time dependent diffusion equation in two-group approximation. The absorption cross section in the thermal neutron range was time dependent. The response functions for radially multi-zone reactor systems and homogeneous reactors were obtained as solutions of the time dependent diffusion equation. Some numerical results obtained by this method are included. U radu je primenjena modalna analiza, razvoj po prostornim svojstvenim funkcijama, za resavanje vremenski zavisne difuzione jednacine u dvogrupnoj aproksimaciji, kada je presek za apsorpciju u termalnoj grupi funkcija vremena. Kao rezultat resavanja vremenski zavisne difuzione jednacine dobijeni su izrazi za prenosne funkcije radijalno multizonih reaktorskih sistema i homogenih reaktorskih sistema. Dati su i neki numericki rezultati primene ove metode (author)

  11. Annex 2 - Design concept of RA reactor fuel element fabrication; Prilog 2 - Koncepcija izrade gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, M; Mihajlovic, A; Ristic, M; Simic, G [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This document shows the construction and description of the individual parts of the fuel element. Planned procedures for fabrication of Al cladding and the fuel element structure are presented. Within the analysis of the results, claddings obtained by applying the proposed procedure are presented as well as the future plans. Dat je prikaz konstrukcije sa opisom i ulogom pojedinih sastavnih delova i sklopa gorivnog elementa. Izneta su predvidjanja za izradu, kako Al kosuljice, tako i sklopa gorivnog elementa. U analizi dosadasnjih rezultata, prikazane su kosuljice dobijene po navedenim postupcima, kao i smernice daljeg rada (author)

  12. RA reactor safety analysis, Part II - Accident analysis; Analiza sigurnosti rada Reaktora RA I-III, Deo II - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Radanovic, Lj; Milovanovic, M; Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This part of the RA reactor safety analysis includes analysis of possible accidents caused by failures of the reactor devices and errors during reactor operation. Two types of accidents are analyzed: accidents resulting from uncontrolled reactivity increase, and accidents caused by interruption of cooling.

  13. Fast neutron flux in the RA reactor experimental channels; Fluks brzih neutrona u eksperimentalnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N; Dobrosavljevic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Fast neutron flux in the RA reactor experimental channels was determined by using threshold reaction detectors. The (n,p) type reactions S{sub 32} (n,p)P{sub 32}, and Al{sub 24} (n,p)Na{sub 24}. Prepared sulphur and phosphorous foils were placed in cadmium boxes and irradiated in experimental channels VK-5, VK-7 and VK-9. Gold foils were irradiated simultaneously for controlling the reactor power. Reactor power was 100 kW during irradiation of half an hour. Activity of P{sub 32} and S{sub 31} after reactor shutdown was measured by 4{pi} counter and three calibrated GM counters. Absolute neutron flux was determined by using thus obtained data.

  14. Investigation of the heavy water distillation system at the RA reactor; Ispitivanje sistema za destilaciju teske vode reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Badrljica, R [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    The heavy water distillation system was tested because this was not done before the reactor start-up. Detailed inspection of the system components showed satisfactory results. Leak testing was done as well as the testing of the instrumentation which enables reliable performance of the system. Performance testing was done with ordinary water and later 2700 l of heavy water from the reactor was purified, decreasing the activity by 45%.

  15. Program of RA reactor start-up to nominal power; Program dizanja reaktora 'RA' na nominalnu snagu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-01

    The zero start-up program is followed by the program of RA reactor start-up to nominal power. This program is desed in detail and includes the following measurements: radiation characteristics at the exit of the channels; gamma and fast neutron dose distribution in the reactor; influence of absorbers on the reactivity; temperature effect; absolute flux and calibration of ionization chambers; xenon effect; thermal and hydraulics; dosimetry around the reactor; neutron flux in the reactor core and in the reactor hall; heavy water level; thermal characteristics after shutdown. A list of measuring devices and instrumentation is included with the detailed action plan and list of responsible staff members.

  16. Dinamika PMA dan PMDN di Indonesia Sebagai Dampak Dari Upah Minimum, Inflasi dan PDRB Tahun 2004-2012: Pendekatan Dynamic Panel Data Model

    Directory of Open Access Journals (Sweden)

    Lea Widowati Sugiharto

    2016-06-01

    Full Text Available This paper aims at investigating the behavior of foreign direct investment (FDI and domestic direct investment (DDI in Indonesia, which is expected to be explained by several explanatory variables including the setting of regional minimum wage, inflation, as well as regional domestic product. More specifically, the investigation is focused on the effect of annual increase in the minimum regional wage, provided that it is a sensitive issue for investors. Using 33 provincial level data in a period from 2004 to 2012, this paper uses a dynamic panel data which allows us to see the behavior of direct investment in the short run as well as in the long run. The result shows that an increase in the regional minimum wage setting reduces both DDI and FDI in the short run. However, in the long run, an increase in the regional minimum wage is likely to increase both DDI and FDI. This is likely indicating that in the long run an increase in wage is expected to be accompanied by higher productivity, eventhough in the short run higher wage increases cost of production which will undermine investment.

  17. DINAMIKA KOMUNITAS PLANKTON DI PERAIRAN EKOSISTEM HUTAN BAKAU SEGARA ANAKAN YANG SEDANG BERUBAH (Plankton Dynamic in the Changing Mangrove Ecosystem of Segara Anakan Central Java

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    Tjut Sugandawaty Djohan

    2010-11-01

    Full Text Available ABSTRAK Perairan hutan bakau Segara Anakan merupakan ekosistem yang sedang berubah karena sedimentasi yang tinggi sejak tahun 1980, dan telah mengakibatkan pendangkalan perainan dan mengganggu proses pasang surut. Perubahan ekosistem ini direspon oleh komunitas plankton. pada musim hujan tabun 2002 salinitas perairannya adalah 0 0/00' dan musim kemarau 20 – 32%. Perubahan komunitas plankton tersebut dicirikan hadimya komunitas baik phyto maupun zooplankton dominan sungai pada musim hujan, dan sebaliknya komunitas laut pada musim kemarau. Pada tahun 2004, karena pendangkalan di perairan Bondan, mudflat dan perairannya dikeruk. Penelitian ini bertujuan untuk mempelajari respon komunitas phyto dan zooplankton terhadap pernbanan ekosistem pada musim kemarau Agustus 2005 di daerah tangkapan ikan nelayan perairan Segara Anakan. Hasil menunjukkan bahwa ada peledakan kemelimpahan phytoplankton yang didommasi olehl populasi Chaetoceros di perairan Bondan dan Klaces sebanyak 206890 dan 397273 individu per 100 liter, dan populasi  Asterione/lajaponica meningkat sebanyak 69778 per 100 liter di perairan Cigatal. Peledakan kedua genus tersebut adalah merupakan respon phytoplankton terhadap meningkatnya kandungan PO4 di perairan oleh pengerukan sedimen di perairan Bondan. Kenaikan P04 di perairan berturut-berturut dari Bondan ke Cigatal sebesar 4,95 ppm, 5,88 ppm, dan 4,62 ppm. Pada musim kemarau, perairan Segara Anakan juga dicirikan dengan hadimya komunitas plankton sungai yaitu sebanyak 19 species phytoplankton, dan 9 spesies zooplankton. Peledakan populasi Chaetoceros tidak direspon oleh peledakan populasi zooplankton. Keadaan ini mencerminkan bahwa kualitas perairan Segara Anakan telah menurun.   ABSTRACT The mangrove ecosystem of Segara Anakan is in the process of changing to the freshwater-wetland due to the heavy sedimentation. This change was responded by the plankton communities. In the 2002 during the rainy season, the salinity was 0 0/00, and the freshwater plankton from the river dominated this mangrove ecosystem. In contrast at the dry season, the salinities were between 20 – 32 0/00, and the estuarine plankton dominated the ecosystem. In the 2004 the Bondan area became shallower and was dredged. In responding to the changing ecosystem, the phyto and zooplankton study was carried out during the dry season of August 2005 at the fishing ground of Segara Anakan. Results showed that there were blooms of phytoplankton. At the Bondan and Klaces waters, Chaetoceros dominated the communities with 206890 and 397273 individuals per 100 liter consecutively. However, at Cigatal Asterionella japonica with 69778 individuals per 100 liter dominated the community. The plankton bloom related to the intensive dredging of sediment at Bondan areas, which increased PO4 highly in the water of Bondan, Klaces, and Cigatal inconsecutively 4.95 ppm, 5.88, and 4.62 ppm. These communities were characterized by the present of 19 species of freshwater phytoplankton and 9 species of zooplankton. Even though the population of Chaetoceros was exploded, but the zooplankton community did not response to the phytoplankton increase. This indicated that the qualities of the mangrove ecosystem waters decreased, and the ecosystem was in the process of changing to freshwater-wetland ecosystem.

  18. Dinamika Populasi Hama dan Penyakit Utama Tanaman Jagung Manis (Zea mays saccharata Sturt pada Lahan Basah dengan Sistem Budidaya Konvensional serta Pengaruhnya terhadap Hasil di Denpasar-Bali

    Directory of Open Access Journals (Sweden)

    SALBERD FERDINAN RONDO

    2016-11-01

    Full Text Available Dynamics of Pest Population and Main Diseases of Sweet Corn Plants (Zeamays saccharata Sturt at Wetland with Conventional Cultivation Systemand Their Effect on Yields in Denpasar-Bali. The study was conducted usingsurvey techniques of pests and diseases in paddy fields belonging to farmers in Denpasar-Bali, which consists of three fields. The three areas were Sidakarya, Renon and Kesiman.Plant samples in each land were taken using the sample plot diagonal method, with the areaof diagonal plot in each land was 3 m x 3 m. Plot observations on each of the specified areaof plant samples was done randomly (lottery as much as 25% of the total number of plantsper-plot, then observation was done for population growth of pests and diseases, temperature,humidity and crop yield. The observations was started from 1week old plants after planting(MST to 1 week before harvesting, with intervals of 1 week. Recording the population ofpests and diseases from week to week, the temperature condition and humidity in each areaand the condition of the field ( the existing other plants, mulching. Recorded informationabout conventional cultivation systems applied by each farmer were be explored throughinterview techniques. The data were then analyzed using correlation and regression and weredescriptively explained. The results showed that there were four main types of pests (locusts,seed flies, armyworm and caterpillars cob and three kinds of major diseases (blight, rust anddowny mildew associated with sweet corn. The results also showed that there was nosignificant between the correlation dynamics of pest population and diseases withtemperature and humidity. As for the commercial harvest, significant effect was shown by thediseases that had an impact on the decrease in yield in quantity especially downy mildew andpest impact on the quality of yields, especially caterpillar cob.

  19. Pola Aktivitas Harian dan Dinamika Populasi Lalat Buah Bactrocera Dorsalis Complex pada Pertanaman Jeruk di Dataran Tinggi Kabupaten Karo Provinsi Sumatera Utara

    OpenAIRE

    Manurung, Binari; Prastowo, Puji; Tarigan, Emmi Ebrina

    2012-01-01

    The fruit fly Bactrocera dorsalis complex is important pest on citrus plantation at highland Karo district North Sumatera Province. The studies with the aim to find out its daily activity pattern and population dynamic on citrus plantation have been done. Fruit flies were collected by water bottle trap with methyl eugenol attractant. Sampling for daily activity pattern was done per two hours for two months (April to May 2011) from 06.00 a.m until 18.00 p.m. Meanwhile, population dynamic study...

  20. POLA AKTIVITAS HARIAN DAN DINAMIKA POPULASI LALAT BUAH BACTROCERA DORSALIS COMPLEX PADA PERTANAMAN JERUK DI DATARAN TINGGI KABUPATEN KARO PROVINSI SUMATERA UTARA

    OpenAIRE

    Binari Manurung; Puji Prastowo; Emmi Ebrina Tarigan

    2013-01-01

    The fruit fly Bactrocera dorsalis complex is important pest on citrus plantation at highland Karo district North Sumatera Province. The studies with the aim to find out its daily activity pattern and population dynamic on citrus plantation have been done. Fruit flies were collected by water bottle trap with methyl eugenol attractant. Sampling for daily activity pattern was done per two hours for two months (April to May 2011) from 06.00 a.m until 18.00 p.m. Meanwhile, population dynamic study...

  1. POLA AKTIVITAS HARIAN DAN DINAMIKA POPULASI LALAT BUAH BACTROCERA DORSALIS COMPLEX PADA PERTANAMAN JERUK DI DATARAN TINGGI KABUPATEN KARO PROVINSI SUMATERA UTARA

    Directory of Open Access Journals (Sweden)

    Binari Manurung

    2013-09-01

    Full Text Available The fruit fly Bactrocera dorsalis complex is important pest on citrus plantation at highland Karo district North Sumatera Province. The studies with the aim to find out its daily activity pattern and population dynamic on citrus plantation have been done. Fruit flies were collected by water bottle trap with methyl eugenol attractant. Sampling for daily activity pattern was done per two hours for two months (April to May 2011 from 06.00 a.m until 18.00 p.m. Meanwhile, population dynamic study was conducted on two citrus plantations per four days for nine months (March to November 2011 in the first and third week of each month. The research result showed that B.dorsalis complex was more active during morning at 10.00 to 12.00 a.m. The peak abundance of fruit fly occurred at the end of June until beginning of July. The peak population coincided with the ripening period of fruits, low number of rainy (d and rainfall (mm in June and July periods. There was a significant correlation between number of rainy day and rainfall with fruit flies caught per month (R = 0.79; Y = 289.34+14.23X1-15.93X2; R2 = 0.62; P < 0.05. The pattern of fruit fly fluctuation in two citrus plantations was similar (rs = 0.47; P < 0.05.

  2. Most tsherez Orezund : potentsialnaja regionalnaja dinamika : integratsija Gopengagena (Danija) i Malme-Linda (Shvetsija). Mezhegosudarstvennõi projekt na urovne Jevropeiskoi metropolii / Christian Wichmann Matthiesen

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    Wichmann Matthiesen, Christian

    2000-01-01

    Öresundi sild Rootsi ja Taani vahel. Rahvusvaheline transport. Ettekanne rahvusvahelisel konverentsil "The future of the Baltic ports". Rööptekst inglise keeles lk. 91-98. Autori elulookirjeldus lk. 87

  3. DINAMIKA PENERAPAN KEWENANGAN PEMERINTAH KABUPATEN BERAU DALAM PENGELOLAAN PERTAMBANGAN BERDASARKAN PERDA NOMOR 17 TAHUN 2011 TENTANG PERTAMBANGAN MINERAL DAN BATU BARA

    Directory of Open Access Journals (Sweden)

    Muhammad Amin, S.H. M.H

    2017-05-01

    Full Text Available One form of state ownership rights, namely in the field of mining. Definition of "Mining" based on Law Number 4 Year 2009, affirmed as part or all phases of activity in the framework of research, management and exploitation of minerals or coal covering general investigation, exploration, feasibility study, construction, mining, processing and refining, transportation And sales and post mining activities. More specifically affirming the authority of regional governments in granting coal mining permits in Berau District before and after the coming into effect of Law No. 4 of 2009 on Mineral and Coal Mining. Obstacles and solutions in the granting of coal mining permits in Berau District after the enactment of Berau District Regulation No. 17 of 2011 on Mining and Coal. The research method used in this research is normative juridical and method of comparative law approach. The normative juridical approach is the approach by prioritizing the discussion on secondary data in the form of legal materials both primary, secondary and tertiary legal materials. The results of the discussion confirm that mineral and coal energy resources as assets to meet the needs of present and future generations as mandated in the Constitution of the State of the Republic of Indonesia 1945 XIV National Economic and Social Welfare Article 33 paragraph (3 and Article 33 Paragraph (4 where mining management does not entitle rights to control over natural resources, but the right to limited utilization is based on permission and is temporary with the understanding that natural resources are owned by all Indonesian people and used for the greatest prosperity of the people.

  4. POLITIK IDENTITAS DALAM KONSTUKSI IDENTITAS ETNIK MANDAR SEBAGAI UPAYA REINVENTION OF IDENTITY (STUDI KUALITATIF KOMUNITAS MANDAR DALAM PEMBENTUKAN IDENTITAS ETNIKNYA)

    OpenAIRE

    Sukri Tamma; Gustiana A. Kambo

    2008-01-01

    ABSTRAK EKOSOSBUDKUM 2010 Penelitian ini diarahkan untuk memahami kompleksitas dinamika politik lokal yang berlatarbelakang identitas dan etnisitas. Dinamika ini terjadi di wilayah etnik Mandar sebagai refresentasi dari Sulawesi Barat. Masalah penelitian yang dikemukakan, pertama, bagaimanakah etnik Mandar mempertahankan identitasnya yang telah dikonstruksikan? Apakah identitas tersebut dapat memperkuatmodal social etnik Mandar sebagai komunitas yang kuat? Kedua, Apakah pemaknaan dan pener...

  5. Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca; Radovi za potrebe eksploatacije reaktora RA - I-IV, II Deo, Predprojekat VI-SA 1, Petlja za ispitivanje gorivnih elemenata reaktora EL-4 u centralnom vertikalnom eksperimentalnom kanalu reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO{sub 2} with beryllium cladding, cooled by CO{sub 2} under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO{sub 2}. This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment.

  6. Spatial distribution of reactor radiation around the horizontal experimental hole of the RA Reactor at Vinca; Prostorna raspodela reaktorskog zracenja oko horizontalnog eksperimentalnog kanala reaktora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Paligoric, D; Vujisic, B [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1964-10-15

    A survey is given of the measurement of the spatial distribution of thermal and fast neutrons and gamma radiations inside and around the reactor radiation beam which is carried through the experimental channel outside the reactor biological shield thus being a potential danger for the personnel in the reactor hall. The results obtained are used to determine the optimal distribution of the shielding elements around the free radiation beam. The activation method was used to determine the distribution of slow and fast neutrons. The detectors were Au{sup 197} and In {sup 115} for slow, and the S{sup 32} (n,p) P{sup 32} reaction for fast neutrons. The relative distribution of slow and fast neutrons along the beam axis in the space outside the reactor, and evaluation of the absolute value of the flux at the place where the beam comes out from the biological shield are given (author)

  7. Two-channel model for dynamic analysis of GCR type reactor, Mathematical model; Dvokanalni model za dinamicku analizu reaktora GCR tipa, formulacija matematickog modela

    Energy Technology Data Exchange (ETDEWEB)

    Bingulac, B; Lazarevic, B; Matausek, M; Radanovic, Lj [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    A two-channel model for reactor dynamic analysis was developed. It enables representation of time dependent behaviour of a reactor as a whole and to obtain time and space dependent changes of temperature in any of the reactor channel. Model is suitable for follow-up of phenomena in limited time intervals up to few tens of minutes, since long term variations caused by fuel burnup and fission products are not taken into account in the model. Parameters are defined to cover the reactor power range from minimum to maximum. Model describes two main processes in the reactor: power generation dependent on the neutron flux and cooling.

  8. Testing measurements at horizontal channels of the MARIA reactor performed using neutron spectrometers; Pomiary testowe przy kanalach poziomych reaktora MARIA wykonane przy uzyciu spektrometrow neutronow

    Energy Technology Data Exchange (ETDEWEB)

    Murasik, A. [Institute of Atomic Energy, Otwock-Swierk (Poland)

    1997-12-31

    By means of neutron diffraction, using the standard polycrystalline sample of Al{sub 2}O{sub 3}, measurements on three (of four spectrometers) already installed in the front of horizontal channels of MARIA reactor have been performed. Basing on these experiments as well as on activation measurements carried out earlier, the fluxes of monoenergetic neutrons have been estimated. These experiments allowed to determine (for a given geometry and kind of monochromators chosen) the resolution efficiency of instruments and high order contamination in the reflected beam. With the help of polycrystalline vanadium and TbBr{sub 3} sample, the possibility of studies using the inelastic scattering process have been tested. (author) 7 refs, 15 figs, 7 tabs

  9. Dosimetry and radiation protection at the RA reactor, Report for 1978 - Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1978. godinu -

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This annex includes data about measured levels of gamma and neutron irradiation as well as level of contamination of the working environment. In addition it covers data about irradiation of the staff, contamination, decontamination of the surfaces, and radioactive waste. During 1978 there were no significant accidents that could impact either staff or the environment. [Serbo-Croat] Ovaj prilog sadrzi podatke o merenim nivoima gama i neutronskog zracenja kao i stepenu kontaminacije radne sredine na reaktoru RA. Pored toga dati su podaci o ozracivanju osoblja, kontaminaciji, dekontaminaciji i radioaktivnom otpadu. Akcidenata vecih razmera koji bi imali znacajnije posledice po osoblje i okolinu tokom 1978. godine nije bilo.

  10. Measurement of rod-drop time for control and safety rods at the RB reactor; Merenje vremena pada kontrolne sipke i sigurnosnih sipki reaktora RB

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M; Marinkovic, P; Stefanovic, D [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1990-12-15

    The objective of this task was to determine the thermal utilization factor f in a heterogeneous reactor cell. For this purpose reliable data about thermal neutron spatial distribution are needed. Spatial distribution of the thermal neutron flux in the reactor cell was measured by perturbation method which showed best results compared to other methods described in this paper experiments were done at the RB reactor.

  11. Estimation of the influence of nuclear reactors in Vinca on the radiation situation in Belgrade; Procena uticaja nuklearnih reaktora u Vinci na radijacionu situaciju u Beogradu

    Energy Technology Data Exchange (ETDEWEB)

    Marsicanin, B [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1981-07-01

    Both reactors RB and RA were built in the period of non existing environmental regulations nor IAEA recommendations. The objective of this study was to review the present radiation situation on the territory of Belgrade, especially the influence of these reactors which could arise in case of some emergency or possible accidental event. This report includes detailed technical data, demographic, meteorological and other information which are significant for the analysis of accidental radioactivity release from the reactors in Vinca.

  12. Dosimetry and radiation protection at the RA reactor, Report for 1976 - Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1976. godinu -

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This annex includes data about measured levels of gamma and neutron irradiation as well as level of contamination of the working environment. In addition it covers data about irradiation of the staff, contamination, decontamination of the surfaces, and radioactive waste. During 1976 there were no significant accidents that could impact either staff or the environment. [Serbo-Croat] Ovaj prilog sadrzi podatke o merenim nivoima gama i neutronskog zracenja kao i stepenu kontaminacije radne sredine na reaktoru RA. Pored toga dati su podaci o ozracivanju osoblja, kontaminaciji, dekontaminaciji i radioaktivnom otpadu. Akcidenata vecih razmera koji bi imali znacajnije posledice po osoblje i okolinu tokom 1976. godine nije bilo.

  13. Measurement of the heavy water level in the fuel channels of the RA reactor - Annex 11; Prilog 11- Merenje nivoa teske vode u gorivnim kanalima reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    The objective of measuring the heavy water level in the reactor channels was to verify experimentally the possibilities of reactor cooling with parallel operation of heavy water pumps od 1500 rotations/min at nominal power of 6.5 MW. Measurements were done in 2 periphery and 2 central fuel channels with pumps speed 1500, 1800 and 3000 rotations/min by a contact probe with electric resistance measuring device. precision of the measurement was {+-}1 cm.

  14. Analysis of neutron flux increase in the horizontal experimental channels of Ra reactor - masters thesis; Analiza povecanja neutronskog fluksa na horizontalnim eksperimentalnim kanalima reaktora RA - magistarski rad

    Energy Technology Data Exchange (ETDEWEB)

    Strugar, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1964-12-01

    Calculation and experimental results shown in this paper show that higher thermal neutron flux is obtained in the reactor core with central horizontal reflector at the same power level. The flux is increased when the moderation capability of the core is decreased. Apart from increase of the thermal component of the neutron flux in the experimental channels, the central reflector causes decrease of the epithermal neutron flux and gamma radiation intensity. This is very useful for studying (n, {gamma}) reaction, neutron diffraction, etc. [Serbo-Croat] Rezultati proracuna i merenja prikazanih u ovom radu ukazuju na cinjenicu da se u reaktoru sa ugradjenim centralnim horizontalnim reflektorom dobija veci fluks termalnih neutron pri istoj snazi i to utoliko veci ukoliko je moderaciona sposobnost aktivne zone manja. Pored uvecanja termalne komponente neutrona u snopu na horizontalnim eksperimentalnim kanalima centralni reflektor uslovljava i smanjenje epitermalne komponente, kao i intenzitet gamma zracenja. Ovo je pozeljno za proucavanje (n,{gamma}) reakcija, neutron diffraction, etc.

  15. Model for spatial synthesis of automated control system of the GCR type reactor; Model za prostornu sintezu sistema automatskog upravljanja reaktora GCR tipa

    Energy Technology Data Exchange (ETDEWEB)

    Lazarevic, B; Matausek, M [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

    1966-07-01

    This paper describes the model which was developed for synthesis of spatial distribution of automated control elements in the reactor. It represents a general reliable mathematical model for analyzing transition states and synthesis of the automated control and regulation systems of GCR type reactors. One-dimensional system was defined under assumption that the time dependence of parameters of the neutron diffusion equation are identical in the total volume of the reactor and that spatial distribution of neutrons is time independent. It is shown that this assumption is satisfactory in case of short term variations which are relevant for safety analysis.

  16. Planning the RA reactor fuel exchange - Task 3.08/03; Zadatak 3.08/03 - Planiranje izmene goriva reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Dobrosavljevic, N; Strugar, P [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    From the reactor start-up until January 1963, after reactor operation of 1246 MWd , there was a need for fuel exchange. It was necessary to develop a method for planning the refuelling scheme which would enable economic and most appropriate further operation. The most suitable scheme for refuelling would be continuous exchange, but this cannot be performed since each fuel exchange demand reactor shutdown of approximately 15 days. For that reason a compromise scheme was adopted, meaning the fresh fuel is added after each 60-80 days of operation. This report describes the method for approximate calculation of reactivity increase during exchange of the spent fuel element with the fresh one. Detailed plan for exchange of fuel exchange is given in the conclusions.

  17. Operation and maintenance of the RA reactor in 1964, I-II, Part I; Pogon i odrzavanje reaktora RA u 1964. godini, I-II, I Deo

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    During 1964, the Reactor as operated about 20 days each months at nominal power of 6.5 MW, 5 days at lower power levels and 5 days were used for maintenance. Total production was 27930 MWh which is 11.7% higher than the planned value. Fuel exchange was done 3 times during this period, 98 spent fuel channels were exchanged. In addition to routine maintenance of reactor components and instruments a series of analyses of heavy water and helium were done. Special attention was devoted to corrosion analyses of the reactor materials because of the heavy water system was refurbished decontaminated in 1963. Utilization of the experimental space in the reactor was better that previously. 546 samples were irradiated till the end of November, of which 443 for users from the Institute. Specific irradiations in the fast neutron flux were done in six VISA-2 channels in the core.

  18. Determining axial perturbation of the reactor cell by introducing construction material into reactor fuel element; Odredjivanje aksijalne perturbacije celije unosenjem konstrukcionog materijala u gorivni element nuklearnog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Dimitrijevic, V [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1975-07-01

    Axial distribution of thermal neutrons in the center and on the surface of a fuel element in the presence of aluminium was measured by reactor cell perturbation method. Experiments were performed by Dy activation foils using 20 mm thick Al disc placed between two fuel elements. Measured values of thermal neutron flux distribution in the reactor cell were compared to calculated values obtained by one-group neutron diffusion method.

  19. WWER-440 reactor emergency cooling using `feed and bleed` procedure; Avarijnoe raskholazhivanie reaktora WWER-440 s pomoshtyu protsedury `podpitka-produvka`

    Energy Technology Data Exchange (ETDEWEB)

    Marinov, M; Dimitrov, B; Popov, E; Avdzhiev, K [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A procedure for emergency cooling in the case of total loss of coolant water is proposed. `Feed and bleed` procedure is applied by the operator and its main goal is to maintain a predefined level in the primary circuit and low pressure and temperature in the reactor. Two extreme cases are considered: 1. the loss of coolant is combined with a blackout; 2. the loss of feeding water is due to a general failure in the control room. The accidents are simulated and the relevant time intervals are estimated. After a simulated operator action following the procedure the reactor temperature is evaluated to 147{sup o} C and the primary circuit pressure to 10 bar. 1 ref., 4 figs., 2 tabs.

  20. Safety analysis of RA reactor operation, I-III, Part II, Accident analysis; Analiza sigurnosti rada reaktora RA - I-III, II deo - Analiza akcidenta

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    This volume covers the analyses of two types of accidents: accidents caused by uncontrolled reactivity increase, and accidents caused by decrease or loss of cooling. First type of accidents, uncontrolled reactivity insertion could occur due to removal of compensation, regulatory or safety rods, or by increase of heavy water level. Removal of irradiated samples from the core could also cause increase of reactivity. Second type of accidents could occur due to interruption of cooling, loss of water in the secondary cooling loop or loss of water in the primary coolant loop.

  1. Nuclear reactors sources of contamination - RA reactor in Vinca as an example; Nuklearni reaktori kao izvori kontaminacije - Primer reaktora RA u Vinci -

    Energy Technology Data Exchange (ETDEWEB)

    Mitrovic, S; Djukic, Z; Dobrosavljevic, N [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-03-15

    This study contains an analysis of possible contamination caused by reactor accidents. In addition to description of maximum credible accident impacts on the environment it covers the prevention and procedures to be undertaken in case of accident. The RA reactor was taken as an example. Since the probability of maximum credible accident is very low minor accident that could cause fission products release were analyzed. Analysis of the spent fuel storage pool at the RA reactor is included as well.

  2. Report of the Service for maintenance of electric equipment Service - Annex 3; Prilog 3 - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1975. godini

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  3. The analysis of the RA reactor irradiated fuel cooling in the spent fuel pool; Analiza hladjenja ozracenog goriva u bazenu za odlaganje reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Vrhovac, M; Afgan, N; Spasojevic, D; Jovic, V [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1985-07-01

    According to the RA reactor exploitation plan the great quantity of the irradiated spent fuel will be disposed in the reactor spent fuel pool after each reactor campaign which will including the present spent fuel inventory increase the residual power level in the pool and will soon cause the pool capacity shortage. To enable the analysis of the irradiated fuel cooling the pool and characteristic spent fuel canister temperature distribution at the residual power maximum was done. The results obtained under the various spent fuel cooling conditions in the pit indicate the normal spent fuel thermal load even in the most inconvenient cooling conditions. (author)

  4. Operation and maintenance of the RB reactor, Annual report for 1977; Pogon i odrzavanje reaktora RB, Izvestaj o radu u 1977. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Vranic, S [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1977-07-01

    The annual report for 1977 includes the following: utilization of the RB reactor; new regulations and instructions for reactor operation; improvement of experimental possibilities of the RB reactor; state of the reactor equipment; dosimetry and radiation protection; reactor staff. Five annexes are concerned with: testing the properties of preamplifiers for linear and logarithmic experimental channels; properties of the neutron converter; maintenance of the reactor equipment; purchase of new equipment; and the program for training reactor operators.

  5. Annex 1 - Task 08/12 final report, testing the RA reactor fuel element; Prilog 1 - Zavrsni izvestaj o podzadatku 08/12, Ispitivanje gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Mihajlovic, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Testing of the RA reactor fuel element is presented in Annex 2 and 3 of this report. Annex 2 describes the construction of individual parts of the fuel elements and the results of the chemical analyses. Annex 3 shows the microstructure of uranium in the fuel element.

  6. Operation and maintenance of the RA reactor in 1964, I-II, Part II; Pogon i odrzavanje reaktora RA u 1964. godini, I-II, II Deo

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    This volume of the report contains the following 15 Annexes: Improvement of the fuel cycle economy (record No. 37009803 in INIS DB); Analysis of neutron flux increase in horizontal experimental channels of the RA reactor record No. 37005698 in INIS DB); Application of the critical system for determining the thermal neutron flux in a research reactor with central horizontal reflector ( record No. 37055005 in INIS DB); Determining the capacity of the RA reactor heat exchanger dependent on the coolant water temperature and flow; Operation of the RA reactor in forced regime; Analysis of the CEN-132 heavy water pumps failures at the RA reactor from decontamination till present; Modifications in the vacuum loop of the distillation system; Report on decontamination of the evaporator and cleaning of the condenser of the distillation system; Operation of reactor at nominal power with reduced D{sub 2}O circulation; Cooling of the RA reactor with reduced flow rate in the heavy water loop; Measurement of the heavy water level in the fuel channels of the RA reactor; Conclusions of the experts group of the RA reactor at the meeting held on November 2 and 3 1964; Conclusions of the experts group at the meeting held on November 23 1964; After heat and the cooling problem after RA reactor shut-down; Measurement of noise and vibrations on the Ra reactor heavy water system; Calculation and measurement of the uranium temperature during irradiation in the experimental channel in the reflector of the RA reactor; Temperature measurement of the reactor materials samples irradiated in the fuel channels of the RA reactor; Study of the modifications in the synchronous generators, heavy water pumps and condenser batteries of the RA reactor.

  7. Identification of mechanical vibrations in a PWR reactor using neutron noise signal analysis of the standard instrumentation; Identifikacija mehanichkih varijacija analizom signala shuma standardne neutronske instrumentacije PWR reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Kostic, Lj [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia); Runkel, J [Institut fuer Kerntechnik und Zerstoerungsfreie Pruefverfahren, Hannover (Germany)

    1988-07-01

    The neutron noise signals in a PWR power plant were analysed in terms of auto- and cross-power spectral densities, phases and coherences. Core barrel motion, fuel element vibrations and reactivity noise effect due to pressure variations have been monitored and analysed. (author)

  8. Calculation of physical and thermo hydro-dynamic parameters of a thermal research reactor; Prorachun fizichkih i toplotno hidro-dinamichkih parametara termichkog istrazhivachkog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Matausek, M; Spasojevic, D; Jovic, V; Marinkovic, N [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1988-07-01

    The paper presents initial activities on creating a design concept of a new thermal research reactor, which should be built according to the research and development program in the field of nuclear fuel cycle technologies. For one possible type of such a reactor basic design parameters are specified and some preliminary results of nuclear, thermal and hydrodynamic design calculations are given. (author)

  9. Perturbation method for experimental determination of neutron spatial distribution in the reactor cell; Metoda perturbacije za eksperimentalno odredjivanje prostorne raspodele neutrona u celiji reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Takac, S M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1972-07-01

    The method is based on perturbation of the reactor cell from a few up to few tens of percent. Measurements were performed for square lattice calls of zero power reactors ANNA, NORA and RB, with metal uranium and uranium oxide fuel elements, water, heavy water and graphite moderators. Character and functional dependence of perturbations were obtained from the experimental results. Zero perturbation was determined by extrapolation thus obtaining the real physical neutron flux distribution in the reactor cell. Simple diffusion theory for partial plate cell perturbation was developed for verification of the perturbation method. The results of these calculation proved that introducing the perturbation sample in the fuel results in flattening the thermal neutron density dependent on the amplitude of the applied perturbation. Extrapolation applied for perturbed distributions was found to be justified.

  10. RA reactor reactivity changes before refurbishment - Task 3.08/02; Zadatak 3.08/02 - Promene reaktivnosti reaktora RA do remonta

    Energy Technology Data Exchange (ETDEWEB)

    Dobrosavljevic, N; Strugar, P; Stamenkovic, S [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    From the the end of 1959, when the RA reactor started operation until January 1963 reactor was operated with the initial fuel batch of 56 fuel channels. After 310 MWd 68 fuel channels were added to the reactor core, and after further 357 MWd the core was filled up to the maximum of 88 fuel channels. Basic reactor parameters were systematically measured during two years of operation. This report covers the measurements concerned directly with the reactor operation: calibration of the control rods and their reactivity worths during operation, determining the total built-in reactivity excess and its change during burnup, determination of reactivity dependence on the temperature, xenon effect in the core.

  11. Regulations and instructions; Propisi i uputstva

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    Regulations and instructions for operating the RA reactor consist of the following chapters: general regulations with the fundamental RA reactor characteristics, operating regulations and instructions for the personnel on duty, regulations for accidental conditions, training program for the staff of the Laboratory for reactor operation. Propisi i uputstva za rad reaktora RA sadrze sledeca poglavlja: opsti deo sa kratkim opisom karakteristika reaktora RA, propisi za rad dezurnog osoblja, propisi za slucaj udesa, program obuke osoblja Laboratorije za eksploataciju reaktora RA.

  12. I-1 General; I-1 Opsti deo

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    General part of the regulations and instructions for operation of the RA reactor includes fundamental data about the reactor properties, biological shields, purpose of reactor operation, organizational scheme, rights and responsibilities of the head of laboratory, leaders of the working teams and all the staff of the laboratory for RA reactor exploitation. Opsti deo knjige propisa i uputstva za rad reaktora sadrzi osnovne podatke o reaktoru, biloskoj zastiti, nameni reaktora, prava i duznosti nacelnika, sefova smena i osoblja laboratorije za eksploataciju reaktora RA.

  13. Description of Radiation Sources Installed at the French Atomic Energy Commissariat; Description de sources de rayonnement installees au commissariat a l'energie atomique; Opisanie istochnikov oblucheniya, nakhodyashchikhsya v frantsuzskom komissariate po atomnoj ehnergii; Descripcion de las fuentes de radiaciones instaladas en el commissariat a l'energie

    Energy Technology Data Exchange (ETDEWEB)

    Leveque, P

    1960-07-15

    organicas, ya que el flujo epitermico y rapido provoca la activacion de la mayor parte de los productos sometidos a la irradiacion. A continuacion, el autor describe las instalaciones del Centro de Aplicaciones Atomicas de Lyon creado en las proximidades de dicha ciudad por un grupo de industriales. Este Centro, que segun esta previsto comenzara a funcionar en 1960, tendra un caracter semi-industrial (para comenzar, una fuente de cobalto-60 de 3 000 curies y mas adelante, otra de 40 000 curies) y permitira realizar operaciones de irradiacion de una manera continua. (author) [Russian] Prezhde vsego avtor daet opisanie chetyrekh ustanovok, nakhodyashchikhsya v yadernom issledovatel'skom tsentre v Sakleh. - Laboratornyj istochnik v 600 kyuri kobal'ta-60; ispol'zuemyj pribor yavlyaetsya prostym i bezopasnym, no ne daet vozmozhnosti izmenyat' potok gamma-luchej. - Pribor, sostoyashchij iz semi istochnikov kobal'ta-60 (samyj moshchnyj v 1000 kyuri), ustanovlennykh v betonnoj kamere; pnevmaticheski j pribor pozvolyaet ustanovit' odin ili neskol'ko neobkhodimykh istochnikov v rabochem polozhenii. - Kamera vmeshchaet 100 sterzhnej yadernogo goryuchego ot novogo reaktora EL3; chast' ehtoj kamery prisposoblena dlya okhlazhdeniya, chto pozvolit proizvodit' opyty nad konservatsiej pishchevykh produktov dejstviem oblucheniya. - Vertikal'nye kanaly reaktora EL 2, tak nazyvaemye ''okna khimika''; kogda ehti kanaly obernuty kadmievoj fol'goj, dostigaemyj potok gamma-luchej perekhodit so 100000 na 200000 rentgeno/chasov, no oni mogut sluzhit' tol'ko dlya oblucheniya organicheskikh materialov, tak kak imeetsya aktivatsiya bol'shej chasti obluchaemykh produktov pri pomoshchi bystrogo ehpitermicheskogo potoka. Zatem avtor daet opisanie pribora, ustanovlennogo v Lionskom tsentre po ispol'zovaniyu atomov, postroennogo okolo Liona gruppoj promyshlennikov. EHtot pribor, pusk v ehkspluatatsiyu kotorogo predusmotren na nachalo 1960 goda, budet nosit' polupromyshlennyj kharakter (istochnik kobal'ta-60

  14. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels. [Serbo-Croat] Ovo (prvo) poglavlje sadrzi sledece: Opis reaktora RA; semu organizacije rada i rukovodjenja; prava i duznosti direktora i rukovodioca pogona reaktora, propise o rezimu rada i kretanja u zgradi reaktora, propise o izvodjenju eksperimenata, propise o unosenju uzoraka u eksperimentalne kanale reaktora.

  15. Report of the Service for maintenance of mechanical structures - Annex 2; Prilog 2 - Rad sluzbe za odrzavanje masinske opreme

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This Annex 2 describes the organizational structure and activities of the Service for maintenance of the mechanical structures of the RA reactor, inspection and maintenance of of reactor components, workshop and storage of spare parts at the reactor. Mechanical structures of the RA reactor included are: heavy water system, gas systems, technical water system, reactor core, and transportation equipment. [Serbo-Croat] Pored opisa organizacije rada sluzbe za odrzavanje masinske opreme reaktora RA, ovaj prilog sadrzi: podatke o stanju, reviziji i remontu masinske opreme reaktora RA, prirucne radionice i magacina. Masinska oprema reaktora RA obuhvata: sistem teske vode, gasne sisteme, sistem tehnicke vode, centralno telo reaktora, transportnu opremu.

  16. The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant; Systeme de Controle des Matieres Nucleaires Brutes et Speciales a l'Usine de Traitement D'Eurochemic; Sistema kontrolya nad iskhodnym i spetsial'nym yadernym materialom na zavode evrokhimicheskoj kompanii po regeneratsii yadernogo topliva; Control de Materiales Nucleares Basicos y de Materiales Fisionables Especiales en la Planta de Regeneracion de la Eurochemic

    Energy Technology Data Exchange (ETDEWEB)

    Frenzel, W.; Schueller, W. [EUROCHEMIC, MOL (Belgium)

    1966-02-15

    Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author) [French] La societe Eurochemic fait actuellement construire une usine de traitement chimique pres de Mol (Belgique). L'auteur indique succinctement les principales caracteristiques de l'usine et les differentes etapes du traitement. Pour assurer un controle correct des matieres nucleaires brutes et speciales, les installations d'Eurochemic sont divisees en secteurs de mesures. Tous les transferts entre ces secteurs de mesure sont determines quantitativement. Les mesures sont faites avec des degres de precision differents qui ont ete fixes en fonction de leur importance pour le bilan matieres general; les auteurs examinent brievement les criteres appliques a cette fin. Pour verifier le bilan, on procede periodiquement a des inventaires materiels. La facon dont sont menes ces inventaires est exposee dans ses grandes lignes. Les auteurs indiquent les livres utilises pour la comptabilite des matieres nucleaires et resument les principes du systeme comptable. (author) [Spanish] La compania Eurochemic esta construyendo una planta de regeneracion en Mol (Belgica). Los autores resumen las principales caracteristicas de la instalacion, y las distintas fases del proceso industrial. Para mantener un control adecuado de los materiales nucleares basicos y de los materiales fisionables especiales, las instalaciones de la compaliia estaran divididas en diversas zonas de balance de materiales. Toda entrada y salida de materiales de estas zonas quedara registrada. Teniendo en cuenta su importancia en relacion con el balance global de materiales, se han fijado distintos requisitos en materia de precision basados en una escala de valores que los autores describen brevemente. Periodicamente se efectuaran inventarios de material a fin de proceder al balance de asientos. Se exponen los correspondientes procedimientos de inventario. Los autores describen los libros utilizados en la contabilidad de los materiales nucleares y enuncian los principios en que se basa el sistema de contabilidad. (author) [Russian] Kompanija Evrohimik v nastojashhee vremja stroit zavod po pererabotke jadernogo topliva okolo Molja (Bel'gija). Summirujutsja glavnye harakteristiki zavoda i razlichnyh stadij obrabotki. Dlja provedenija nadlezhashhego kontrolja nad ishodnym i special'nym jadernym materialom ustanovki kompanii razdeleny na zony material'nogo balansa. Opredeljajutsja vse peremeshhenija v jeti zony i iz nih. B zavisimosti ot vazhnosti jetih materialov dlja obshhego material'nogo balansa ustanovleny razlichnye trebovanija v otnoshenii tochnosti v sootvetstvii so shkaloj vazhnosti, kotoraja kratko opisyvaetsja. Dlja pravil'nogo sostavlenija zhurnal'nogo balansa periodicheski provodjatsja fizicheskie inventarizacii. Izlagajutsja sootvetstvujushhie metody inventarizacii. Daetsja kratkoe opisanie zhurnalov ucheta jadernyh materialov i principov sistemy u cheta. (author)

  17. Reactor Radiation Loops as Large Gamma Sources; Boucles d'irradiation des reacteurs nucleaires utilisees comme sources gamma intenses; Radiatsionnye kontury yadernykh reaktorov kak moshchnye gamma-istochniki; Empleo de circuitos de irradiacion de los reactores como fuentes gamma de gran intensidad

    Energy Technology Data Exchange (ETDEWEB)

    Ryabukhina, Yu. S.

    1963-11-15

    vybrany kontury na zhidkikh pri komnatnoj temperature splavakh indiya. Bylo izucheno povedenie dvukh ehvtekticheskikh splavov indiya po otnosheniyu k nekotorym konstruktivnym materialam, i v nachale 1960 g. byl zapushchen pervyj stendovyj indij-gallievyj kontur. V rezul'tate dal'nejshikh rabot byli zapushcheny model'nyj indij-galdievyj kontur s aktivnost'yu v obluchatele do {approx} 100 g. eh k v radiya pri reaktore IRT AN Gruzinskoj SSR i stendovyj indij-gallij-olovyannyj kontur v kanale reaktora IRT IAEH AN SSSR. Nakonets, v 1962 g. byl zapushen rabochij indij-gallij-olovyannyj kontur pri reaktore IRT AN Latvijskoj SSR dlya provedeniya polupromyshlennykh radiatsionnykh protsessov. Maksimal'naya aktivnost' obluchatelya kontura 30 000 g. eh k v radiya. Doklad sostoit iz 4 razdelov: 1. Raschety radiatsionnykh konturov. Obobshchaetsya prodelannaya rabota po metodam rascheta radiatsionnykh konturov. 2. Model' radiatsionnogo indij-gallievogo kontura reaktora IRT-2000 v Tbilisi. Opisyvaetsya dejstvuyushchij kontur. 3. Indij-gallij-olovyannyj radiatsionnyj kontur yadernogo reaktora IRT AN Latvijskoj SSR. Opisyvaetsya dejstvuyushchij kontur. 4. Perspektivy dal'nejshego razvitiya radiatsionnykh konturov. Opisyvayutsya ehksperimenty, skhemy i privodyatsya raschety, na osnovanii kotorykh predstavlyaetsya vozmozhnym sozdanie konturov na tverdom margantse i mobil'nykh konturov na zhidkikh splavakh indiya. (author)

  18. Tasks related to increase of RA reactor exploitation and experimental potential, 02. Verification of the system for detecting failures of the RA reactor fuel element cladding; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 02. Provera sistema za detekciju pucanja kosuljice gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    For the purpose of this task it was necessary to analyze the time dependent distribution of fission products in the fuel element and leaks through the cracks in the cladding; to calculate the quantity of solid fission products, volatile fission products and fission gases for the RA reactor; to collect the data for estimating the activity of the short-living isotopes created by neutron irradiation of D{sub 2}O; analyze the number of delayed neutrons in D{sub 2}O. Experiment were needed to estimate the distribution of Xe and Kr in the heavy water in the reactor channel and analyze the activity of D{sub 2}O and helium based on reactor operation data. For the purpose of verifying the efficiency and safety of the existing system for detecting the cracks of the fuel element cladding is presented in this report together with the review of similar systems at a number of reactors in the world.

  19. Measuring set: Reactor Power Meter (type of SG-8), Reactor Energy Meter (type of SG-11) and Digital Dose Meter (type of SG-9) for reactor rigs operation. Zestaw pomiarowy: miernik mocy reaktora (typ SG-8), miernik energii reaktora (typ SG-11) oraz cyfrowy miernik dawki (typ SG-9) dla potrzeb eksploatacji sond reaktorowych

    Energy Technology Data Exchange (ETDEWEB)

    Glowacki, S W

    1982-01-01

    A measuring set consisting of the Reactor Power Meter, Reactor Energy Meter and Digital Dose Meter is described. The gamma radiation of water in the reactor primary cooling circuit reaches the ionisation chamber and involves the output current, driving the Reactor Power Meter and Reactor Energy Meter. The Digital Dose Meter is controlled by the output current of the self-powered detector mounted inside the reactor rig.

  20. Tasks related to increase of RA reactor exploitation and experimental potential, 01. Designing the protection chamber in the RA reactor hall for handling the radioactive experimental equipment (I-II) Part II, Vol. II; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 01. Projektovanje zastitne komore u hali reaktora RA za rad sa aktivnim eksperimentalnim uredjajima (I-II), II Deo, Album II

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    This second volume of the project for construction of the protection chamber in the RA reactor hall for handling the radioactive devices includes the technical description of the chamber, calculation of the shielding wall thickness, bottom lead plate, horizontal stability of the chamber, cost estimation, and the engineering drawings.

  1. Tasks related to increase of RA reactor exploitation and experimental potential, 03. Crane for handling the vertical experimental channels of the RA reactor - design project; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 03. Kran za opsluzivanje vertikalnih eksperimentalnih kanala reaktora RA - izrada projekta

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    Within the work related to improvement of experimental potential of the RA reactor, this document describes the design project of the new crane for handling the vertical experimental channels of the RA reactor, engineering drawings of the crane main elements, mechanical part, design project of the electrical part of the crane and cost estimation.

  2. Tasks related to increase of RA reactor exploitation and experimental potential, 04. Device for transport of radioactive reactor channels and semi channels of the RA reactor, design project (I-III) Part II, Vol. II; Radovi na povecanju eksploatacionih i eksperimentalnih mogucnosti reaktora RA, 04. Uredjaj za transport aktivnih tehnoloskih kanala I semikanala reaktora RA - izrada projekta (I-III), II Deo, Album II

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    This second volume includes calculations of the main components of the transporter, description of the mechanical part of the transporter and the engineering drawing of the device for transport of radioactive reactor channels and semi channels of the RA reactor.

  3. ANALISIS PERMIBILITAS KERUANGAN DAN DINAMIKA FLUIDA ANGIN DAN SUHU KAWASAN PERMUKIMAN TROPIS SUNGAI DI BANJARMASIN, INDONESIA (An Analysis on Spatial Permeability and Fluid Dynamics of Wind and Thermal in Tropical Riverside Residential Areas

    Directory of Open Access Journals (Sweden)

    Budi Prayitno

    2013-07-01

    Full Text Available ABSTRAK Permukiman tepian sungai di Banjarmasin secara alami merupakan permukiman berbasis pada alam dan budaya huni sungai, saat ini mengalami degradasi kualitas kehidupan dan alamnya. Hal ini diakibatkan oleh bencana kebakaran, banjir dan tinggi resiko terjadinya urban heat island. Secara konfigurasi keruangan tidak terjadi hubungan dan keterpaduan antara ruang arsitektur dan infrastruktur kawasan yang berbasis daratan dan perairan. Fenomena yang terjadi adalah kepadatan, hubungan kawasan darat dan sungai yang lemah serta degradasi kualitas lingkungan. Selain itu kenyamanan termal kawasan pun sangat rendah, yaitu: aliran angin yang tidak lancar, kelembaban cukup tinggi dan suhu yang tidak nyaman. Penelitian ini mencoba melakukan eksperimen melalui pendekatan simulasi permibilitas ruang dan kenyamanan termal dengan menggunakan metode analisis ruang dengan program Space Syntax dan metode analisis kenyamanan termal dengan program Envimet. Penelitian ini membandingkan kondisi eksisiting dan usulan model arsitektur permukiman kampung beringkat yang berbasis arsitektur permukiman vernakular tepi sungai Banjarmasin. Kesimpulan dari penelitian ini adalah melalui pendekatan permibilitas keruangan yang mensimbiosiskan konfigurasi antara ruang darat dan air serta arsitektur kawasan dapat ditingkatkan kinerja kejelasan keruangannya tetapi secara kenyamanan termal tidak menunjukkan peningkatan kinerja secara signifikan karena morfologi kawasan yang relatif datar dan dengan proporsi ketinggian rata-rata bangunan yang rendah sehingga tidak terbentuk jalur pergerakan angin sebagai sarana ventilasi dan kenyamanan termal kawasan. ABSTRACT Riverside settlements in Banjarmasin that were initially based on their river culture and nature are currently experiencing degradation of life quality and nature. This is caused by fires, floods, and a high risk of urban heat island. In terms of spatial configuration there are no interrelation and integration between regional architecture and infrastructure, which are based on land and water. Problems occurring in these areas are density, less interconnectivity, poor accessibility, and very low intelligibility. In addition, the areas’ thermal comfort is very low – poor wind circulation, high humidity, and uncomfortable temperatures. In the study the researcher conducted an experiment based on permeability approach to solve the challenges and problems related to spatial and thermal comfort by using a spatial analysis method, space syntax, and a thermal comfort analysis method, Envimet. This study compared the existing condition with a model architecture of a city block kampung settlement, which was based on local vernacular architecture of Banjarmasin river banks. The research concluded that the intelligibility performance of spatial permeability approach could be improved. This approach resulted in a symbiosis between spatial configuration of land and water and the regional architecture. However, in terms of thermal comfort no significant improvement of performance occurred because the morphology of the area was relatively flat and the proportion of the average height of buildings was low. Consequently, wind path as ventilation was not formed and area thermal comfort was not created.

  4. Letna Dinamika Pojavljanja Vodnih Ptic Na Reki Dravi Med Mariborskim Jezerom In Jezom Melje (Sv Slovenija / Yearly dynamics of waterbirds’ occurrence on the Drava River between Lake Maribor and Melje Dam (NE Slovenia

    Directory of Open Access Journals (Sweden)

    Logar Katja

    2014-11-01

    Full Text Available Between April 2007 and April 2008, 40 systematic waterbird counts were conducted on the Drava River between Lake Maribor and the Melje Dam (length 8.5 km, area 155 ha to determine the specific composition, abundance and seasonal dynamics of bird occurrence. Between October and May, counts were conducted every week, whereas between June and September they were carried out once every two weeks. In total, 26,803 individuals of 30 species were counted. The number of waterbirds and diversity of species were the highest from late December to late February, when more than 1,000 individuals were regularly present in the area. Waterbirds were distributed along the river unequally, with the highest number of birds present yearround in the city centre and in the first counting sector of Lake Maribor. The Mallard Anas platyrhynchos and Mute Swan Cygnus olor were recorded during every count, while occurrence frequency was greater than 50% in another 10 species. Dominant species in terms of percentage composition were Mallard, Black-headed Gull Chroicocephalus ridibundus, Coot Fulica atra, Mute Swan, Pochard Aythya ferina and Tufted Duck Ay. fuligula. Mute Swan and Mallard were the only breeding waterbirds in the study area. Both the total number of waterbirds and the highest daily total in the first two counting sectors were greater between October and March 1992/93 than in our study. The decline in numbers was the greatest for Mallard, Pochard and Tufted Duck, while an increase was noted in Mute Swan and Yellow-legged / Caspian Gull Larus michahellis / cachinnans. The total number of waterbirds and the number of some species in the study area were significantly higher than expected solely based on its length compared to the length of the lowland Drava in Slovenia (125.7 km. The study area is conservationally important for Pochard, Tufted Duck and Black-headed Gull

  5. Measurements of neutron flux in the RA reactor; Merenje karakteristika neutronskog fluksa u reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This report includes the following separate parts: Thermal neutron flux in the experimental channels od RA reactor; Epithermal neutron flux in the experimental channels od RA reactor; Fast neutron flux in the experimental channels od RA reactor; Thermal neutron flux in the thermal column and biological experimental channel; Neutronic measurements in the RA reactor cell; Temperature reactivity coefficient of the RA reactor; design of the device for measuring the activity of wire. [Serbo-Croat] Ovaj izvestaj sadrzi sledece referate: Fluks termalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks epitermalnih neutrona u eksperimentalnim kanalima reaktora RA; Fluks brzih neutrona u eksperimentalnim kanalima reaktora RA; Fluks termalnih neurona u termalnoj koloni i bioloskom eksperimentalnom kanalu; Neutronska merenja u elementarnoj celiji reaktora RA; Temperaturni koeficijent reaktivnosti reaktora RA; Projekat uredjaja za merenje radioaktivnosti zice.

  6. Thermal Shock Tests on UO{sub 2} Small Spheres; Essais de choc thermique sur des elements spheriques de UO{sub 2}; Ispytaniya nebol'shikh sharikov iz UO{sub 2} teplovykh udarom; Ensayo de pequenas esferas de UO{sub 2} por choque.termico

    Energy Technology Data Exchange (ETDEWEB)

    Perona, G.; Brutto, E.; Galbusera, U.; Palladino, G.; Sesini, R. [Centro Informazioni Studi Esperienze, Milan (Italy)

    1963-11-15

    exponen los resultados obtenidos. La aplicacion de este metodo presenta, al parecer, considerable interes, sobre todo en lo que concierne a las investigaciones encaminadas a mejorar las caracteristicas de las esferas de UO{sub 2} por medio de aditivos. En e fecto, permite verificar el efecto global con una sola medicion. (author) [Russian] Ispol'zuya malye pariki iz UO{sub 2} v kachestve yadernogo topliva v reaktore, gde oni nakhodyatsya v soprikosnovenii s teplonositelem, neobkhodimo znat' maksimal'nuyu pri rabochem rezhime reaktora velichinu termicheskikh napryazhenij, kotorye mogut vyderzhivat' bez povrezhdeniya ehti shariki. Esli izvestny fizicheskie svojstva materiala, to mozhno rasschitat' ehti napryazheniya pri rabochem rezhime. Odnako vvidu mnogochislennosti podlezhashchikh uchetu faktorov i neizbezhnoj doli neopredelennosti kazhdogo iz nikh predstavlyaetsya predpochtitel'nym provesti neposredstvennye ispytaniya ehtikh sharikov, podvergnuv ikh tem zhe napryazheniyam, kakie oni ispytyvayut v reaktore. V nastoyashchej rabote byl izuchen metod teplovogo udara v primenenii k malym sharikam i ukazyvayutsya usloviya, pri kotorykh ehtot metod pozvolyaet proizvesti napryazheniya, neposredstvenno sravnimye s temi, kotorye sushchestvuyut v reaktore. V sluchae malykh sharikov zatrudnenie zaklyuchaetsya v osushchestvlenii okhlazhdeniya, pozvolyayushchego dostigat' ochen' bol'shikh znachenij koehffitsienta poverkhnostnoj teploperedachi. Opisyvayutsya ehksperimental'nye metody i soobshchayutsya poluchennye rezul'taty. Primenenie ehtogo' metoda, po-vidimomu., predstavlyaet bol'shoj interes, v osobennosti v oblasti tekhnologicheskikh izyskanij s tsel'yu uluchsheniya svojstv malykh sharikov iz UO{sub 2} putem vklyucheniya dobavochnykh komponentov. Fakticheski,ehtot metod daet vozmozhnost' pri pomoshchi odnogo tol'ko izmereniya kontrolirovat' izuchaemoe vozdejstvie. (author)

  7. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  8. RA Reactor operation and maintenance (I-IX), Part III, Task 3.08/04-02 Refurbishment of the electrical equipment; Pogon i odrzavanje reaktora RA (I-IX), III Deo, Zadatak 3.08/04-02 Remont elektro opreme

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M; Poznanovic, B; Rajic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    This volume contains detailed action plan for repair of electrical equipment of the RA reactor, the list of electrical equipment parts which were either repaired or exchanged for improvement of their performance. Detailed work describing the repair and maintenance work done of the listed equipment is part of this report. Equipment related to dosimetry and control systems are included as well.

  9. Control of the working environment dosimetry and technical radiation protection at the RA reactor, Part I; Deo I: Kontrola radne sredine - poslovi dozimetrije i tehnicke zastite od zracenja kod reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, N; Bjelanovic, J; Minicic, Z; Komatina, R; Raicevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    This report contains data and analysis of the of measured sample results collected during radiation protection control in the working environment of the RA reactor. First part contains basic exposure values and statistical review of the the total number of radiation measurements. It includes contents of radioactive gasses and effluents in the air, as well as the level of surface contamination of clothes and uncovered parts of the personnel bodies. Second part deals with the analysis of personnel doses. It was found that the maximum individual dose from external irradiation amounted to 16.9 mSV during past 10 months. Individual exposures for 9/10 of the personnel were less than 1/10 of the permissible annual exposure. Data are compared to radiation doses for last year and previous five years. Third part of this annex contains basic data about the quantity of collected radioactive waste, total quantity of contaminated and decontaminated surfaces. The last part analyzes accidents occurred at the reactor during 1984. It was found that there have been no accidents that could cause significant contamination of working surfaces and components nor radiation exposure of the personnel.

  10. RA Research nuclear reactor, Part II - radiation protection at the RA nuclear reactor in 1984; Istrazivacki nuklearni reaktor RA - Deo II - zastita od zracenja kod nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Ajdacic, N; Zaric, M; Vukovic, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    Radon protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each category is described as a separate annex of this report.

  11. RA Reactor operation and maintenance (I-IX), Part II, Task 3.08/04; Pogon i odrzavanje reaktora RA (I-IX), II Deo, Zadatak 3.08/04

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Repair and maintenance work of the RA reactor components and equipment was longer than planned due to the following reasons: chemical decontamination of the reactor heavy water system indispensable for maintenance of the heavy water pumps; findings of contamination origin changed the maintenance schedule; some construction materials of the heavy water pumps which caused contamination had to be removed; a number of the planned operations had to be performed under increase level of gamma radiation which increased the time needed for repair. This report covers detailed description of all the maintenance and repair work done from 25 Jan to 22 Apr 1963.

  12. Graphical method for determination of critical dimensions and neutron flux distribution in multi zone nuclear reactors; Graficka metoda za odredjivanje kriticnih dimenzija i raspodele fluksa kod multiregionalnih nuklearnih reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Radanovic, Lj; Bingulac, S; Lazarevic, B; Matausek, M [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    This paper describes the graphical method for calculating the neutron flux distribution by using normalized Riccati equations. It was shown that the solutions of adequately normalized Riccati equations could be used as standard curves for determining the critical dimensions and radial flux distribution in multi zone nuclear reactors. the methos is applicable irrelevant of the number and position of the region in the core.

  13. Operation and maintenance of the RA reactor, Report on operation in 1966, task 6.08; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1966. god. Zadatak 6.08

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D and others [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-12-15

    During 1966, RA reactor was operated at nominal power for 196 days and 28 days at lower power levels. The total production was 31015 MWh which is 3% higher than planned. Practically there were no discrepancies from the plan. The reactor was used for irradiation and experiments according to the demand of 644 users, of which 516 were from the Institute. This report contains detailed data about reactor power and experiments performed in 1966, and a chart showing discrepancies from the plan. data concerned about the utilization of reactor experimental channels are included as well. Total number of safety shutdowns was 37, of which 20 were caused by power cuts, 10 due to voltage instabilities, 4 due to human error and 3 due to failures of instrumentation. These data are compared to safety shutdown data of previous few years. There have been no accidents which could cause any significant effects. The incidents occurred during this year are described in detail. Detailed data concerning exposure of the personnel are part of this report.

  14. Operation and maintenance of the RA reactor, Report on operation in 1967, task 7.08; Pogon i odrzavanje reaktora RA, Izvestaj o radu u 1967. god. Zadtak 7.08

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D and others [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1967-12-15

    During 1967, RA reactor was operated at nominal power for 190 days and 23 days at lower power levels. The total production was 31060 MWh. Report contains data until Dec. 22. 1967, but the reactor was planned to operate three more full days at nominal power of 6.5 MW, meaning that the total number of operation at full power would be 193 days ant the total production would be 30625 which is 2% higher than planned. Practically there were no discrepancies from the plan. There have been 5 shorter interruptions in operation caused by demand of the experiment, minor repairs and thunderstorm. Only one longer interruption was caused by difficulties in secondary water supply. The reactor was used for irradiation and experiments according to the demand of 590 users, of which 470 were from the Institute. This report contains detailed data about reactor power and experiments performed in 1967, and a chart showing discrepancies from the plan. Data concerned about the utilization of reactor experimental channels are included as well. Total number of safety shutdowns was 19, of which 11 were caused by power cuts, 6 due to voltage instabilities, and 2 due to failures of instrumentation. These data are compared to safety shutdown data from 1962 - 1967. There have been no accidents which could cause any significant effects. The only important incident occurred this year was caused by leaking of sulphur from an experimental capsule. It is described in detail. Detailed data concerning exposure of the personnel are part of this report. In spite of the fact that this year the spent fuel was for the first time packed and mixing of the fuel in the core there have been no unplanned difficulties nor contaminations.

  15. From a critical assembly heavy water - natural uranium to the fast - thermal research reactor in the Institute Vinca; Od kriticnog sistema teska voda - prirodni uranium do brzo - termickog istrazivackog reaktora u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, D; Pesic, M [Vinca Institute of Nuclear Sciences, Beograd (Yugoslavia)

    1995-07-01

    A part of the Institute in Vinca this monograph refers to is the thermal nuclear zero power reactor RB, with a heavy water moderator and variously enriched uranium fuel, that is, its present day version, the coupled fast-thermal system HERBE. A group of research workers, technicians, operators and skilled workmen in the workshop have worked continuously on it. Some of them have spent their whole working age at the reactor, and some a part of it. There is about a hundred and fifty internationally published papers, twenty master's and fourteen doctor's theses left behind them for the past thirty five years. This book is devoted to them. The first part of the text refers to the pioneering efforts on the reactor and fundamental research in reactor physics. The experimental reactor RB was designed and constructed at the time to operate with natural uranium and heavy water. Measurements are presented and the first results of reaching critical state, measurements of migration length of thermal neutrons and neutron multiplication factor in an infinite medium; also measurements of neutron flux density distribution and reactor parameter, and in the domain of safety, measurement of safety rods reactivity. Those were also the times when the known serious accident occurred with the uncontrolled rise of reactivity, which was especially minutely described in a publication of the International Atomic Energy Agency from Vienna. Later on, new fuel was acquired with 2 % enriched uranium. A series of experiments in reactor and neutron physics followed, with just the most interesting results of them presented here. In the period which followed, another type of fuel was available, with 80 % enriched uranium. New possibilities for work opened. Measurements with mixed lattices were performed, and the RA reactor lattices were simulated. After measurements mainly in the sphere of reactor and neutron physics, a need for investigations in the field of gamma and neutron radiation protection arose. While the RB reactor system was purely thermal with a variable neutron reflector, possibilities for this kind of research were comparatively limited. However, these possibilities were greatly increased by system configurations which had neutron converters built into them, and which created significant and spacious fast neutron fields suitable for various experiments. In the beginning of the eighties at the Institute in Vinca, designing and construction of a fast zero power reactor called LASTA began. The design was completed, location for it examined and arranged. In a mid-phase, even the main design of a subcritical system called MALA LASTA was also elaborated. RB reactor has its role in these designs, which consisted mostly of creation of neutron fields similar to the energy spectrum like the one in the LAST A, intended for basic measurements and acquiring of experimental experience for future experiments. In order to fulfil this task, a hybrid coupled fast-thermal system HERBE was completed, which will, in view of its significance, be devoted a part of this monograph. Reactor RB began its operation as part of the Laboratory for Physics and Dynamics of the Reactor. It was also a Basic Organization of Associated Labour, and now the Nuclear Engineering Laboratory developed around it. All the important data on this several-decades long work are presented in this monograph. (author)

  16. Determination of fine neutron flux distribution in multi-region reactor cell by applying spherical harmonics method; Odredjivanje fine rspodele fluksa u viseregionalnoj celiji reaktora primenom metode sfernih harmonika

    Energy Technology Data Exchange (ETDEWEB)

    Jockovic, M; Stefanovic, D; Barucija, M [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1964-07-01

    Neutron distribution in space, direction of movement, energy and time is described by Boltzmann equation. This paper describes the adaptation of method for calculating the neutron flux distribution in P{sub 3} approximation and the computer code written for the ZUSE-Z-23 computer. Some results for a few typical reactor cells are included. The number of regions in the reactor cell treated by the code is limited only by the capacity of the computer.

  17. Calculation of the fine neutron flux distribution in the multi-zone reactor cell by spherical harmonics method; Odredjivanje fine raspodele fluksa u viseregionalnoj celiji reaktora primenom metode sfernih harmonika

    Energy Technology Data Exchange (ETDEWEB)

    Jockovic, M; Stefanovic, D; Barucija, M [The Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-07-01

    This presentation contains development and application of method for calculating the neutron flux distribution by P{sub 3} approximation. A computer codes was developed for the ZUSE-Z-23 computer. Some typical results are included.

  18. Activity of the Service for maintenance of RA reactor electrical equipment in 1976, report - Annex III; Prilog III - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1976. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada Sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  19. Dosimetry and technical radiation protection at the RA Reactor - Report for 1977, Annex V; Prilog V - Dozimetrija i tehnicka zastita od zracenja kod reaktora RA - Izvestaj za 1977. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1977-12-15

    This report includes data about the level of gamma and neutron radiation, and level of contamination in the working environment at the RA reactor, data about collective and individual exposure of the staff to radiation, data about contamination and decontamination as well as radioactive waste. During 1977, at the RA reactor there was no accident that would cause significant exposure of tf the staff or contamination of the working space and the environment of the reactor. [Serbo-Croat] Ovaj Izvestaj sadrzi podatke o nivou gama i neutronskog zracenja i stepenu kontaminacije radne sredine, podatke o individualnom i kolektivnom izlaganju zracenju radnog osoblja, podatke o kontaminaciji i dekontaminaciji kao i o radioaktivnom otpadu. U toku 1977. godine, na reaktoru RA nije bilo akcidenata vecih razmera koji bi za posledice imali znacajnije ozracivanje radnog osoblja i kontaminaciju radne sredine i okoline.

  20. Activity of the Service for maintenance of RA reactor electrical equipment in 1978, report - Annex III; Prilog III - Rad sluzbe za odrzavanje elektro opreme reaktora RA u 1978. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Stamenkovic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-12-15

    This report describes organisational structure of the Service dealing with control and maintenance of electrical supply system and equipment. It includes detailed data about electric power consumption, power cuts and failures during the past period. [Serbo-Croat] Ovaj izvestaj opisuje organizaciju rada Sluzbe za kontrolu i odrzavanje elektro-opreme i sadrzi detaljne podatke o potrosnji elektricne energije, smetnjama u napajanju elektricnom energijom, kvarovima u proteklom periodu.

  1. Monte Carlo estimation of the influence of elastic scattering anisotropy on the neutron flux in a nuclear reactor cell; Monte Carlo procena uticaja anizotropije elasticnog rasejanja na vrednost neutronskog fluksa u celiji nuklearnog reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Kocic, A [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1974-07-01

    Anisotropy of neutron elastic scattering is a problem of special importance in solving the Boltzmann transport equation numerically. This is not the case when Monte Carlo method is applied. Estimation of the influence of elastic scattering anisotropy on the neutron flux is treated in order to justify the application of Monte Carlo method which is computer time consuming. Correlation procedure was applied for the study of this influence. One group case was used as an example to enable comparison of other methods.

  2. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1984; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    During the 1984 the reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981. Operation of the primary cooling system was changed in order to avoid appearance of the previously noticed aluminium oxyhydrate on the surface of the fuel element claddings. The new cooling regime enabled more efficient heavy water purification. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks are planned: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. Financing of the planned activities will be partly covered by the IAEA. this Part I of the report includes 8 Annexes describing in detail the reactor operation, and 6 special papers dealing with the problems of reactor operation and utilization.

  3. Annex 7 - Task 08/32 final report, Diffusion bond between the fuel and cladding of the RA reactor fuel element; Prilog 7 - Zavrsni izvestaj o podzadatku 08/32, Difuziona veza goriva i kosuljice gorivnog elementa reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Kustudic, D [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Based on testing the diffusin bond between the fuel and the aluminium cladding of the RA reactor fuel element it was found that the diffusion bond exists; uranium is protected by a nickel layer to prevent the damaging diffusion between uranium and aluminium; the nickel layer is about 5 microns thick. Under assumption that the diffusion annealing was done after cladding the annealing temperature was about 500 deg C for about 1 hour.

  4. Measurement of thermal neutron spectrum by chopper at the RA reactor in the 'Boris Kidric' Institute; Merenje termickog neutronskog spektra iz reaktora RA u Institutu 'Boris Kidric' pomocu copera

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-04-15

    Measurement of neutron spectrum described in this paper is one of the first measurements of neutron energy distribution at the reactor by time-of-flight method performed in our Institute. Measurement was done by applying the mechanical spectrometer (chopper) designed and constructed in 1961. Spectrometer was calibrated at the end of 1962.

  5. Study of reactor parameters of on critical systems, Phase I: Safety report for RB zero power reactor; Ispitivanje reaktorskih parametara na kriticnim sistemima, I faza: Izvestaj o sigurnosti reaktora nulte snage RB

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1962-09-15

    In addition to the safety analysis for the zero power RB reactor, this report contains a general description of the reactor, reactor components, auxiliary equipment and the reactor building. Reactor Rb has been reconstructed during 1961-1962 and supplied with new safety-control system as well as with a complete dosimetry instrumentation. Since RB reactor was constructed without shielding special attention is devoted to safety and protection of the staff performing experiments. Due to changed circumstances in the Institute ( start-up of the RA 7 MW power reactor) the role of the RB reactor was redefined.

  6. Study of the modifications on the synchronous generators, heavy water pumps and condenser batteries of the RA reactor - Annex 17; Prilog 17 - Elaborat o izmenama u semama sinhronih generatora, teskovodnih pumpi i kondenzatorskih baterija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Modifications done on the synchronous generators are related to the emergency power supply system, meaning one of the most important devices responsible for reactor safety. Without reducing the efficiency of the heavy water pumps the improved stability of generators operation was achieved by reducing the possibility of errors and simplifying manipulation. Condensator batteries were improved in order to decrease the leakage currents.

  7. Testing of the fuel element - radiation damage of the construction materials of the fuel element and reactor core; Ispitivanje gorivnog elementa - radijaciono ostecenje konstrukcionih materijala gorivnog elementa i jezgra reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    This report covers the following: review of present radiation damage testing of stainless steels and zircaloy-2 used in heavy water reactors; plan of experiments for irradiation of of these materials.

  8. Activities of the Service for maintenance of the RA reactor electronic equipment in 1979 - Report - Annex IV; Prilog IV Rad sluzbe za odrzavanje elektronske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1979-12-15

    Within the organizational structure of the RA reactor staff, the Service for instrumentation maintenance has the following tasks: maintenance of the existing electronic equipment; participating in experiments planning and preparation of electronic equipment; purchasing new equipment, spare parts and components; construction of new equipment for internal needs; implementation of new equipment. Basic instrumentation of the reactor facility includes: control and protection system, and dosimetry system. [Serbo-Croat] U okviru organizacione seme OOUR nuklearni reaktor RA sluzba za odrzavanje instrumentacije postrojenja ima sledece zadatke: odrzavanje postojece elektronske opreme; ucesce u planiranju eksperimenata i priprema elektronske opreme; nabavka nove opreme, rezervnih delova i komponenti; rad na izradi elektronske opreme i uredjaja za sopstvene potrebe i izrada projekata u domenu reaktorske opreme i ucesce u ugradnji nove opreme. Osnovna instrumentacija postrojenja obuhvata: sistem za upravljanje i zastitu, sistem za tehnolosku kontrolu i sistem za dozimetrijsku kontrolu.

  9. Theoretical analysis of nuclear reactors (Phase II), I-V, Part IV, Depletion of nuclear fuel; Razrada metoda teorijske analize nuklearnih reaktora (II faza) I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This phase of the project deals with the U{sup 238} isotope chain with the analysis of Pu{sup 239} build-up. Part one of the report shows two theoretical approaches, one leading to a system of differential equations which could be solved by using a computer, and the second Machinari-Goto method which gives analytical expressions for approximations for certain isotopes. Part two includes the results obtained by using digital computer ZUSE-Z22-R.

  10. Development of methods for theoretical analysis of nuclear reactors (Phase II), I-V, Part IV, Fuel depletion; Razrada metoda teorijske analize nuklearnih reaktora (II faza), I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-10-15

    This report includes the analysis of plutonium isotopes from U{sup 238} depletion chain. Two theoretical approaches for solving the depletion of fuel are shown. One results in the system of differential equations that can be solved only by using electronic calculators and the second, Machinari-Goto method enables obtaining analytical equations for approximative values of particular nuclei. In addition, differential equations are given for different approximation levels in calculating Pu {sup 239}, as well as relations between the released energy and irradiation. Ova faza obuhvata analizu stvaranja izotopa plutonijuma u lancu U{sup 238}. Prikazana su dva teorijska pristupa resavanju problema 'konverzije goriva', jedan dovodi do sistema diferecijalnih jednacina za cije je resavanje neophodno koriscenje elektronskih racunskih masina, i drugi, Machinari-Goto metod koji omogucava da se dobiju analiticki izrazi vrednosti aproksimacije pojedinih jezgara. Osim toga date su diferencijalne jednacine raznih stepena aproksimacije u racunanju Pu {sup 239}, kao i veze izmedju oslobodjene energije i ozracivanja.

  11. Mechanical neutron spectrometer Chopper - Experimental study of the neutron beam topography in the channel C of the 'A' reactor; Neutronski mehanicki spektrometar (coper) - Eksperimentalno odredjivanje topografije neutronskog snopa na kanalu 'C', reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, V [Institute of Nuclear Sciences Boris Kidric, Laboratorija za reaktorsku i neutronsku fiziku, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    The objective of the experiment was to measure the axis of the neutron beam from the reactor channel. The collimator, mechanical spectrometer and detectors are to be placed along this axis. Two points along the channel are determined to be defined as centres of the neutron beam. During this experiments the collimators were placed in the reactor at distance of 100 cm and cross section of 3.5 cm in diameter. BF{sub 3} detectors were used for the experiment.

  12. Theoretical analysis of nuclear reactors (Phase I), I-V, Part IV, Nuclear fuel depletion; Razrada metoda teorijske analize nuklearnih reaktora (I faza) I-V, IV Deo, Promena izotopnog sastava goriva

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-15

    Nuclear fuel depletion is analyzed in order to estimate the qualitative and quantitative fuel property changes during irradiation and the influence of changes on the reactivity during long-term reactor operation. The changes of fuel properties are described by changes of neutron absorption and fission cross sections. Part one of this report covers the economic significance of fuel burnup and the review of fuel isotopic changes during depletion. Pat two contains the analysis of the U{sup 235} chain, analytical expressions for the concentrations of U{sup 235}, U{sup 236} and Np{sup 237} as a function of burnup. Part three contains the analysis of neutron spectrum influence on the Westcott method for calculating the cross sections. Part four contains the calculation method applied on Calder Hall type reactor. The results were obtained by applying ZUSE-22 R digital computer.

  13. Application of Nuclear Radiation to Textile Materials and Processes. Radiation-induced graft copolymerization of vinyl monomers and fibrous polymers; Applications des rayonnements aux textiles. Formation radiochimique de copolymeres ''greffes'' par l'action de monomeres vinyliques sur des polymeres en fibre; Primenenie yadernogo izlucheniya v tekstil'noj promyshlennosti. Obrazovanie privitykh sopolimerov iz vinilovykh monomerov i voloknistykh polimerov pod dejstviem izlucheniya; Aplicaciones de las radiaciones nucleares a los procesos y materiales textiles. Copolimerizacion por injerto radioinducida de monomeros vinilicos y de polimeros fibrosos

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, Jr., A. A.; Rutherford, H. A. [University of North Carolina at Raleigh, NC (United States)

    1963-11-15

    A technique has been developed that permits the radiation grafting of volatile vinyl monomers to fibrous polymers in a uniform manner. It involves the addition of the organic compound from the vapour phase, and the process may be done by either a mutual or a pre-irradiation process using cobalt-60. Systems that accelerate the rate of graft copolymerization have been studied, and it is possible to add significant amounts of several of the monomers without radiation damage to the fibre substrate. The fibrous materials that are relatively unstable toward radiation are the ones that add the vinyl compounds the most readily. These are the celluloses, celluloseesters, polyamides, and polypropylene. The addition of the monomer to the fibre substrate apparently takes place by a free-radical mechanism and, as already indicated above, it is possible to irradiate the material first and subsequently obtain grafting by exposure of the irradiated material to the monomer vapour. Attempts have been made to determine the life of the free-radicals and while it has been difficult to obtain exact figures, it has been demonstrated that they may continue to exist in some fibres for15 to 20 hr after irradiation, even at room temperature. Preliminary experimental evidence has also suggested that the diffusion time of the monomer to free-radical sites in post-irradiation grafting proceeds at different rates in the different fibres. The modification of cotton by the addition of polyacrylonitrile results in a fibre almost completely resistant to micro-organisms. Only 3.5% deposition is required and the material retains the appearance and feel of untreated cotton. The product is superior to that made by the addition of acrylonitrile using the ironperoxide catalyst system. Polypropylene may be grafted with several different monomers to produce a fibre that is dyeable by commonly-used dyeing procedures. At the present stage of development, however, the wash fastness of the grafted and dyed materials is not good enough for commercial acceptance. The strength of cellulose acetate yam, as well as the modulus, can be materially increased by the addition of polyacrylonitrile. Other monomers do not behave in this manner. There is some indication that the fibre may be improved with one compound, especially with respect to its behaviour in the wet state. Fibre modification by the procedure described might be practical commercially if techniques that will increase the rate of diffusion of the monomer into the fibre structure can be developed. (author) [French] Les auteurs ont mis au point une methode qui permet de realiser par les rayonnements un greffage homogene de monomeres vinyliques volatils sur des polymeres en fibres. Elle consiste a ajouter le compose organique en phase vapeur; on procede, soit par irradiation de l'ensemble, soit par irradiation prealable des polymeres, aux rayons du cobalt-60. Les auteurs ont etudie des systemes qui accelerent la formation des copolymeres ''greffes''; ils ont constate qu'il est possible d'ajouter des quantites significatives de plusieurs des monomeres sans qu'il en resulte de dommages radioinduits dans le substrat fibreux. Les polymeres en fibres relativement instables en presence des rayonnements sont ceux qui fixent le plus facilement les composes vinyliques. C'est le cas des matieres cellulosiques, des esters de cellulose, des polyamides et du polypropylene. Le monomere s'ajoute au substrat fibreux par un mecanisme de radicaux libres, et, comme on l'a indique plus haut, on peut irradier d'abord les polymeres et ensuite provoquer le greffage par exposition de la matiere irradiee S la vapeur du monomere. On a tente de determiner la duree de vie des radicaux libres; il est difficile de donner des chiffres exacts, mais on a demontre qu'ils peuvent subsister dans certaines fibres 15 a 20 heures apres l'irradiation, meme a la temperature ambiante. Des resultats experimentaux preliminaires donnent egalement a penser que le temps de diffusion du monomere vers les sites des radicaux libres au cours du greffage apres irradiation prealable varie selon la nature des fibres. En traitant la fibre de coton par du polyacrylonitrile, on obtient une fibre ayant une resistance aux micro-organismes presque absolue. Un depot de 3,5% suffit et le tissu conserve l'apparence et la consistance de coton non traite. Ce produit est superieur a celui que l'on obtient par traitement a l'acrylonitrile en utilisant du peroxyde de fer comme catalyseur. Sur le polypropylene, on peut ''greffer'' plusieurs monomeres differents et obtenir une fibre susceptible d'etre teinte par les procedes courants. Mais en l'etat actuel des recherches, les tissus ainsi greffes et teints ne sont pas encore assez solides au lavage, pour une production industrielle. La resistance d'un fil d'acetate de cellulose ainsi que son module d'elasticite peuvent etre nettement augmentes par l'addition de polyacrylonitrile. D'autres monomeres ne se component pas de la meme facon. On a des raisons de penser que la fibre peut etre amelioree avec un certain compose, notamment en ce qui concerne sa resistance a l'etat humide. Les fibres modifiees par les procedes qui viennent d'etre decrits seraient susceptibles d'etre produites industriellement si l'on pouvait mettre au point des methodes permettant d'accelerer la diffusion du monomere dans la structure de la fibre. (author) [Spanish] Los autores describen un procedimiento nuevo que permite radioinjertar homogeneamente monomeros vinueicos volatiles en polimeros fibrosos. El proceso entrana la adicion del compuesto organico en la fase vapor, y puede llevarse a cabo de una manera simultanea o mediante una irradiacion previa, utilizando {sup 60}Co. Se han estudiado sistemas que aceleran la velocidad de copolimerizacion por injerto, y se ha comprobado que es posible adicionar cantidades significativas de varios monomeros sin que el substrato de la fibra resulte danado por la irradiacion. Los materiales fibrosos que son relativamente inestables frente a las radiaciones son los que con mayor facilidad adicionan los compuestos vinflicos. Esos materiales son los celulosicos, los esteres de celulosa, las poliamidas y el polipropileno. La adicion del monomero al substrato fibroso tiene lugar, al parecer, por accion de radicales libres y, como ya se ha indicado, es posible irradiar primero el material y conseguir despues el injerto exponiendo el material irradiado al vapor del monomero. Se ha procurado determinar la vida de los radicales libres, y aunque ha resultado dificil obtener cifras exactas, se ha podido comprobar que pueden subsistir en algunas fibras por espacio de 15 a 20 h despues de la irradiacion, incluso a la temperatura ambiente. Las pruebas experimentales parecen indicar tambien que el tiempo de difusion del monomero en los puntos correspondientes a los radicales libres, en el injerto subsiguiente a la irradiacion, varia segun la fibra. El algodon modificado por adicion de poliacrilonitrilo constituye una fibra que presenta una resistencia casi perfecta a la accion de los microorganismos. Solo se precisa un deposito de un 3,5% y el material conserva el aspecto y el tacto del algodon no tratado. El producto obtenido es de calidad superior al que se consigue con la adicion de acrilonitrilo en presencia de peroxido de hierro como catalizador. El polipropeno puede ser injertado en distintos monomeros, dando una fibra que puede ser teSida por los procedimientos usuales. No obstante, por el momento la solidez al lavado de los materiales injertados y tenidos no es satisfactoria para un producto comercial. La resistencia del hilo de acetato de celulosa, asi como su modulo de elasticidad pueden incrementarse por adicion de poliacrilonitrilo, pero otros monomeros no dan resultados comparables. Existen indicios de que la calidad de la fibra puede ser mejorada mediante un compuesto, en particular por lo que se refiere a su resistencia en estado humedo. Los autores estiman que la modificacion de las propiedades de la fibra mediante el procedimiento descrito podria aprovecharse en el terreno comerical de encontrarse procedimientos que permitan aumentar la velocidad de difusion del monomero en la estructura de la fibra. (author) [Russian] Razrabotana standartnaya metodika radiatsionnoj privivki letuchikh vinilovykh monomerov k voloknistym polimeram. Ehta metodika sostoit v vvedenii organicheskogo soedineniya v parovoj faze; protsess osushchestvlyaetsya ili putem odnovremennogo oblucheniya ili predvaritel'nym oblucheniem ot istochnika Co''6''0. Issledovany sistemy, povyshayushchie skorost' privitoj sopolimeriehatsii. Ustanovleno, chto mozhno vvodit' znachitel'nye kolichestva nekotorykh monomerov, ne vyzyvaya radiatsionnogo povrezhdeniya voloknistogo substrata. Imenno te voloknistye materialy, kotorye sravnitel'no neustojchivo reagiruyut na radiatsiyu naibolee legko prisoedinyayut vinilovye soedineniya. K takim materialam otnosyatsya tsellyulozy, slozhnye ehfiry tsellyulozy, poliamidy i polipropilen. Prisoedinenie monomera k voloknistomu substratu, ochevidno, proiskhodit po svobodno-radikal'nomu mekhanizmu, i, kak uzhe ukazyvalos' vyshe, mozhno snachala obluchit' volokno a zatem provodit' privivku, podvergaya obluchennyj material vozdejstviyu parov mono- mera. Predprinimalis' popytki vyyasnit' dlitel'nost' sushchestvovaniya svobodnykh radikalov i, khotya dovol'no trudno poluchit' tochnye dannye, bylo pokazano, chto svobodnye radikaly prodolzhayut sokhranyat'sya v nekotorykh voloknakh spustya 15 - 20 chasov posle oblucheniya, dazhe pri komnatnoj temperature. Predvaritel'nye opytnye dannye takzhe navodyat na mysl' o tom,chto pri posleradiatsionnom privivanii monomer diffundiruet k svobodno-radikal'nym tsentram s razlichnymi skorostyami v raznykh voloknakh. Volokno khlopka, modifitsirovannoe vvedeniem v ego sostav poliakrilonitrila, ustojchivo k dejstviyu mikroorganizmov. Vvedenie 3,5%-nogo poliakrilonitrila pozvolyaet materialu sokhranyat' vneshnij vid i grif, kak u neobrabotannogo khlopka. Po svoim svojstvam ehtot produkt luchshe produkta, poluchennogo vvedeniem akrilonitrila i primeneniem kataliehatsionnoj sistemy zhelezo - perekis'. K polipropilenu mozhno privit' ryad razlichnykh monomerov, poluchaya volokna, kotorye mozhno okrashivat', primenyaya standartnye metody okraski. Tem ne menee na nastoyashchej stadii razrabotki prochnost' privitykh i okrashennykh materialov vo vlazhnom sostoyanii eshche nedostatochno vysoka, chtoby mozhno bylo ehti materialy pustit' v proizvodstvo. Krepost' atsetattsellyuloznoj pryazhi, takzhe kak i ee modul' uprugosti, mozhno zametno povysit' vvedeniem poliakrilonitrila. Drugie monomery vedut sebya inache. Imeyutsya nekotorye ukazaniya na to, chto kachestvo volokna mozhno uluchshit', vvedya v ego sostav opredelennoe soedinenie, osobenno ehto otnositsya k svojstvam volokna vo vlazhnom sostoyanii. Modifikatsiya volokon sposobom, opisannym vyshe, mozhet stat' ehkonomicheski vygodnoj, esli budet razrabotana metodika, pozvolyayushchaya uvelichit' skorost' diffuzii monomera v voloknistuyu strukturu. (author)

  14. The Radioisotopic Determination of Diffusion Coefficients and Currents in Natural Waters. Surface Collection of Radioactive Fall-Out on a Large Alpine Lake; Determination par detection nucleaire des coefficients de diffusion et des courants dans les eaux naturelles. Evolution de la surface de collection d'un grand lac alpin pour les retombees radioactives; Opredelenie koehffitsienta diffuzii i skorosti techeniya estestvennykh vod pri pomoshchi yadernogo detektirovaniya. Ehvolyutsiya poverkhnosti sbora radioaktivnykh osadkov na bol'shom al'pijskom ozere; Determinacion por deteccion nuclear de los coeficientes de difusion y de las corrientes en las aguas naturales evolucion de la superficie de captacion de un gran lago alpino para las precipitaciones radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Chesselet, R.; Nordemann, D. [Service d' Electronique Physique, Centre d' Etudes Nucleaires de Saclay (France); Dussart, B. [Centre de Recherches Hydrobiologiques, CNRS, Gif-sur-Yvette (France)

    1963-08-15

    In an initial stage, the authors brought about the in situ diffusion of a radioactive emitter (sodium-22, in the form of Na{sup +}) with very low activity, i.e. less than 1 mc. The diffusion laws applied in this case made it easy to predict the rate of diffusing of the {sup r}adioactive cloud{sup .} In this way, plotting the activities, as measured by two suitably placed gamma detectors, against time permits the estimation of a diffusion coefficient for the emitter used and, if appropriate, the measurement of current velocity at the point of measurement (in the case described, the Lake of Geneva). Subsequently, and in conjunction with a geophysical study on the general problem of radioactive fall-out, the authors worked on the increases in radioactive fall-out caused by nuclear tests in the atmosphere (October 1961 - January 1962). Measurements of radioactivity were made every day on samples of Lake Geneva water taken at depths of 0 m, 10 m and 20 m and also on a collector of dry and moist atmospheric fall-out. Despite the complex pattern, over a period, of theincreasesinfall-out , the interpretation of the diagrams obtained can help to explain what happens to radioactive products in the diffusion and current conditions encountered. The use of the diffusion of radioactive products in very small quantities and of the various highly sensitive techniques of nuclear detection now available can lead to a better understanding of in situ diffusion and of the movement of natural water masses. (author) [French] Dans un premiere etape, les auteurs ont provoque la diffusion in situ d'un emetteur radioactif, le sodium 22, sous forme de Na{sup +}, avec des activites tres faibles, inferieures au millicurie. Les lois de la diffusion appliquee a ce cas permettent aisement de prevoir l'allure du 'n'uage radioactif'' en cours de diffusion. Ainsi, l'enregistrement en fonction du temps des activites mesurees par deux detecteurs gamma convenablemen t disposes conduit a l'evaluation d'un coefficient de diffusion pour l'emetteur utilise et a la mesure eventuelle de la vitesse du courant au point ou la mesure est effectuee (dans le cas decrit, le lac Leman). Dans une seconde etape, en correlation avec une etude de geophysique concernant le probleme general des retombees radioactives, les auteurs ont utilise l'apport des retombees radioactives ayant pour origine les essais nucleaires atmospheriques (octobre 1961-janvier 1962). Des mesures de la radioactivite ont ete effectuees chaque jour sur des prelevements d'eau du lac Leman a des profondeurs de 0 m, 10 m, 20 m et sur un collecteur de retombees atmospheriques seches et humides. Malgre la complexite du regime des apports en fonction du temps, l'interpretation des diagrammes obtenus peut contribuer a resoudre le probleme du devenir des produits radioactifs dans les conditions de diffusion et de courants rencontrees. L'utilisation de la diffusion de produits radioactifs en tres faibles quantites et des differentes techniques de detection nucleaires a haute sensibilite actuellement disponibles peut conduire a une meilleure connaissance de la diffusion in situ et du mouvement des masses d'eaux naturelles. (author) [Spanish] En una primera etapa, los autores ha i provecado la difusion in situ de un emisor radiactivo, el sodio-22 en forma de Na{sup +}, de actividad muy baja (inferior al milicurie). La aplicacion de las leyes de la difusion a este caso facilita el calculo de la velocidad de difusion de la ''nube radiactiva''. Por consiguiente, el registro en funcion del tiempo de las actividades medidas con dos detectores gamma dispuestos de modo conveniente permite asignar un coeficiente de difusion ai emisor empleado y, eventualmente, evaluar la velocidad de la corriente en el punto en que se efectua la medicion (en el caso descrito, el lago Leman). En una segunda etapa, en relacion con un estudio geofisico del problema general de las precipitaciones radiactivas, los autores utilizaron la aportacion de las precipitacione s radiactivas debidas a las explosiones nucleares en la atmosfera (octubre de 1961-enero de 1962). Midieron diariamente la radiactividad en muestras de agua del lago Leman tomadas a 0, 10 y 20 m de profundidad y en un colector de precipitaciones atmosfericas secas y humedas. A pesar de la complejidad del regimen de aportaciones en funcion del tiempo, la inter- pretacion de los diagramas obtenidos puede contribuir a resolver el problema del destino de los productos radiactivos en las condiciones de difusion y de corriente que reinan en la practica. La difusion de productos radiactivos en cantidad muy pequena, unida a la utilizacion de diversas tecnicas de deteccion nuclear de alta sensibilidad, permitiran obtener mas datos sobre la difusion in situ y el movimiento de las masas de aguas naturales. (author) [Russian] Na pervom ehtape avtory vyzvali diffuziyu ''in situ'' na radioaktivnom izluchatele, natrii-22, v vide Na{sup +}, s aktivnost'yu nizhe 1 millikyuri. Zakony diffuzii, primenennye v ehtom sluchae, legko pozvolyayut predvidet' skorost' ''radioaktivnogo Oblaka'' vo vremya diffuzii. Takim obrazom, registratsiya aktivnosti v zavisimosti ot vremeni, izmerennaya s pomoshch'yu dvukh nadlezhashchim obrazom raspolozhennykh gamma- detektorov, privela k otsenke koehffitsienta diffuzii dlya ispol'zuemogo izluchatelya i k izmereniyu skorosti techeniya v toj tochke, gde proizvodilos' izmerenie (v dannom sluchae ozero Leman). Na vtorom ehtape v sootvetstvii s geofizicheskim issledovaniem obshchej problemy radioaktivnogo vypadeniya, avtory ispol'zovali nakoplenie radioaktivnykh osadkov, voznikshikh v rezul'tate yadernykh ispytanij, provedennykh v atmosfere v oktyabre 1961 - yanvare 1962 g. Kazhdyj den' bralis' proby vody Lemanskogo ozera na glubinakh O, 10 i 20 m, a takzhe sukhikh i vlazhnykh atmosfernykh vypadenij. Nesmotrya na slozhnost' rezhima nakopleniya v zavisimosti ot pogody, tolkovanie poluchennoj-diagrammy mozhet sposobstvovat' razresheniyu problemy vypadeniya radioaktivnykh produktov v usloviyakh diffuzii i vstrechnykh potokov. Ispol'zovanie diffuzii radioaktivnykh produktov v ochen' nebol'shikh kolichestvakh i razlichnye metody obnaruzheniya pri pomoshchi yadernykh izmerenij vysokoj chuvstvitel'nosti mogut privesti v nastoyashchee vremya k nailuchshemu ponimaniyu diffuzii Tin situ'' i dvizheniyu mass prirodnykh vod. (author)

  15. Review of Development Status of Nuclear Superheat; Expose sur l'etat actuel des travaux concernant la surchauffe nucleaire; Obzor razrabotki voprosa o yadernykh peregrevatelyakh; Estudio de los progresos realizados en niateria de sobrecalentamiento nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Imhoff, D. H.; Pennington, R. T. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    nuclear utilizado en el sobrecalentador, evaluaciones de la corrosion uniforme y localizada, tanto en el interior como en el exterior del reactor, resultados de experimentos criticos de sobrecalentamiento termico, y de las comprobaciones experimentales de transmision de calor; por ultimo, examen sucinto de las ventajas economicas que, segun los estudios, presentan los reactores de sobrecalentador separado, los reactores de sobrecalentador integrado y los reactores con sobrecalentamiento de espectro mixto. b) Breve descripcion del programa ESADA-VESR de desarrollo de combustibles para sobrecalentamiento nuclear, patrocinado por la Comision de Energia Atomica. Examen de los trabajos de investigacion, del diseflo de los elementos combustibles de la primera carga del sobrecalentador, de la gama de variables experimentales y de los resultados previstos para el programa trienal de desarrollo del combustible. (author) [Russian] Nachinaya s 1959 goda kompaniya ''Dzheneral Ehlektrik'' aktivno zanimalas' provedeniem raboty v oblasti yadernogo peregreva na reaktorakh s zamedlitelem iz obychnoj vody. Za ehtot period v SSHA vpervye byl proizveden yadernyj peregretyj par v khode provedeniya usovershenstvovannogo demonstratsionnogo ehksperimenta s peregrevom cha ustanovke SADE. Ehtot proekt finansirovalsya kompaniej. Nyneshnee sostoyanie s yadernym peregrevom podrazdelyaetsya na dve glavnye kategorii. Pervaya yavlyaetsya opisaniem trekh osnovnykh ustanovok po oblucheniyu peregretogo topliva, ispol'zuemykh kompaniej ''Dzheneral ehlektrik'', i vtoraya - opisaniem dvukh glavnykh razrabotannykh programm deyatel'nosti, vmeste s obzorom po sostoyaniyu na segodnyashnij den' znachitel'nykh rezul'tatov razvitiya v oblasti peregreva. 1. Glavnye usovershenstvovannye ustanovki: a) Daehtsya kratkoe opisanie ehksperimenta (SADE) na Vallesitosskom reaktore s kipyashchej vodoj (VBWR), privodyatsya tablitsy ehkspluatatsionnykh uslovij, dannye o toplivnykh ehlementakh, obluchennykh v period mezhdu maem

  16. RB research nuclear reactor - Annual report for 1986, I - III; Istrazivacki nuklearni reaktor RB (Izvestaj o radu u 1986. godini), I-III

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Jevremovic, M; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1987-07-01

    This report includes data concerning the RB reactor operation in 1986, state of the reactor components, data about the employed personnel and the database of experimental and other reactor related devices. It is made of 3 parts: Engineering description and operation of the RB reactor including dosimetry, reactor staff data and financial report; Reactor facility components and maintenance; RB reactor operation and utilization in 1986. Izvestaj pokazuje podatke o radu reaktora RB u toku 1986. godine, stanje reaktorske opreme, podatke o angazovanom osoblju na reaktoru i datoteku sa podacima o eksperimentalnoj i drugoj opremi reaktora RB. Sastoji se od 3 dela: tehnicki opis, pogon i rad reaktora, oprema postrojenja i njeno odrzavanje, koriscenje reaktora u 1986. godini.

  17. II-1 General regulatory guide for staff on duty; II-1 Opsti pravilnik za rad dezurnog osoblja

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    Personnel responsible for RA reactor operation is working in shifts. This regulatory guide describes in detail rights, tasks and responsibilities of each staff member in duty when operating the reactor under regular conditions, during start-up, during shutdown, during repair and maintenance shutdown periods. Rad reaktora odvija se po smenama. Ovaj pravilnik regulise prava, duznosti i odgovornost svakog od clanova tima u smeni pojedinacno u regularnim uslovima rada, prilikom remonta, u toku stajanja, dostizanja nominalne snage, zaustavljanja rada reaktora.

  18. Project RA Research nuclear reactor - Annual report 1993 with comparative review for the period 1991 - 1993; Projekat Istrazivacki nuklearni reaktor RA - Izvestaj za 1993. godinu, uz uporedni pregled za period 1991 - 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-15

    Research reactor RA Annual report for year 1993 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. The ninth separate annex deals with the feasibility of RA reactor applications. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1993. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Poseban prilog razmatra mogucnosti koriscenja istrazivackog reaktora RA. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  19. Research nuclear reactor RA - Annual Report 1975. Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1975. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    The plan for 1975 was successfully fulfilled. This is reflected in research related to improvement of operating properties of the RA reactor, mostly due to the effort of the RA staff employed in operation and maintenance of the reactor. Fuel saving achieved by this activity amounted to about 38% (80% enriched fuel). Preliminary work is done, concerned with new reactor core with highly enriched fuel. This is a significant saving as well. New fuel elements have arrived at the end of this year. It is going to enable increase of neutron flux by 50% without changing the nominal operating power. The possibility of further improvement of the reactor are analyzed, to enable material testing and production of radioactive sources. Mid term plan for reactor operation was made according to this analysis. It is planned to further increase the neutron flux in isolated smaller zones, and building new experimental loops with cooling and fast neutron converters. Much was done to increase the safety level of reactor operation and preparing the safety report. [Serbo-Croat] Izvrsenje zadataka u 1975. godini bilo je uspesno. To se ogleda u povecanju istrazivackog rada vezanog za poboljsanje eksploatacionih karakteristika reaktora RA, pretezno koriscenjem sopstvenog kadra angazovanog u pogonu i odrzavanju reaktora. Ovim radom postignuta je usteda goriva od oko 38% (80% obogaceno gorivo). Izvrseni su preliminarni radovi na prevodjenju reaktora RA na novo gorivo, sto je takodje velika usteda. Novo gorivo je stiglo krajem godine i ono ce obezbediti porast neutronskog fluksa od 50%, bez promene nominalne snage reaktora. Izvrsena je analiza mogucnosti daljeg usavrsavanja reaktora za potrebe ispitivanja materijala kao i proizvodnju radioaktivnih izvora. Na osnovu ove analize nacinjen je srednjorocni program rada reaktora RA sa tezistem na daljem povecanju fluksa u izdvojenim manjim zonama i ugradnju 'hladjenih petlji' i brzih konvertora. Mnogo je ucinjeno na povecanju stepena sigurnosti

  20. Research nuclear reactor RA - Annual report 1992; Istrazivacki nuklearni reaktor RA - Izvestaj za 1992. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-12-01

    Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Drugi prilog (B) je rad Z. Vukadina 'Recurrence formulas for evaluating expansion series of depletion functions' objavljen u casopisu Kerntechnik, 1991. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  1. Reproduction of the RA reactor fuel element fabrication; Reprodukcija izrade gorivnog elementa za reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This document includes the following nine reports: Final report on task 08/12 - testing the Ra reactor fuel element; design concept for fabrication of RA reactor fuel element; investigation of the microstructure of the Ra reactor fuel element; Final report on task 08/13 producing binary alloys with Al, Mo, Zr, Nb and B additions; fabrication of U-Al alloy; final report on tasks 08/14 and 08/16; final report on task 08/32 diffusion bond between the fuel and the cladding of the Ra reactor fuel element; Final report on task 08/33, fabrication of the RA reactor fuel element cladding; and final report on task 08/36, diffusion of solid state metals. Ovaj rad sadrzi devet priloga: 1. Zavrsni izvestaj o podzadatku 08/12, ispitivanje elementa goriva reaktora RA; 2. Koncepcija izrade gorivnog elementa reaktora RA; 3. Ispitivanje mikrostrukture gorivnog elementa reaktora RA; 4. Zavrsni izvestaj o podzadatku 08/13, dobijanje binarnih legura urana sa legirajucim komponentama Al, Mo, Zr, Nb i B; 5. Dobijanje legure U-Al; 6. Zavrsni izvestaj o podzadacima 08/14 i 08/16; 7. Zavrsni izvestaj o podzadatku 08/32, difuziona veza goriva i kosuljice gorivnog elementa reaktora RA; 8. Zavrsni izvestaj o podzadatku 08/33, izrada kosuljice gorivnog elementa reaktora RA; 9. Zavrsni izvestaj o podzadatku 08/36, difuzija kod metala u cvrstom stanju.

  2. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Cupac, S; Vukadin, Z; Stosic, T; Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    This report describes the organisational structure of the technology service and its activities and tasks: routine control of reactor parameters and cooperation with the reactor users; development of methodology of reactor control and its application; control of heavy water and gas system operation; dosimetry measurements of contamination in the reactor building; technical aspects of radiation protection; decontamination and accident analysis. Separate chapter describes building of the reactor experimental loop for irradiation of fuel elements and construction materials, which will be placed in the central experimental channel VK-5. [Serbo-Croat] Ovaj izvestaj opisuje organizacionu semu tehnoloske sluzbe i zadatke koje ona obavlja: rutinska kontrola reaktorsko-fizickih parametara reaktora i saradnja sa korisnicima reaktora, razvojni rad na metodologiji kontrole reaktora i njegovog koriscenja, kontrola rezima rada teskovodnog i gasnog sistema, dozimetrija i tehnicka zastita od zracenja u zgradi reaktora, dekontaminacija i akcidentalna analiza. Posebno poglavlje opisuje izgradnju eksperimentale petlje za ozracivanje gorivnih elemenata i konstrukcionih materijala koja ce biti postavljena u centralnom eksperimentalnom kanalu VK-5 reaktora RA, koja je projektovana kao slozena eksperimentalna instalacija.

  3. Determination of the tritium content in the reactor heavy water, Phase II; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi, II faza

    Energy Technology Data Exchange (ETDEWEB)

    Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-07-15

    Measurement results of the {sup 3}H activity in non-irradiated water and after reactor operation are presented. Methods were developed for sampling and radiochemical water purification by ion exchange and multiple distillation. Methods for absolute measurement of soft beta radiation of tritium were established. Migration of tritium through the heavy water RA reactor system was monitored. Results were compared with other measured reactor parameters. Prikazani su rezultati merenja aktivnosti {sup 3}H u nezracenoj vodi i posle rada reaktora; razradjeni su metodi za uzimanje i radiohemijsko preciscavanje vode putem jonske izmene i visestepene destilacije; postavljeni metodi za apsolutno merenje mekog beta-zracenja tritijuma; pracene su migracije tritijuma kroz teskovodni sistem reaktora; takodje su interpretirani i poredjeni rezultati sa drugim merenim parametrima reaktora.

  4. Decision, Annex 3[Organizational structure of the Division for reactor maintenance]; Prilog br. 3, Odluka

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The objective of the decision about the change in the organizational scheme of the Division for RA reactor maintenance is to achieve efficiency. The tasks are precisely defined as to divide the maintenance and repair tasks from special ones related to improvement of reactor operation its applicability. [Serbo-Croat] U cilju poboljsanja organizacije rada Odelenja odrzavanja reaktora RA, kao i efikasnijeg koriscenja raspolozivog kadra izvrsice se razgranicenje poslova odrzavanja i remonta od posebnih zadataka koji se odnose na poboljsanje rada reaktora i povecanje njegovih mogucnosti.

  5. Action plan for 1965, Annex 2; Prilog br. 2 - Plan zadataka u 1965. godini

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-15

    Action plan presented in this annex includes tasks of the mechanics, electrical and electronic equipment services. It includes a detailed list of planned and preventive maintenance actions related to the heavy water system, technical water system, helium system, reactor core, transportation equipment, hot cells, heating and ventilation systems in the reactor building, power supply system, auxiliary systems in the RA reactor building. [Serbo-Croat] Plan zadataka obuhvata aktivnosti masinske i elektro grupe na preventivnom odrzavanju i planskom remontu sistema teske vode, sistema tehnicke vode, sistema helijuma, centralnog tela reaktora, sistema grejanja i ventilacije, sistema za snabdevanje elektricnom energijom, i ostalih pomocnih sistema u zgradi reaktora RA.

  6. Radiation protection at the RA Reactor in 1985, Part -2, Annex 2c, Reconstruction of the measuring device on the meteorology tower; Deo 2 - Zastita od zracenja kod reaktora RA u 1985. godini - Prilog 2c - Rekonstrukcija merne instalacije na meteoroloskom stubu

    Energy Technology Data Exchange (ETDEWEB)

    Savic, Z; Stevanovic, M; Kovacevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-12-01

    Original meteorology measuring instrumentation dates from 1960-1961. In order to enable more efficient measurements it was indispensable to reconstruct measuring devices completely. Description of the reconstruction works and specification is included in this report. [Serbo-Croat] Prvobitna instrumentacija namenjena meteoroloskim merenjima datira iz perioda 1960-1961. Sa ciljem da se merenja usavrse bilo je neophodno rekonstruisati celokupnu mernu opremu. Opis rekonstrukcije i specifikacija opreme sadrzani su u ovom izvestaju.

  7. Theoretical analysis of nuclear reactors (Phase III), I-V, Part V, Establishment of Monte Carlo method for solving the integral transport equation; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-V, V Deo, Postavljanje Monte Carlo metode za resavanje integralnog oblika transportne jednacine

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-02-15

    General mathematical Monte Carlo approach is described with the elements which enable solution of specific problems (verification was done by estimation of a simple integral). Special attention was devoted to systematic presentation which demanded explanation of fundamental topics of statistics and probability. This demands a procedure for modelling the stochastic process i.e. Monte Carlo method. Dat je matematicki prilaz Monte Carlo metodi uopste, a po elementima koji dozvoljavaju konkretno resavanje izvesnih problema. (Provera je izvrsena na estimiranju prostog integrala). Narocito je vodjeno racuna o sistematicnosti izlaganja materije sto je mestimicno zahtevalo tretiranje i osnovnih pojmova, statistike i verovatnoce, a sve to skupa zahteva postupak modeliranja stohastickog procesa odnosno Monte Carlo metod (author)

  8. Industrial Ultrasonic Inspection of Stainless-Steel Claddings for the EL4 Reactor; Controle Industriel par Ultrasons des Gaines en Acier Inoxydable du Reacteur EL4; Promyshlennyj kontrol' obolochechnykh trub iz nerzhaveyushchej stali reaktora dlya EL4 s pomoshch'yu ul'trazvukovogo metoda; Metodos Ultrasonicos para Control Industrial de las Vainas de Acero Inoxidable del Reactor EL4

    Energy Technology Data Exchange (ETDEWEB)

    Prot, A. C.; Foulquoer, H. E.; Peyrot, J. P. [Centre d' Etudes Nucleaires de Saclay (France)

    1965-09-15

    Improved reactor performance requires the use of accurately fabricated and carefully inspected components. One inspection relates to the quality of the cladding tubes, whose mechanical reliability is essential for economic reactor operation. The choice and development of a method is a difficult matter and the authors explain the main factors involved. Once the choice has been made and the method has been developed in the laboratory, two new problems arise: Adaptation to meet industrial requirements; and The need to reconcile the quality standards attainable with the manufacturing process at any given stage and the somewhat arbitrarily defined specifications for the finished product. In practice, this involves a statistical study of batches of tubes from various sources and their classification in relation to more or less strict thresholds. The number of tubes which have to be inspected is much larger than originally expected. This has led to the design of an automatic inspection device geared both to the output rates involved and to the requirements of the type of inspection adopted; the latter are generally mechanical and impose particularly careful product fabrication. These various characteristics are now embodied in a device whose capacity can already easily meet the requirements of a fuel-element production line. The potentialities of the device are closely dependent on the characteristics of the inspection equipment used, especially the performances of the electronic part of ultrasonic inspection instruments and of the transducers. This study shows that standard equipment is not very suitable and that immediate thought should be given to special instruments for this type of inspection. (author) [French] L'accroissement des performances des reacteurs necessite l'utilisation de materiaux finement elabores et soigneusement controles. L'un des aspects de ce controle est celui de la qualite des tubes de gainage utilises, dont la tenue mecanique est un facteur essentiel de rentabilite du reacteur. Il s'avere que le choix de la methode a utiliser et a mettre au point est delicat; le memoire en donne les elements essentiels. Ce choix etant fait, apres mise au point en laboratoire, deux nouveaux problemes se posent: - la transposition dans le domaine industriel; - la necessite de tenir compte de la qualite permise, a un instant determine, par les procedes de fabrication, en relation avec les normes de reception definies de maniere plus ou moins arbitraire. Ceci se traduit en fait par la necessite d'une etude statistique sur des lots de tubes de diverses provenances, et leur classement par rapport a des seuils plus ou moins severes. On verra que le nombre de tubes a controler est tres superieur a celui prevu initialement. Cela conduit a l'etude d'une machine de controle automatique, capable de satisfaire a la fois les exigences de cadence et celles propres au type de controle choisi: ces dernieres sont generalement d'ordre mecanique et necessitent une construction particulierement soignee. L'ensemble de ces considerations a conduit a concevoir une machine dont la cadence peut des maintenant couvrir sans difficulte les besoins d'une chaihe de fabrication d'elements combustibles. Les possibilites de cette machine sont etroitement liees aux caracteristiques du materiel de controle choisi, en particulier aux performances de l'electronique des appareils de controle par ultrasons et a celles des traducteurs utilises. Il resulte d'ailleurs de cette etude que le materiel standard ne repond que tres imparfaitement au probleme et que l'on doit envisager des maintenant un appareillage particulier pour ce type de controle. (author) [Spanish] Las mayores exigencias a que se someten los reactores obligan a utilizar materiales elaborados y controlados con sumo cuidado. Un aspecto de tal control se refiere a la calidad de las vainas empleadas, cuyas propiedades mecanicas ejercen una influencia decisiva sobre la rentabilidad del reactor. La eleccion del metodo a utilizar representa un proceso delicado, cuyas consideraciones fundamentales se exponen en el presente trabajo. Una vez elegido el metodo y puesto a punto en el laboratorio, surgen dos nuevos problemas: Transposicion a escala industrial. Necesidad de tener siempre presente la calidad que puede alcanzarse en la industria, en relacion con normas de aceptacion definidas de manera mas o menos arbitraria. En la practica, ello obliga a realizar un estudio estadistico sobre partidas de tubos de diversos origenes y clasificarlos teniendo en cuenta umbrales de aceptacion de distintos grados de severidad. Como se ve en el trabajo, el numero de tubos a controlar es muy superior al previsto inicialmente. Este hecho indujo a estudiar una maquina de control automatico, capaz de satisfacer al mismo tiempo las exigencias de la cantidad y las propias del tipo de control seleccionado; estas ultimas son por lo general de orden mecanico y requieren una construccion especialmente esmerada. El conjunto de estas consideraciones llevo a concebir una maquina capaz de satisfacer sin dificultad las necesidades de una cadena de fabricacion'de elementos combustibles. Las posibilidades de esta maquina estan estrechamente ligadas a las caracteristicas del material descontrol escogido, sobre todo al rendimiento de los circuitos electronicos correspondientes a los aparatos de control por metodos ultrasonicos y al de los transductores utilizados. Se deduce del presente estudio, por otra parte, que el material corriente no responde al problema sino de manera muy imperfecta, y que se debe encarar desde ya el proyecto de un aparato especial para este tipo de control. (author) [Russian] Uluchshenie rabochih harakteristik reaktorov trebuet primenenija tshhatel'no razrabotannyh i strogo kontroliruemyh materialov. Odnim iz aspektov jetogo kontrolja javljaetsja kachestvo ispol'zuemyh pokrytij dlja trub, mehanicheskoe sostojanie kotoryh predstavljaet soboj sushhestvennyj faktor rentabel'nosti reaktorov. Podtverzhdaetsja, chto vybor metoda, kotoryj sleduet primenjat' i razrabatyvat', javljaetsja trudnym. Privodjatsja osnovnye momenty. Posle togo, kak v rezul'tate laboratornyh rabot sdelan vybor, voznikajut dve novye problemy: D) vnedrenie v promyshlennost' neobhodimost' ucheta dopustimogo kachestva v opredelennyj moment metodami izgotovlenija v svjazi s ustanovlennymi bolee ili menee proizvol'nym obrazom normami dlja priema. Jeto, v dejstvitel'nosti, obuslavlivaetsja neobhodimost'ju v statisticheskom issledovanii komplektov trub razlichnogo izgotovlenija i ih klassifikacii po otnosheniju k bolee ili menee strogim normam. Vidno, chto kolichestvo podlezhashhih kontrolju trub znachitel'no prevyshaet pervonachal'no namechennoe. Jeto vedet k izucheniju avtomaticheskogo kontrol'nogo mehanizma, sposobnogo udovletvorit' odnovremenno i trebovanijam tempa, i trebovanijam, vytekajushhim iz vybrannogo tipa kontrolja: poslednie obychno svodjatsja k mehanicheskomu kontrolju i nuzhdajutsja v osobenno tshhatel'no razrabotannoj konstrukcii. Sovokupnost' jetih soobrazhenij privela k razrabotke ustrojstva, temp raboty kotorogo uzhe sejchas mozhet bez truda pokryt' potrebnosti vsego cikla proizvodstva toplivnyh jelementov. Vozmozhnosti jetogo ustrojstva tesno svjazany s harakteristikami podobrannogo oborudovanija navedenija i kontrolja, v osobennosti so svojstvami jelektroniki priborov kontrolja po ul'trazvuku i so svojstvami ispol'zuemyh preobrazovatelej. K tomu zhe iz jetogo issledovanija javstvuet, chto standartnoe oborudovanie daleko ne sootvetstvuet probleme i chto uzhe sejchas sleduet predusmotret' osoboe ustrojstvo dlja dannogo tipa kontrolja. (author)

  9. Irradiated uranium reprocessing, Final report I-VI, IV Deo IV - Separation of uranium, plutonium and fission products from the irradiated fuel of the reactor in Vinca; Prerada ozracenog urana. Zavrsni izvestaj - I-VI, IV Deo - Odvajanje urana, plutonijuma i fisionih produkata iz isluzenog goriva reaktora u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za visoku aktivnost, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    This study describes the technology for separation of uranium, plutonium and fission products from the radioactive water solution which is obtained by dissolving the spent uranium fuel from the reactor in Vinca. The procedure should be completed in a hot cell, with the maximum permitted activity of 10 Ci.

  10. Conclusions of the experts group of the RA reactor at the meeting held on November 2 and 3 1964 - Annex 12a; Prilog 12a - Zakljucci sa sastanka Strucnog kolegijuma reaktora RA odrzanog na dan 2. i 3. novembra 1964. godine

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    Conclusions of the experts group of the RA reactor are related to: analyses of reactor operation at 6.5 MW power with heavy water coolant flow of 250 m{sup 3}/h (2 pumps rotation speed 1500 rotations/min); decisions of future operation; further preparation activities related to reactor operation in forced regime and reduced cooling conditions.

  11. Determination of the Effectiveness of Control Rods in the VVER Reactor Fuel Assemblies; Determination de l'Efficacite des Barres de Reglage dans les Ensembles Combustibles du reacteur VVER; Opredelenie ehffektivnosti reguliruyushchikh sterzhnej v sborkakh reaktora VVEHR; Determinacion de la Eficacia de las Barras de Control en los Conjuntos de Elementos Combustibles del Reactor VVER

    Energy Technology Data Exchange (ETDEWEB)

    Semenov, V. N.; Lunin, G. L.; Komissarov, L. V.; Kamyshan, A. N.; Halizev, V. I.; Andrianov, G. Ja.; Voznesenskij, V. A.; Kuz' micheva, V. A.; Lebedev, V. I. [Ordena Lenina Institut Atomnoj Energii Im. I.V. Kurchatova, Moskva, SSSR (Russian Federation)

    1964-06-15

    The paper describes experiments done in homogeneous mock-ups of the fuel assemblies from the VVER Reactor (at one level of enrichment) to determine the effectiveness of absorbing systems comprising shim fuel assemblies or water cavities and of absorbing rods clad in jackets made of differing materials. The paper also gives data on some experiments that have been done in mock-ups of assemblies with differing levels of enrichment. These experiments make it possible to verify the methods used in calculation and to evaluate the prospects of using them for heterogeneous reactors. (author) [French] Le memoire decrit les experiences qui ont ete faites pour determiner l 'efficacite des absorbants contenus dans les barres de compensation, l'effet cavitaire et l 'efficacite des absorbants gaines de materiaux divers, au moyen d'assemblages homogenes de cartouches de combustible du reacteur VVER (reacteur de puissance ralenti et refroidi a l 'eau ayant le meme taux d'enrichissement. On y trouve en outre des donnees sur certaines experiences executees a l 'aide d'assemblages de cartouches de combustible taux d'enrichissement differents. Ces travaux permettent de verifier la methode de calcul et d'evaluer ses possibilites d'application aux reacteurs non homogenes. (author) [Spanish] Se describen en la memoria experimentos para determinar la eficacia de los materiales absorbentes contenidos en las barras de compensacion, el efecto de cavitacion y la eficacia de los materiales absorbentes revestidos de diversos materiales, realizados con ayuda de los conjuntos homogeneos de elementos combustibles del reactor VVER (reactor de potencia moderado y refrigerado por agua) con un solo grado de enriquecimiento. Ademas, se exponen datos sobre los experimentos efectuados con ayuda de conjuntos de grados de enriquecimientos; variados. Tales experimentos permiten verificar el metodo de calculo teorico, utilizad o y evaluar la posibilidad de aplicarlo a los reactores no homogeneos. (author) [Russian] V doklade opisyvajutsja jeksperimenty po opredeleniju jeffektivnosti poglotitelej kompensirujushhih kasset vodjanyh polostej i poglotitelej kompensirujushhih k a s set vodjanyh polostej i poglotitelej s chehlami iz razlichnyh materialov na odnorodnyh sborkah, sostojashhih iz kasset s razlichnym obogashheniem. Krome t o go , privodjatsja dannye po nekotorym jeksperimentam na sborkah iz kasset s razlichnym obogashheniem. Jeti jeksperimenty pozvoljajut proverit' metodiku ra sch eta i ocenit' vozmozhnosti ee primenenija dlja neodnorodnyh reaktorov . (author)

  12. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci - Radiohemija

    Energy Technology Data Exchange (ETDEWEB)

    Dizdar, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    The history of the work in the field of radiochemistry at the Boris Kidric Institute of nuclear sciences, Vinca, Yugoslavia, is given. The technical, organization and staff conditions on which further successful development in this domain depends are discussed (author) [Serbo-Croat] Daje se istorijat rada na radiohemiji u Institutu za nuklearne nauke 'Boris Kidric' u Vinci od njegovog osnivanja do danas. Govori se o tehnickim, organizacionim i kadrovskim uslovima od kojih zavisi dalji uspesan razvoj ove oblasti (author)

  13. Actions needed for RA reactor exploitation - I-IV, Part I, Thermotechnical experiments related to RA reactor hot start-up; Radovi za potrebe eksploatacije reaktora RA - I-IV, I Deo, Termotehnicki eksperimenti u vezi pustanja rektora RA na snagu

    Energy Technology Data Exchange (ETDEWEB)

    Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Heavy water coolant loop of the RA reactor includes the reactor, circulation pumps, heat exchangers and pipes. The objective of this task was measuring the thermal parameters of the RA reactor during operation. This report contains the results of the experiment, calculations of thermal regime for the outer and inner tubes, maximum temperature of the fuel element, fluid flow rate in the reactor channels, temperature of the coolant and fuel element cladding.

  14. Action plan for the task: Physical measurements at the RA reactor related to VISA-2 project, '0' program, Reactor start-up and measurement of basic parameters of the new core; Plan rada po zadatku: Fizicka merenja na reaktoru RA u vezi projekta VISA-2, '0' program, Pustanje u rad reaktora RA i merenje osnovnih parametara novog jezgra

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Raisic, N [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-07-01

    This report consists of two parts. Part one describes the RA reactor start-up, measurements of thermal neutron flux distribution, measurements of epithermal flux, fast neutron flux distribution, absolute values of both thermal and fast neutron fluxes, calibration of regulating rods, and measurements of neutron flux inside the fuel elements. All the mentioned measurements were done at low power level. Part two includes description of the reactor power increase up to nominal value of 6.5 MW, and measurements of thermal neutron flux distribution under xenon poisoning conditions, measurements of epithermal neutrons, absolute values of both thermal and fast neutron fluxes, and measurements of thermal and epithermal neutron fluxes at the exit of the horizontal experimental channel HK-d.

  15. Radioactivity in the environment of the RA nuclear reactor in Vinca for the period 1977-1980. Material prepared for the RA reactor safety report; Radioaktivnost okoline nuklearnog reaktora RA u Vinci u periodu 1977-1980, Materijal pripremljen za izradu Sigurnosnog izvestaja za reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    Ajdacic, N; Martinc, R [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1980-12-15

    Review of the environmental monitoring data presented in this report is prepared for the RA reactor safety report. These data resulted from four-year monitoring of precipitations and deposited dust. Measurements were done daily. In addition to these data, tables contain mean daily values, total monthly values of beta activities of precipitation from 1977 - 1980. Radioactivity control of the RA reactor environment showed that there was no significant discrepancy compared to the mean values for several years, apart from seasonal variations and meteorological influences. In the period from October 1976 to mid 1978 a number of higher values were recorded probably due to nuclear explosions. During 1979 the general activity level was relatively low, showing increase tendency during 1980.

  16. RA Reactor operation and maintenance (I-IX), part V, Task 3.08/04-06, Refurbishment of the heavy water pumps; Pogon i odrzavanje reaktora RA (I-IX), V Deo, Zadatak 3.08/04-06 Remont teskovodnih pumpi

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M; Milic, J [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    In addition to detailed instructions for maintenance and repair of the heavy water pumps at the RA reactor this document includes nine annexes. They are as follows: cleaning the heavy water pump Avala with distilled water; instructions for repair of the pump CEN-132 (two annexes); list of operating characteristics of the pumps before repair; conclusions of the experts concerning the worn out bearings of the heavy water pump Avala, with the analysis of the stellite layer; report on the completed repair actions on the pumps Avala and CEN-132; report on the measurements done on the pump Avala; and the certificate concerning inspection of the pump.

  17. Theoretical analysis of nuclear reactors (Phase III), I-V, Part IV, Influence of isotopic composition of nuclear fuel on the reactivity with constant flux; Razrada metoda teorijske analize nuklearnih reaktora (III faza) I-IV, IV Deo, Uticaj promene izotopnog sastava goriva na reaktivnost uz konstantan fluks

    Energy Technology Data Exchange (ETDEWEB)

    Pop-Jordanov, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Part one of this report presents a series of differential equations describing the nuclear fuel depletion during reactor operation. This series of differential equations is extended to describe the fission products. This part includes equations for effective multiplication factor k{sub eff} and reactivity {rho} as a function of irradiation {tau}. Part two includes results obtained on the analog computer PACE 231 R, and related to Calder Hall type reactor. Part three covers detailed preparation of the series of equations for solution by using the analog computer. Part four includes the list of references related to this task.

  18. Dispersions of Oxides in Oxide Matrices as High-Temperature Reactor Fuels; Dispersions d'oxyde dans des matrices d'oxyde, utilisees comme combustibles dans des reacteurs a haute temperature; Dispersiya okisej v okislovykh matritsakh v kachestve topliva dlya vysokotemperaturnogo reaktora; Empleo de dispersiones de oxidos en matrices de oxidos, como combustibles para reactores de elevada temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Williams, J. [Atomic Energy Research Establishment, Harwell (United Kingdom)

    1963-11-15

    The potential usefulness of dispersions of PuO{sub 2}, UO{sub 2} and ThO{sub 2} in matrices of BeO, Al{sub 2}O{sub 3}, MgO and SiO{sub 2} is reviewed in terms of fuel integrity and fabrication. Dimensional stability and fission-product retentivity are the two features most important to fuel integrity. Compatibility of the constituents of the fuels with one another and with the coolant will influence dimensional stability, but oxide fuels are well favoured in these respects. Dimensional changes under irradiation will contain contributions from neutron and fission fragment damage to the matrix, from radiation damage to the fissile-fertile phase and from agglomerated fission-product gases. Thermal stresses are also capable of effecting changes in shape. However, information on mechanisms for stress relaxation is too limited to enable any reasonable theoretical assessment of behaviour to be made. Both light irradiation and high burn-up studies of fission-product release from the fissile-fertile oxides have concerned themselves mainly with the gaseous products, chiefly xenon. Data on the release of other fission products is very limited as is also information on the movement of fission products in general through the potential matrix materials. Studies of the permeability of sintered pure oxides indicate that densities of at least 95% theoretical density (maybe even 98%) will be needed to eliminate open porosity in such matrices. A variety of techniques are available for the preparation of fissile-fertile particles, for their coating and for their incorporation into high-density matrices. Work on laboratory-scale fabrication processes is well advanced. (author) [French] L'auteur examine la possibilite d'utiliser des combustibles disperses - PuO{sub 2}, UO{sub 2} et ThO{sub 2} et matrices de BeO, Al{sub 2}O{sub 3}, MgO et SiO{sub 2} - dans des reacteurs a haute temperature, au point de vue de l'integrite du combustible et de sa transformation. La stabilite dimensionnelle et l'aptitude a retenir les produits de fission sont les deux caracteristiques les plus importantes de l'integrite du combustible. La compatibilite des elements constitutifs des combustibles les uns avec les autres et avec le refroidisseur exerce une influence sur la stabilite dimensionnelle, mais les combustibles sous forme d'oxydes presentent beaucoup d'avantages a cet egard. Les variations de dimension sous irradiation ont trois composantes: les dommages causes a la matrice par les neutrons et les produits de fission, les dommages causes par les rayonnements a la phase produit fissile/produit fertile, les effets d'une accumulation de produits de fission gazeux. Les contraintes thermiques peuvent egalement etre a l'origine de modifications de forme. Cependant, les renseignements dont on dispose sur les mecanismes de la relaxation des contraintes sont trop limites pour qu'il soit possible de formuler des appreciations theoriques sur le comportement du materiau. Les etudes sur le degagement des produits de fission provenant d'un melange d'oxydes fissiles et fertiles sous faible irradiation ou pour un taux de combustion eleve, ont porte principalement sur les produits gazeux, notamment le xenon. Les donnees sur le degagement d'autres produits de fission sont tres limitees comme le sont d'ailleurs celles qui ont trait aux mouvements des produits de fission en general a travers les materiaux que l'on peut utiliser pour les matrices. Des etudes relatives a l'etancheite des oxydes purs frittes indiquent qu'il faut atteindre des densites egales a 95% au moins et peut-etre meme a 98% de la densite theorique pour supprimer la porosite ouverte dans de telles matrices. On peut recourir a diverses methodes pour preparer des particules de produits fissiles et fertiles, pour les revetir et pour les incorporer dans des matrices de densite elevee. Les travaux sur les procedes de transformation a l'echelle du laboratoire sont assez avances. (author) [Spanish] El autor examina la posibilidad de utilizar dispersiones de PuO{sub 2}, UO2 y ThO{sub 2} en matrices de BeO, Al{sub 2}O{sub 3}, MgO y SIO{sub 2}, desde el punto de vista de la integridad y elaboracion del combustible. Las dos caracteristicas mas importantes en lo que atane a la integridad del combustible son su estabilidad dimensional y su capacidad de retener los productos de fision. La compatibilidad de los componentes del combustible entre si, y entre ellos y el refrigerante, influye en la estabilidad dimensional, pero en este aspecto, las propiedades de los combustibles en forma de oxido son satisfactorias. A la alteracion de las dimensiones del combustible por irradiacion contribuyen los factores siguientes: deterioracion de la matriz por los neutrones y los fragmentos de fision, deteriorizacion de la fase fisionable/fertil por las radiaciones y gases de los productos de fision acumulados. Las tensiones termicas pueden tambien provocar deformaciones. Los conocimientos que se poseen sobre los mecanismos de atenuacion de tensiones son, sin embargo, insuficientes para permitir un estudio teorico razonable del comportamiento de los materiales. Los estudios sobre la liberacion de productos de fision por los oxidos fisionables/fertiles, realizados tanto en condiciones de irradiacion poco intensa como de elevado grado de combustion, han tratado principalmente de los productos gaseosos, en particular del xenon. Los datos que se poseen sobre el desprendimiento de otros productos de fision son muy escasos, lo mismo que los conocimientos sobre el movimiento de los productos de fision en general a traves de los materiales que podrian utilizarse como matrices. De los estudios realizados sobre la permeabilidad de los oxidos puros sinterizados, se deduce que se deberan alcanzar densidades teoricas de 95%, como minimo, o quiza incluso de 98%, paca eliminar la porosidad de dichas matrices. Se han elaborado una serie de procedimientos para preparar las particulas fisionables/fertiles, para revestirlas y para incorporarlas en matrices de elevada densidad. Los trabajos sobre metodos de elaboracion en escala experimental se hallan bastante avanzados. (author) [Russian] Daetsya obzor vozmozhnosti primeneniya dispersij PuO{sub 2},UO{sub 2}, ThO{sub 2} v matritsakh iz BeO, Al{sub 2}O{sub 3}, MgO i SiO{sub 2} s tochki zreniya sokhraneniya tselostnosti takogo topliva i sposobov ego izgotovleniya. Neizmennost' razmerov i sposobnost' uderzhaniya produktov deleniya yavlyayutsya naibolee vazhnymi svojstvami s tochki zreniya sokhraneniya tselostnosti topliva. Sovmestimost' sostavnykh ehlementov topliva drug s drugom i s teplonositelem okazyvayut vliyanie na neizmennost' razmerov, no v ehtom otnoshenii okislovye vidy topliva obladayut znachitel'nymi preimushchestvami. Na izmenenie razmerov pod dejstviem oblucheniya okazyvayut vliyanie: povrezhdeniya matritsy pod dejstviem nejtronov i oskolkov deleniya; radiatsionnoe povrezhdenie fazy delyashchikhsya veshchestv vosproizvodyashchikh materialov i nakoplenie produktov deleniya v gazoobraznom sostoyanii. Termicheskie napryazheniya takzhe mogut vyzyvat' izmeneniya formy. Odnako svedeniya o mekhanizme relaksatsii napryazhenij slishkom ogranicheny, chtoby mozhno bylo dat' kakuyu-libo priemlimuyu teoreticheskuyu otsenku povedeniyu topliva. Issledovaniya vykhoda produktov deleniya kak v sluchae legkogo oblucheniya, tak i pri sil'nom vygoranii okisej delyashchikhsya veshchestv/vosproizvodyashchikh materialov ogranichivalis' glavnym obrazom gazoobraznymi produktami deleniya, preimushchestvenno ksenonom. Dannye o vykhode drugikh produktov deleniya, a takzhe svedeniya o prokhozhdenii produktov deleniya voobshche cherez vozmozhnye materialy dlya matrits ochen' ogranicheny. Issledovaniya pronitsaemosti chistykh spekshikhsya okisej pokazyvayut, chto dlya ustraneniya otkrytoj poristosti takikh matrits potrebovalos' by dostizhenie plotnostej, dokhodyashchikh po men'shej mere do 95, a to i do 98% ot teoreticheski osushchestvimoj. Dlya izgotovleniya chastits delyashchikhsya veshchestv/vosproizvodyashchikh materialov, dlya ikh pokrytiya i dlya ikh vklyucheniya v matritsy bol'shoj plotnosti imeetsya bol'shoe raznoobrazie metodov. Rabota po vyrabotke tekhnologicheskikh protsessov izgotovleniya v laboratornom masshtabe uzhe dostatochno podvinulas'. (author)

  19. Physical measurements at the RA reactor related to VISA-2, e. Measurements of flux and reactivity during RA reactor operation and exploitation; Fizicka merenja na reaktoru RA u vezi projekta VISA-2, e. Pracenje fluksa i reaktivnosti u toku eksploatacije reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-05-15

    This report includes the following: characteristics of neutron flux in vertical experimental channels of the RA reactor; characteristics of neutron flux in VISA-2 channels; reactivity changes in the reactor during VISA-2 irradiation including calibration of control rods.

  20. Accident conditions analysis of spent fuel storage pool RA research reactor in Vinca; Analiza udesnih stanja u odlagalistu isluzenog goriva istrazivackog rektora RA u Vinci

    Energy Technology Data Exchange (ETDEWEB)

    Jovic, V; Jovic, L [Institute of Nuclear Sciences VINCA, Belgrade (Serbia and Montenegro)

    2000-07-01

    Based on Safety analysis of the spent fuel pool RA research reactor in Vinca, conditions and possibilities accident sequences in present configuration storage facility are considered (author) [Serbo-Croat] Na osnovu Analize sigurnosti odlagalista isluzenog goriva istrazivackog reaktora RA u Vinci razmatraju se uslovi i mogucnosti pojave udesnih stanja u postojecoj konfiguraciji odlagalista (author)

  1. RA research nuclear reactor - Annual report 1985; Istrazivacki nuklearni reaktor RA - Izvestaj za 1985. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1985 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  2. RA Research reactor, Annual report 1986; Istrazivacki nuklearni reaktor RA - Izvestaj za 1986. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1986 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  3. Annual report of the maintenance division for 1965; Godisnji izvestaj Odelenja odrzavanja za 1965. g

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The personnel of the Division is organized in groups, each responsible for a number of tasks related to maintenance of reactor mechanical structures, electric equipment, electronic equipment. According to the action plan for 1965 the division for RA reactor maintenance the main activities were: planned maintenance of the reactor components, planned repair of the main components, indispensable repairs during reactor operation, repair during planned shutdown periods and tasks related to improvement of operation components and systems. Quite a significant number of failures was related to electronic equipment resulting from failures of thermometers in the heavy water system due to vibrations of the pumps. A number of spare parts and tools were produced needed for maintenance of reactor components, as well as instruments for control and calibration of reactor measuring devices. [Serbo-Croat] Odelenje odrzavanja reaktora RA organizovano je po grupama, od kojih je svaka odgovorna za odrzavanje pojedinih delova sistema: masinske opreme, elektricne opreme, elektronskih uredjaja. Prema planu rada za 1965. godinu Odelenja za odrzavanje reaktora RA osnovne aktivnosti bile su: planirano odrzavanje komponenti reaktora, planirane popravke osnovnih komponenti, neodlozne popravke tokom eksploatacije i u toku planiranih zaustavljanja kao i usavrsavanje opreme i sistema. Znatan broj kvarova pojavio se na elektronskoj opremi usled kvarova termometara u sistemu teske vode usled vibracija koje izazivaju pumpe. Odredjeni broj delova izradjen je za potrebe odrzavanja komponenti reaktora, kao i instrumenata za kontrolu i kalibraciju mernih uredjaja.

  4. Present Status of Nitrogen Fixation by Reactor Radiation; Etat Actuel des Recherches sur l'oxydation directe de l'azote sous irradiation dans des reacteurs; Sovremennoe sostoyani opytov po okisleniyu azota izlucheniem iz reaktorov; Estado actual de las investigaciones sobre fijacion del nitrogeno por irradiacion en reactores

    Energy Technology Data Exchange (ETDEWEB)

    Harteck, P; Dondes, S [Rensselaer Polytechnic Institute, Troy, NY (United States)

    1960-07-15

    sistema funktsioniruet v nastoyashchee vremya v Brukkhejvenskom reaktore v zakrytom konture. Dayutsya dannye o vliyanii temperatury, davleniya, proportsii smesi i intensivnosti izlucheniya, chto mozhet byt' ispol'zovano dlya proektirovaniya budushchego khimiko-yadernogo reaktora. Sushchestvuyushchaya sistema rabotaet pri davlenii v 10 atmosfer i pri .temperature v 150''oC. Temperatura zavisit ot ehnergii rasshchepleniya chastits, osvobozhdaemoj v steklyannom volokne, i ot ognestojkosti zakrytogo kontura. V nastoyashchee vremya stroitsya drugoj zakrytyj kontur, kotoryj dolzhen rabotat' pri davlenii v 50-75 atmosfer i pri temperature v 600''oC. EHti zakrytye kontury dayut vozmozhnost' sudit' o parametrakh potochnykh sistem, vklyuchaya povedenie produktov rasshchepleniya, vypuskaemykh v gazovyj potok. Slozhnaya kinetika okisleniya azota opisyvaetsya na trekh stadiyakh : nachal'nye reaktsii v sisteme; reaktsii posle obrazovaniya nekotorogo kolichestva okislennogo azota i, nakonets, kinetika pri ustanovlenii ravnovesiya izlucheniya. Rassmatrivayuts ya usloviya obrazovaniya N{sub 2}0{sub 5}, N{sub 2}0{sub 4} i O{sub 3}, a takzhe ikh vliyanie na ves' protsess. (author)

  5. Simulasi Sifat Fisis Model Molekuler Dinamik Gas Argon dengan Potensial Lennard-Jones

    Directory of Open Access Journals (Sweden)

    Wira Bahari Nurdin

    2014-01-01

    Full Text Available DOWNLOAD PDFTelah  dilakukan  pembuatan  dan  pengujian  suatu  simulasi  tentang  sifat  fisis  gasargon  dengan  menggunakan  dinamika  molekuler  menggunakan  potensial Lennard-Jonesdalam sistem terisolasi (ensemble mikrokanonik. Jumlah molekul, energi total sistem danluas  kotak  simulasi  telah  divariasikan.  Untuk  menghitung  perubahan  posisi  digunakanalgoritma Verlet. Sifat fisis yang ditentukan dalam simulasi adalah temperatur dan energitotal  sistem  untuk  menentukan  adanya  fase  transisi.  Dari  hasil  simulasi,  terdapatkesesuaian antara simulasi dengan gas argon dan tidak diperoleh adanya fase transisi.Kata kunci: Simulasi dinamika molekul, argon, potensial Lennard-Jones, ensemblemikrokanonik, algoritma Verlet

  6. LANDASAN KONSEPTUAL PERENCANAAN DAN PERANCANGAN AIKIDO TRAINING CENTER DI YOGYAKARTA

    OpenAIRE

    WAHYUNINGTYAS, GRAZIA SETJO

    2016-01-01

    tindak kejahatan yang terjadi di masyarakat pada masa kini. Membekali diri dengan ilmu beladiri defensif dan dapat dipelajari oleh segala usia merupakan salah satu cara untuk menanggulangi ancaman kejahatan tersebut. Aikido memperkenalkan diri sebagai beladiri yang cocok untuk dipelajari segala usia serta dapat menjadi sarana untuk berlatih dalam dinamika kehidupan. Di Yogyakarta kondisi dojo masih sangat kurang dalam mewadahi kegiatan latihan dan seminar serta belum membantu aikidoka dalam m...

  7. Warsaw Pact: The Question of Cohesion. Phase II, Volume 1. The Greater Socialist Army: Integration and Reliability,

    Science.gov (United States)

    1984-02-01

    235 CHAPTER 9 - Military Political Socialization : Themes and Effectiveness .................................... 268 CHAPTER 10 - Factors...by comprehensive political socialization efforts,6 the last two also coordinated by Moscow. An in-depth analysis of the national attitudes of all... Political Socialization ...," below. See Chapter 5, "Historical Precedents...," below. 8 See, for example, S.I. Bruk and M.I. Kabuzan, "Dinamika chislennosti

  8. Bibliography of Soviet Laser Developments, Number 48 July-August 1980.

    Science.gov (United States)

    1981-07-01

    80, 8Ye4) IV. SOURCE ABBREVIATIONS (CIRC Codens) APP (ATPLB) Acta physica polonica * BWAT (BWATA) Biuletyn Wojskowej akademji technicznej J...Ois (OPSPA) Optika i spektroskopiya OMP (OPMPA) Optlko-mekhanicheskax’a promysh lennost’ PSS (PSSAB) Physica Status Solidi (A). Applied Research PTE...Dinamika izluchayushchego gaza. no. 3, Moskva, 1980. Sb23 Acta Universitatis Palackianae Olomucensis. Facultas rerum naturalium. v. 61, Olomouc, 1979

  9. Annual report of the mechanics group; Godisnji izvestaj masinske grupe

    Energy Technology Data Exchange (ETDEWEB)

    Bratic, A [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    Planned maintenance and repair of fundamental reactor systems was done during planned shut down periods in 1965. For that reason there was no interruption of reactor operation caused by failures of the equipment. Planned repairs were concerned with: heavy water system, gas system, technical water system, distillation system, graphite cooling system, ventilation and heating systems and emergency power supply system in the reactor building. This report includes as well, the list of unplanned repairs. [Serbo-Croat] U 1965. godini vrsen je planski remont osnovnih agregata reaktorskih sistema u planiranim periodima stajanja reaktora, te nije doslo ni do kakvih duzih prekida rada reaktora usled kvarova na opremi. Planski remont obuhvatio je: sistem teske vode, gasni sistem, sistem tehnicke vode, sistem destilacije, sistem hladjenja grafita, sistem ventilacije i grejanja, transportne uredjaje, dizel agregata. Ovaj izvestaj sadrzi i listu vanplanskih remonta i popravki.

  10. Annual report of the group for maintenance of electrical equipment; Godisnji izvestaj elektro grupe

    Energy Technology Data Exchange (ETDEWEB)

    Rajic, M [Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis remontnih i revizionih radova na elektroopremi reaktora RA izvrsenih prema godisnjem planu u periodima kada reaktor nije radio. Vanplanski poslovi ukljucujuci popravke elektroopreme su takodje deo ovog izvestaja.

  11. RB Research nuclear reactor, 30 years of operation; Istrazivacki nuclearni reaktor RB, povodom 30 godina rada

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M; Stefanovic, D [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1988-06-15

    Paper describes utilization, modifications and changes of construction and control-safety systems done at the RB reactor during 30 years of operation. Experiments performed at the reactor are summarized, new reactor equipment is described and the future plans are shown. Rad prikazuje eksploataciju reaktora RB tokom 30 godina rada, modifikacije i izmene u konstruktivnim i upravljacko-sigurnosnim sistemima. Sumirani su eksperimenti izvedeni na njemu, prikazana je nova oprema i planovi za buduci rad.

  12. Measurement of the effective resonance integral of natural uranium; Merenje efektivnog rezonantnog integrala prirodnog urana

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, V; Kocic, A [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-12-15

    Good understanding of the nuclear properties of the materials in the reactor core is essential for reactor operation. One of the fundamental properties is the resonance absorption of the fuel, which is directly included in the reactor calculation through resonance escape probability and influences the choice of the materials quality in the core. This paper describes the measurement of resonance absorption integral of the natural uranium as a function of the S/M ratio. Improved experiment planning and analysis of results, as well as improvement of the ROB-1 reactor oscillator device related to the interpretation of results and decrease of reactor drift variations during measurement enabled higher precision of results compared to previous experiments. Poznavanje osobina nuklearnih karakteristika materijala koji ulaze u jezgro nuklearnog reaktora predstavlja bitan faktor u njegovom rezimu rada. Jedna od osnovnih je svakako rezonantna apsorpcija goriva, cija velicina - preko faktora rezonantnog izbegavanja - direktno ulazi u proracun nuklearnih reaktora i utice na izbor kvaliteta materijala koji ga sacinjavaju. U radu se opisuje merenje rezonantnog apsorpcionog integrala prirodnog urana u funkciji odnosa S/M. Bolja postavka eksperimenta i interpretacija rezultata, s jedne strane, i poboljsanje uredjaja reaktorskog oscilatora ROB-1 /1/ u pogledu analize podataka i smanjenja promene drifta reaktora u toku merenja, s druge strane, daju znacaj ovom radu u pogledu dobijanja preciznijih rezultata u odnosu na ranije /2/ (author)

  13. Annual report of the group for maintenance of electronic equipment; Godisnji izvestaj elektronske grupe

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, B [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging. [Serbo-Croat] Remontni radovi na opremi sistema za upravljanje i sigurnost reaktora RA ravnomerno su rasporedjeni tokom cele godine i obavljaju se prema planu remonta. Izvrsen je citav niz popravki elektronske instrumentacije, kao i zamena komponenti i elektronskih cevi. Sve kontrole ispravnosti i kalibracije lanaca za upravljanje i zastitu reaktora redovno su vrsene prema potrebi i u vezi sa radnim stanjem reaktora prema uputstvu za ove operacije. Pregledi, remonti i popravke kao i radne karakteristike pojedinih elemenata kao i kompletnih instrumentalnih kontrolnih lanaca u toku 1965. godine pokazali su da su sistemi upravljanja i sigurnosne zastite jos u dobrom stanju. Nesto veci broj kvarova usled starenja elektronskih cevi je normalna posledica starenja opreme i instrumentacije.

  14. KAJIAN STRUKTUR SOSIAL MASYARAKAT NELAYAN DI EKOSISTEM PESISIR

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    Edi Susilo

    2012-05-01

    Full Text Available Abstrak Tujuan penelitian ini adalah menganalisis perubahan sosial masyarakat dan dinamika kapasitas ruang dan titik kritis struktur sosial dalam ekosistem pesisir. Penyebab utama perubahan struktur adalah masuknya unsur-unsur pembentuk struktur dari luar (individu, sistem, atau karena meningkatnya akses masyarakat terhadap perubahan di lingkungan lokal, maupun di lingkungan sosial luarnya. Dinamika kapasitas ruang struktur sosial di ekosistem pesisir Karanggongso selama masa pengamatan dapat dijelaskan melalui dua indikator penting, obyektif dan subyektif. Titik kritis ada yang berlaku secara umum, dan ada yang berlaku secara khusus. Penelitian ini menjelaskan bahwa teori evolusi berpeluang besar untuk disintesakan dengan teori-teori lain seperti teori konflik, ekuilibrium, dan teori timbul –tenggelam. Proses sistesa ini merupakan langkah opearasional pemetaan teori skematis yang dilakukan oleh Appelbaum. Dinamika struktur sosial sangat penting diketahui oleh pemeritah dan LSM, yang mana mereka memiliki perencanaan pembangunan dalam masyarakat nelayan. Kata kunci: struktur sosial, evolusi, kapasitas ruang, titik kritis ABSTRACT Research aim is to analyse any social changes and dynamic of space capacity and critical point of social structure in  coastal ecosystem. The main factor of  structural change is external factor of structural formation (individu , system, or increase of community access to the change of local social environment, and external social environment. Dynamics of space capacity of social structure in coastal ecosystem of Karanggongso during periode of research can be explained through the two indicators, objective and subjective. There are a general critical point and a special critical point. This results explain that a evolution theory  suggest a high possibility to be synthesized with any other theories, e.g. a conflict theory, an equilibrium theory,   and a “timbul-tenggelam” theory. The synthesis process is an

  15. Proverbs as ethnolinguistic heritage

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    Pejović Anđelka

    2014-01-01

    Full Text Available In this paper we have based our analysis on proverbs of Serbian and Spanish language in order to demonstrate the role of these linguistic and cultural constructions in the ethnolinguistic investigation. Relativism observed in them, often reflected as contradictions, is of a huge significance for the ethnolinguistic analysis, since it shows or it might show the ways in which certain society adjust or opposes to the changes, how it reacts, whether it changes only on the surface, or its deep and inside values change as well. [Projekat Ministarstva nauke Republike Srbije, br. 178014: Dinamika struktura savremenog srpskog jezika

  16. Factors Influencing A Customer-Service Culture In A Higher Education Environment

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    Jacques Liebenberg

    2004-11-01

    Die hoëronderwysomgewing is besig om betekenisvol te verander, en die fokus is besig om na mededingendheid en kliëntesorg te verskuif. Die rol van organisasiekultuur en werksbevrediging in die lewering van hoëgehaltekliëntediens is in hierdie studie ondersoek. Daar is aanduidings dat daar ’n verband tussen organisasiekultuur en leerdertevredenheid is, maar dit het geblyk dat daar nie ’n betekenisvolle verband tussen werksbevrediging en leerdertevredenheid is nie. ’n Evaluering van ’n voorgestelde leerdertevredenheidsmodel het interessante dinamika wat die verhouding tussen die kerndimensies van die studie beïnvloed, aan die lig gebring.

  17. RESOLUSI KONFLIK ANTARA MASYARAKAT LOKAL DENGAN PERUSAHAAN PERTAMBANGAN (STUDI KASUS: KECAMATAN NAGA JUANG, KABUPATEN MANDAILING NATAL, PROVINSI SUMATERA UTARA

    Directory of Open Access Journals (Sweden)

    Dian Taufik Ramadhan

    2016-03-01

    Full Text Available Konflik antara PT. SMM, masyarakat Kecamatan Naga Juang, dan Pemerintah Kabupaten Mandailing Natal, berakar pada hubungan ekonomi yang menyangkut pengelolaan dan pemanfaatan komoditi emas. Penelitian ini berupaya melihat relasi di antara ketiga stakeholder tersebut. Melihat hal-hal yang menjadi sebab konflik, mengurai struktur dan dinamika konfik serta merumuskan strategi resolusi konflik. Hasil penelitian menunjukkan, dimensi sebab konflik disebabkan oleh dimensi ekonomi atas pengelolaan dan pemanfaatan komoditi emas, dimensi struktur dan dinamika sangat dipengaruhi oleh peran aktor yang mendorong peningkatan ketegangan dan eskalasi konfik. Resolusi konflik yang dirumuskan yaitu strategi akomodatif. Strategi akomodatif adalah strategi yang mengakomodir kepentingan dan espektasi dari dua stakeholder kunci yaitu, Pemkab Madina dan masyarakat Kecamatan Naga Juang. Conflict between PT. SMM, Naga Juang district community, and the government of Mandailing Natal Regency, rooted in economic relations that concern to the management and utilization of gold’s commodity.  This research attempt to see the relationship between the three stakeholders, see the causes of conflict, analyze the structure and dynamics of conflict, and also formulate strategies of conflict resolution. The results showed, the economic dimension of the conflict caused by the management and utilization of gold commodity, structural and dynamics dimensions are strongly influenced by the role of actors which encouraged tension escalation and conflicts. The formulation of conflict resolution is an accommodative strategic which is a strategy that accommodates the interests and expectations of two key stakeholders, namely Mandailing Natal regencial government, and Naga Juang district community.

  18. Audit Internal Universitas X: Suatu Refleksi

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    David Adechandra Ashedica Pesudo

    2017-04-01

      Penelitian ini bertujuan untuk menyediakan bukti empiris tentang dinamika beroperasinya fungsi audit internal dalam sebuah universitas swasta dengan mendeskripsikan berbagai faktor yang mempengaruhi keefektifan fungsi audit internal di sebuah universitas. Secara khusus, studi ini mendeskripsikan kondisi berbagai faktor yang mempengaruhi keefektifan fungsi audit internal dalam organisasi nirlaba yang diidentifikasi oleh Ahmad et al.., (2009 dalam suatu konteks organisasi sebuah universitas swasta. Studi ini menggunakan strategi penelitian studi kasus dengan menggunakan pendekatan kualitatif untuk menganalisis data. Wawancara mendalam dengan berbagai pihak yang memiliki pengetahuan tentang kegiatan audit internal di universitas yang menjadi studi kasus menjadi sumber utama data untuk studi ini.  Penelitian ini menunjukkan bahwa dinamika beroperasinya fungsi audit internal universitas swasta yang menjadi studi kasus dipengaruhi oleh berbagai faktor. Beroperasinya fungsi audit internal di organisasi dipengaruhi oleh sejumlah faktor yang bersifat mendukung  yaitu jumlah staf audit internal, kerjasama dari auditee, kompetensi/pengetahuan tentang teknik audit, tindakan pada temuan audit dan rekomendasi oleh auditee/manajemen, dan pengalaman audit. Sementara itu, sejumlah faktor bersifat tidak mendukung  bagi beroperasinya fungsi audit internal, yaitu komitmen dari manajemen puncak, pelatihan, independensi, perubahan dalam organisasi divisi audit internal, persepsi dari auditee terhadap fungsi audit internal, dan sumber daya.

  19. PERGULATAN TEOLOGI SALAFI DALAM MAINSTREAM KEBERAGAMAAN MASYARAKAT SASAK

    Directory of Open Access Journals (Sweden)

    Faizah Faizah

    2012-12-01

    Full Text Available Abstract: The Salafi movement has recently spread so widely in Indonesia that it has reached rural communities. In that context, its contact with local beliefs and practices produces a dynamic and creative tension between them. This paper will explore the contact dynamics by photographing wrestle of Salafi’s theological movement and beliefs in the mainstream of theological beliefs of local Sasak society of Lombok. The authors found that local knowledge that expressed through practicing several ceremonies associated with the human life-cycle from moment of human birth to death events considered by the Salafi as unauthentic element of Islam called heretic to which the Salafi has to carry out purification. That potential conflict between the Sasak and Salafis, requiring mutual respect and tolerance among them.Abstrak: Gerakan Salafi akhir-akhir ini semakin meluas penyebarannya di Indonesia hingga mencapai wilayah-wilayah pedesaan. Dalam konteks itu persentuhannya dengan keyakinan dan praktek masyarakat lokal menciptakan dinamika dan ketegangan kreatif di antara mereka. Tulisan ini akan mengupas dinamika itu dengan memotret pergulatan paham teologi gerakan Salafi itu di tengah mainstream keyakinan keberagamaan masyarakat Sasak, Lombok. Penulis menemukan bahwa keyakinan lokal yang diekspresikan melalui penyelenggaraan beberapa upacara yang berhubungan dengan lingkaran hidup manusia dari peristiwa kelahiran hingga kematian dipandang oleh kaum Salafi sebagai unsur baru yang disebut bid’ah dan keharusan bagi Salafi untuk melakukan purifikasi. Hal itu berpotensi menimbulkan konflik antara Sasak dan Salafi, sehingga diperlukan sikap saling menghargai dan tenggang rasa di antara mereka.

  20. Metamorfosis Gerakan Sosial Keagamaan: Antara Polemik, Desiminasi, Ortodoksi, dan Penerimaan terhadap Ideologi Lembaga Dakwah Islam Indonesia (LDII

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    Limas Dodi

    2017-05-01

    Abstrak: Lembaga Dakwah Islam Indonesia (LDII dikonotasikan sebagai penerus dari perjuangan pemikiran Islam Jamaah, sehingga muncul labeling sesat oleh pihak-pihak tertentu. Meskipun banyak indikasi yang mengarahkan persepsi demikian, namun pada hakikatnya LDII merupakan suatu organisasi bentukan pemerintah Orde Baru yang ditugaskan untuk membenahi penyelewengan ajaran Islam yang dilakukan oleh kelompok Islam Jamaah. Tulisan ini berusaha untuk mengalisa sejauh mana metamorfosis (dalam arti; melepaskan dinamika masa lalu yang dianggap menyesatkan, dan kemudian memakai paradigma baru gerakan sosial keagamaan LDII dipengaruhi oleh Islam Jamaah, antara polemik, desiminasi, ortodoksi, dan penerimaan terhadap Ideologi-nya. Keterikatan historis dan kultural LDII dengan Islam Jamaah menyebabkan kelompok keagamaan yang lain masih bersikukuh pada keputusan tentang kesesatan ajaran LDII. Gerakan sosial memberikan gambaran bahwa gerakan itu muncul dan langgeng dari berbagai macam bentuk dan pola-pola. Dalam hal ini terdapat 2 pola yang mempengaruhi: State-oriented Islamic movement dan society-oriented Islamic movement, ini muncul dalam dua pola. (1 Everyday life-based. (2 Inward-oriented contemplative movements. Dinamika dan strategi LDII dengan birokrasi pemerintahan ataupun kelompok keagamaan lainnya merupakan jalinan hubungan untuk memposisikan diri sebagai kelompok yang sejajar sebagai kelompok ortodoks.

  1. Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Petrovic, M; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-12-15

    .) upoznavanje eksploatacionih karakteristika reaktora TVRS sa 80% obogacenim gorivom, kao i iskustva u vezi sa koriscenjem tog goriva u reaktoru TVRS u Moskvi; b.) upoznavanje sa elementima sigurnosnih analiza u vezi sa uvodjenjem i kriscenjem tog goriva u reaktoru TVRS kao i c.) razmena gledista o programu prevodjenja reaktora RA na novo 80% obogaceno gorivo. U izvestaju su prikazani rezultati ove posete. Osnovni zakljucci do kojih se doslo jesu: a.) poseta je bila korisna i pored toga sto na neka pitanja nije dobijen odgovor; b.) posle obrade dobijenih informacija, posle sticanja prvih iskustava o koriscenju novog goriva u reaktoru RA kao i posle donosenja definitivnog suda o ravnoteznom rezimu reaktora RA sa novim gorivom, bilo bi veoma korisno da se izvrsi jos jedna poseta Institutu u Moskvi; c.) novo disperziono gorivo je mnogo pouzdanije u eksploataciji od starog 2% obogacenog metalnog goriva (kakvo je sada u reaktoru RA); d.) nije bilo primedbi sa aspekta sigurnosti na nas program prevodjenja (prelazni rezim) reaktora RA na novo gorivo; e.) zatrazice se dopunske informacije o maksimalnom dopustivom stepenu izgaranja 80% obogacenog disperzionog goriva i po potrebi izvrsice se blagovremena revizija predvidjenog optimalnog ravnoteznog rezima izgaranja za reaktor RA (baziranog na maksimalnom izgaranju goriva koje omogucuju parametri reaktora RA); f.) metodologija termickog proracuna gorivnih kanala, koja se primenjuje na reaktor RA ocenjena je kao ekvivalentna postupku koji se primenjuje za proracun kanala reaktora TVRS u Moskvi (author)

  2. Report on the activity of the RA reactor operation for the period from July 1 1961 - Sept. 30 1961; Tromesecni izvestaj za period od 1.VII do 30.IX 1961. g

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Laboratorija za eksploataciju reaktora RA, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-09-15

    During the reporting period the reactor was permanently ready for operation and responding to the demands of the experimenters. The reactor was operating for 408.5 hours at power levels from 50 - 5000 kW, or 1985 MWh in total, burnup of the first batch of fuel was 22.55%. Reactor core was made of 56 fuel channels. Activities related to construction of new and improvement of the existing equipment was continued in order to enable safe operation and successful utilization of the RA reactor. Exchange of the electronic tubes was continued in order to increase the stability of the reactor control and reactor protection systems. About 65% of tubes planned to be exchanged this year was done. Cooperation with the CEN Saclay, France related to construction of experimental loops VISA-1 and VISA-2 was continued as well as cooperation with Poland concerned with exchange of experts. The problem of lack of properly trained staff was nor solved. [Serbo-Croat] U izvestajnom periodu reaktor je uvek bio spreman za rad i odgovarao je zahtevima eksperimentatora. Reaktor je radio 408,5 casova na snagama od 50-5000 kW, odnosno ukupno 1985 MWh, pri cemu je ukupan utrosak prve sarze goriva bio 22,55%. Jezgro reaktora bilo je sacinjeno od 56 tehnoloskih kanala. Radi bezbednijeg pogona i sto uspesnije eksploatacije reaktora RA nastavljeno je sa radovima na realizaciji novih i poboljsanju postojecih uredjaja. U cilju povecanja stabilnosti elektronskih instrumenta u sistemu upravljanja i zastiti reaktora nastavljeno je sa zamenom elektronskih cevi, do sada je zamenjeno oko 65% radova predvidjenih za ovu godinu. Nastavljena je saradnja sa nuklearnim centrom u Saclay, Francuska na izradi petlje VISA-1 i VISA-2 i saradnja sa Poljskom u razmeni strucnjaka. Problem nedostatka kadrova nije resen.

  3. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

    Cupac, S; Vukadin, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    This annex covers: description of the organisational structure of the service, safeguard activities, increase of reactor operation capability, dosimetry and radiation protection tasks and an overview of the the activities of this Service. During 1992, there have been 12 safeguard IAEA inspections. Each time inspection covered fresh fuel, every third inspection included control of the spent fuel storage pool, and once during the fuel inventory control the reactor core was included. With the aim of increasing the operating capabilities besides improvement of experimental devices, construction of the experimental loop with separate cooling system was started. It is planned, as well to improve operating capabilities of horizontal experimental channels by purchasing neutron diffractometer, constructing three-crystal neutron spectrometer, application of three-crystal neutron spectrometer from Krakow, and using the time-of flight spectrometer constructed in the Institute. This Annex describes the possible activities for neutron radiography and isotope production, and includes radiation protection data. [Serbo-Croat] Ova prilog sadrzi opis organizacije tehnoloske sluzbe, 'safeguard' aktivnosti, moguce poboljsanje eksploatacionih mogucnosti reaktora, tehnicke zastite od zracenja i dozimetrije, kao i pregled svih poslova Sluzbe. Tokom 1992. bilo je 12 'safeguard' IAEA inspekcija. Tokom svake inspekcije kontrolisano je sveze gorivo, svaka treca je ukljucila kontrolu bazena za odlezavanje ozracenog goriva, a jednom je kontrolisano i jezgro reaktora RA. Sa ciljem da se poboljsaju operativne mogucnosti reaktora, pored poboljsanja eksperimentalnih uredjaja, pocela je i izgradnja reaktorske petlje sa sopstvenim hladjenjem. Planirano je da se poboljsaju i operativne mogucnosti horizontalnih eksperimentalnih kanala, sto je ucinjeno kupovinom neutronskog difraktometra, izgradnjom trikristalnog neutronskog spektrometra, koriscenjem trikristalnog neutronskog spektrometra koji je

  4. Operational report, Advantages of gradual introducing of highly enriched fuel into the RA reactor core from economic aspect and users needs; Radni izvestaj, Prednost postupka parcijalnog uvodjenja visokoobogacenog goriva u reaktor RA sa aspekta ekonomicnosti i potreba korisnika

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-10-14

    The possibility of increasing the neutron flux in the RA reactor was considered for a number of years. The possibilities of reactor reconstruction are not realistic and they should be disregarded. The possibility that remains is to achieve higher neutron flux by improving the fueling scheme and above all by introducing highly enriched fuel into the reactor core. Decision to purchase highly enriched fuel was quicker due to the fact that the 2% enriched uranium fuel is not fabricated any more. There are two procedures for exchanging the fuel in the reactor core: a) removal of partially spent 2% enriched fuel and formation of the core with fresh highly enriched fuel; b) gradually introducing the new fuel into the existing RA reactor core according to a special transfer regime. This report includes some comparative analyses of these two procedures from both economic point of view and the needs of users, as well as some technical conditions. These results are in favour of gradual introducing of new fuel into the reactor core. relevant direct savings amount to 3 000 000 dinars. Some of the most important advantages cannot be estimated in this way. This report does not cover the safety analyses results which are presented in a series of other papers. [Serbo-Croat] Vec vise godina razmatra se mogucnost za povecanje neutronskog fluksa u reaktoru RA. Mogucnosti za rekonstrukciju reaktora RA u tom smislu su minimalne i realno ih treba odbaciti. Prema tome preostaje da se povecanje neutronskog fluksa postigne usavrsavanjem seme izmene goriva, a pre svega uvodjenjem goriva sa visokim stepenom obogacenja u reaktor RA. Donosenje odluke o nabavci visokoobogacenog goriva i njegovom uvodjenju u reaktor ubrzano je i cinjenicom da se staro 2% obogaceno uransko gorivo vise ne proizvodi. Postoje dva postupka za prevodjenje reaktora na ovo gorivo: a) Uklanjanjem poluistrosenog 2% obogacenog goriva iz reaktora i formiranjem jezgra iskljucivo od svezeg visokoobogacenog goriva, b

  5. RA research reactor - properties and experimental capabilities; Istrazivacki reaktor RA - Tehnicke karakteristike i eksploatacione mogucnosti

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1978-05-15

    The brief survey of the Reactor RA exploitation experience, as well as the reactor equipment state, after 18 years of operation is presented. The results of efforts spent on reactor characteristics improvement in order to ensure safe and reliable reactor operation for next 15-20 years, are described. Prikazani su fragmenti iz eksploatacije reaktora kao i stanje opreme, posle 18 godina rada. Na kraju je dat prikaz sta je preduzeto i sta se preduzima da se poboljsaju karakteristike i poveca sigurnost i bezbednost rada za sledecih 15-20 godina.

  6. Program of critical experiment and measurements at the RA reactor; Program kriticnih eksperimenata i merenja na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-14

    Program described in this document describes in detail the following experiments: critical experiments with two reactor core lattices with 38 and 44 fuel channels, initial heavy water level being 1300 mm, criticality is achieved by adding heavy water; preliminary analysis of heavy water quality and verification of the fuel isotopic contents; experiment with the initial core which contains 56 fuel channels with maximum heavy water level according to the Russian proposal; measurement of neutron flux by Dy and In foils; measurement of reactivity excess dependent on the heavy water level and number of fuel rods; measurement of reactor period for determined reactivity change; measurement of moderator temperature coefficient; measurement of absolute flux. [Serbo-Croat] Program sadrzan u ovom dokumentu opisuje detaljno sledece eksperimente: kriticni eksperiment sa dve konfiguracije jezgra reaktora, sa 38 i 44 gorivna kanala, pocetni nivo teske vode je 1300 mm, kriticnost se dostize dodavanjem teske vode; prethodno izvrsenom analizom teske vode i proverom izotopskog sastava goriva; eksperiment sa pocetnom resetkom koja prema ruskom predlogu sadrzi 56 gorivnih kanala i maksimalnom visinom teske vode; merenje raspodele neutronskog fluksa folijama Dy i In; kalibracija regulacionih sipki; merenje viska reaktivnosti sa promenom visine nivoa teske vode i promenom broja sipki; merenje periode reaktora za odredjenu promenu reaktivnosti; merenje temperaturnog koeficijenta za vodu; merenje apsolutnog fluksa.

  7. Methods for measuring nuclear properties of materials, Safety coefficient method and measurement of effective absorption coefficient of graphite by safety coefficient method; Razvijanje metoda merenja nuklearnih karakteristika materijala, Razrada metode koeficijenta opasnosti i merenje efektivnog apsorpcionog preseka grafita metodom koeficijenta opasnosti

    Energy Technology Data Exchange (ETDEWEB)

    Maglic, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1962-11-15

    Reactivity of a reactor depends on production, absorption and leaking of neutrons. Change of absorption causes reactivity change, and this fact is used for determining the neutron absorption cross section for the sample inserted in the reactor core. Method for determining the absorption cross section based on reactivity change is called method of safety coefficient. Measurements of neutron absorption cross section for graphite was done in the RA reactor vertical experimental channel VK-5. taking into account the results obtained for five types of graphite this method is considered to be reliable for use. Comparison of nuclear properties of different types of graphite was done as well. Reaktivnost reaktora zavisi od proizvodnje neutrona, apsorpcije i isticanja neutrona. Promena apsorpcije izaziva promene reaktivnosti reaktora pa se ova osobina koristi za odedjivanje neutronskog apsorpcionog preseka uzorka koji se unosi u reaktor. Metoda merenja apsorpcionog preseka na bazi promene reaktivnosti nazvana je metodom koeficijenta opasnosti. Merenje apsorpcionog preseka grafita uradjeno je na reaktoru RA u vertikalnom eksperimentalnom kanalu VK-5. S obzirom na rezultate koji su dobijeni za pet vrsta grafita moze se smatrati da je opravdano koriscenje ove metode. Izvrseno je i poredjenje nuklearnih osobina pomenutih tipova grafita.

  8. RA Research reactor, Annual report 1972; Istrazivacki nuklearni reaktor RA - Izvestaj za 1972. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1972-12-15

    During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO{sub 2} capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system. [Serbo-Croat] Ukupni rad Reaktora RA je u 1972. godini iznosio je 31151 MWh odnosno 3,8% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 381 korisnika od cega 340 iz Instituta i 41 za korisnike izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i

  9. Research nuclear reactor RA - Annual Report 1991; Istrazivacki nuklearni reaktor RA - Izvestaj za 1991. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Construction of some support elements is almost finished by the local staff. The Institute has undertaken this activity in order to speed up the ending of the project. If all the planned instrumentation would not arrive until the end of March 1992, it would not be possible to start the RA reactor testing operation in the first part of 1993, as previously planned. In 1991, 53 staff members took part in the activities during 1991, which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1991. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci

  10. DAMPAK PROGRAM RESITASI TERHADAP PERUBAHAN KONSEPTUAL MAHASISWA PADA TOPIK HUKUM III NEWTON

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    Ida Bagus Rini Jayanti

    2016-02-01

    Melalui penelitian ini telah dikembangkan program resitasi berbantuan komputer berisi 9 soal-soal konseptual dalam bentuk pilihan ganda beserta balikan langsung. Penelitian ini dimaksudkan untuk menyelidiki dampak program tersebut terhadap penguasaan konsep dan perubahan konsep mahasiswa mengenai hukum III Newton. Data diambil melalui pretes berupa tes pilihan ganda yang diberikan setelah pembahasan topik kinematika (satu dan dua dimensi dan dinamika partikel (hukum-hukum Newton tentang gaya dan gerak dan postes diberikan setelah menggunakan program resitasi. Program digunakan mahasiswa selama seminggu secara offline. Subjek penelitian terdiri atas 35 mahasiswa tahun pertama Program Studi Pendidikan Fisika Universitas Negeri Malang yang sedang menempuh mata kuliah Fisika Dasar I. Hasil penelitian ditemukan bahwa penguasaan konsep mahasiswa secara keseluruhan meningkat secara signifikan dengan nilai N-gain sebesar 0.31 dan perubahan konsep mahasiswa semakin baik dengan meningkatnya jumlah mahasiswa yang memiliki pemahaman mantap dan pemahaman sebagian, serta berkurangnya jumlah mahasiswa yang mengalami miskonsepsi dan yang tidak paham.

  11. Metode Pembelajaran Terpadu untuk Mingkatkan Kreativas Verbal Dan Figural Pada Siswa Kelas Enam di SDN 2 Kenayang Tulungagung

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    Mentari Marwa

    2017-12-01

    Full Text Available Penelitian ini bertujuan untuk mengetahui apakah dengan adanya metode pembelajaran terpadu dapat meningkatkan kreativitas verbal dan figural pada siswa kelas VI Penelitian ini menggunakan desain eksperimen Pretest-Posttest One Group Design. Metode pembelajaran terpadu yaitu suatu pembelajaran yang memadukan berbagai materi dalam satu sajian pembelajaran agar siswa memahami keterkaitan antara satu materi dengan materi lain atau antara satu mata pelajaran dengan mata pelajaran lain dan partisipasi aktif dari siswa akan membuat siswa lebih mudah untuk mengingat dan mengembangkan kognitif, dinamika afektif dan psikomotorik anak secara simultan. Hasil penelitian menunjukkan bahwa terdapat pengaruh metode pembelajaran terpadu untuk meningkatkan kreativitas verbal pada anak kelas VI. Metode pembelajaran terpadu ternyata mampu meningkatkan kreativitas verbal siswa, dimana semua siswa mengalami peningkatan kreativitas verbal, dengan nilai Z = -2,041 dan p 0,05

  12. Etnoarheologija – sadašnjost kao ključ za prošlost

    Directory of Open Access Journals (Sweden)

    Marko Porčić

    2016-03-01

    Full Text Available Tema ovog teksta jeste etnoarheologija kao amalgam dve discipline, etnologije i arheologije. Cilj ovog rada je da ukaže na mogućnost veze između etnologije i arheologije, predstavljajući etnoarheologiju kao metodološki put ka pronalaženju načina da se dinamika ljudske aktivnosti poveže sa statikom arheološkog zapisa. Predstavljene i razmotrene su osnovne teorijske pretpostavke koje leže u osnovi etnoarheološkog metoda, a posebna pažnja je posvećena ideji o teoriji srednjeg opsega, nastaloj u kontekstu procesne arheologije. Ključni element teorije srednjeg opsega jeste etnoarheologija kao direktna spona između etnologije i arheologije. Takođe, autor razmatra mogućnosti povezivanja srpske arheologije i etnologije kroz etnoarheološku praksu.

  13. PENDIDIKAN ISLAM SEBAGAI GRAND DESIGN PENDIDIKAN KARAKTER

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    Muhammad Isnaini

    2017-02-01

    Full Text Available Pendidikan karakter dapat dimaknai sebagai proses penanaman nilai-nilai esensial pada diri anak melalui serangkaian kegiatan pembelajaran dan pendampingan sehingga para siswa sebagai individu mampu memahami, mengalami, dan mengintegrasikan nilai-nilai yang menjadi core values dalam pendidikan yang dijalaninya kedalam kepribadiannya. Dengan menempatkan pendidikan karakter dalam kerangka dinamika dan dialektika proses pembentukan individu, para insan pendidik diharapkan semakin dapat menyadari pentingnya pendidikan karakter sebagai sarana pembentuk pedoman perilaku, pembentukan akhlak, dan pengayaan nilai individu dengan cara menyediakan ruang bagi figur keteladanan dan menciptakan sebuah lingkungan yang kondusif bagi proses pertumbuhan, berupa kenyamanan dan keamanan yang membantu suasana pengembangan diri satu sama lain dalam keseluruhan dimensinya (teknis, intelektual, psikologis, moral, sosial, estetis, dan religius.

  14. MELACAK AKAR IDEOLOGI PURITANISME ISLAM: SURVEI BIOGRAFI ATAS “TIGA ABDULLAH”

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    Mutohharun Jinan

    2014-12-01

    Artikel ini membahas tentang varian gerakan Islam di Surakarta dengan pen­dekat­an biografi tokoh. Tokoh yang dijadikan objek kajian adalah Abdullah Sungkar (pendiri gerakan Jamaah Islamiyah, Abdullah Marzuki (pendiri Majelis Pengajian Islam, dan Abdullah Thufail Saputro (pendiri gerakan Majelis Tafsir Al-Quran. Tiga tokoh ini dikenal oleh masyarakat dengan sebutan Tiga A. Pemikiran dan lembaga mereka sangat berpengaruh dalam dinamika perkembangan dan dakwah Islam di Surakarta pada tahun 1970-an hingga sekarang. Mereka pernah bekerja sama dalam lembaga dakwah. Dengan pendekatan kualitatif dan kajian dokumen ditemukan bahwa karenas beberapa perbedaan latar belakang, pandangan, dan orientasi ideologi menjadikan mereka berpisah dan membentuk gerakan sendiri-sendiri. Abdullah Sungkar memilih jalur berseberangan dengan negara, Abdullah Marzuki memilih jalur pendidikan pesantren dan tidak berpolitik, sedangkan Abdullah Thufail Saputro memilih jalur akomodasi dan bekerjasama dengan negara.

  15. Identifikasi Sistim Peternakan di Manokwari, Papua Barat-Indonesia

    Directory of Open Access Journals (Sweden)

    D. A. Iyai

    2015-06-01

    Full Text Available Pembangunan peternakan yang moderen membutuhkan kejelasan dan ketegasan batasan, corak dan dinamika produksinya. Penelitian eksploratif dengan metode survei melalui pendekatan Participative Rural Appraisal selama satu bulan dilakukan untuk mencatat sumberdaya yang dimiliki oleh para peternak berdasarkan kawasan agro-ekologi di Manokwari, yang meliputi Manokwari Utara, Manokwari Selatan, Warmare, Prafi, Masni, Oransbari, Ransiki, Anggi dan Minyambouw. Karakteristik agroekologi dibuat dengan software Microsoft Office VISIO. Matriks sederhana digunakan untuk pengelompokan kriteria komoditi ternak, komoditi pertanian, dan komoditi perikanan dan indikator BioFisik. Sistim peternakan terpadu yang dapat diidentifikasi pada wilayah agroekologi pesisir adalah sistim peternakan sapi berbasis tanaman kelapa (cocobeef dan tanaman pertanian (crops livestock farming system serta backyard poultry farming system. Pada daerah dataran rendah sistim yang dikembangkan adalah cattle-palm farming system, pig palm farming system, goat faming system, poultry farming system dan Crops livestock farming system. Pada kawasan Agroekologi Dataran Tinggi, Crop Pig Farming System, Poultry Farming System dan Backyard Cattle farming system sudah dikembangkan.

  16. Simbolisme Menurut Mircea Eliade

    Directory of Open Access Journals (Sweden)

    Ivan Th.J Weismann

    2005-04-01

    Full Text Available Dalam kehidupan berbangsa dan bernegara kita memiliki simbol yaituPancasila; sedangkan dalam kehidupan beragama kita memiliki simbolyaitu Wahyu atau Kitab Suci. Pancasila dan Kitab Suci sebagai simbolmemberi dasar dinamika dan vitalitas dalam kehidupan berbangsa, bemegara,dan beragama; berfungsi sebagai ungkapan dan jawaban yang berdiridi tengah-tengah antara manusia Indonesia dengan Yang Kudus; tidakhanya mengundang untuk berpikir atau menjadi dasar berpikir tetapijuga mendorong dalam tindakan dan pengambilan keputusan; bahkanPancasila dan Kitab Suci sebagai simbol bagi masyarakat Indonesiayang religius menuntut untuk diperiakukan sebagai partner dialog dalammembangun manusia Indonesia yang seutuhnya. Sebagai partner dialogyang selalu hadir di samping manusia Indonesia yang religius; ia mengajar,menyatakan kesalahan, memperbaiki kelakuan, dan mendidik dalam kebenaran.

  17. THE POSITION OF ISLAM NUSANTARA IN GEOPOLITICAL DINAMYCS OF ISLAMIC WORLD

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    Abdul Chalik

    2016-12-01

    Full Text Available Peranan Islam Nusantara dalam Dinamika Geopolitik Dunia Islam. Tulisan ini berangkat dari kegelisahan terhadap lahirnya ISIS, sebuah gerakan sosial politik yang lebih ekstrim dibandingkan dengan pendahulunya, al-Qaeda. Satu sisi, organisasi ini tidak saja membuat Barat ketakutan atas segala sepak terjangnya, terutama pasca teror Paris di pertengahan Nopember 2015, pada sisi yang lain juga menciderai perasaan umat Islam karena dianggap mendompleng atas nama agama (Islam—sementara perilakunya berlawanan dengan ajaran Islam. Secara geopolitik posisi dunia Islam mengalami dilema; satu sisi harus berhadapan dengan Muslim sendiri sementara pada sisi yang lain harus bersinergi dengan kekuatan asing untuk melawan bangsa atau saudara sendiri. Berbeda dengan Islam ala ISIS atau al-Qaeda yang bercorak ekstrim dan eksklusif, Islam Nusantara berpandangan sebaliknya. Artikel ini ditulis dengan metode ekploratif deskriptif—dengan menyajikan persoalan dunia Islam saat ini dan hubungannya dengan ideologi Islam Nusantara yang sedang dibangun.

  18. THE DYNAMICS OF A DISTRIBUTION SYSTEM SIMULATED ON A SPREADSHEET

    Directory of Open Access Journals (Sweden)

    R. Reinecke

    2012-01-01

    Full Text Available

    ENGLISH ABSTRACT: The dynamics of a typical production-distribution system, namely from manufacturer to distributors to retailers has been simulated with the aid of Lotus 123 on a personal computer. The original simulation program DYNAr10 was run on an IBM 1620 mainframe computer but we successfully converted it to run on a personal computer using LOTUS 123.
    This paper deals with problems encountered in using the present MS-DOS limited PC machines to run application programmes written for earlier mainframe machines. It is also shown that results very comparable with those obtained on mainframe machines can be generated on a simple PC.

    AFRIKAANSE OPSOMMING: Hierdie referaat beskryf die ervaring van magisterstudente met die omskakeling van die simulasieprogram DYNAMO vir die ondersoek van die dinamika van industriele stelsels van hoofraamrekenaar na 'n persoonlike rekenaar.

  19. USING A NEW SUPPLY CHAIN PLANNING METHODOLOGY TO IMPROVE SUPPLY CHAIN EFFICIENCY

    Directory of Open Access Journals (Sweden)

    A.L.V. Raubenheimer

    2012-01-01

    Full Text Available

    ENGLISH ABSTRACT: Effective supply chain planning and management has emerged as one of the most challenging opportunities for companies in the global economy during the last decade or two. This article reviews the evolution of Supply Chain Management and the traditional Supply Chain Solutions. It then introduces a new Supply Chain Planning methodology in which simulation modelling plays an important value-adding role to help organisations understand the dynamics of their Supply Chains.

    AFRIKAANSE OPSOMMING:Effektiewe voorsieningskettingbeplanning en –bestuur het gedurende die laaste twee dekades ontwikkel tot een van die mees uitdagende geleenthede vir ondernemings in die wêreldekonomie. Hierdie artikel hersien kortliks die ontwikkeling van voorsieningskettingbestuur en die tradisionele oplossings. ‘n Nuwe voorsieningskettingbeplanningsmetodologie word dan voorgestel en bespreek waarin simulasiemodellering ‘n belangrike rol speel om ondernemings te help om die dinamika van hul voorsieningskettings te begryp.

  20. Pajamų iš tiesioginių mokesčių tyrimas Lietuvoje

    OpenAIRE

    Stelmakovienė, Reda

    2012-01-01

    Bakalauro baigiamąjame darbe atskleidžiama tiesioginių mokesčių vieta Lietuvos mokesčių sistemoje, išskiriant mokesčių rūšis priskiriamas prie tiesioginių mokesčių grupės, nagrinėjami GPM, pelno mokesčio ir turto mokesčių (nekilnojamojo turto mokesčio, žemės mokesčio, paveldimo turto mokesčio) apmokestinimo instrumentarijai. Nagrinėjama nacionalinio biudžeto mokestinių pajamų struktūrą, dinamika 2006-2010 m., atskleidžiama pajamų iš tiesioginių mokesčių lyginamieji svoriai nacionalinio biudže...

  1. PROTOTIPE SISTEM KONTROL JARAK JAUH BEBERAPA ALAT PENDINGIN RUANGAN BERBASIS RASPBERRY PI

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    mochamad subianto

    2016-11-01

    Full Text Available Saat ini pengendalian on/off berbagai piranti listrik kebanyakan masih dikendalikan dengan menekan tombol saklar atau remote yang penggunaannya dengan jarak yang dekat. Untuk menjawab kebutuhan masyarakat tentang sistem kontrol yang cepat dan dinamis diperlukan suatu teknologi sistem kontrol jarak jauh yang memungkinkan proses secara cepat agar dapat menghemat waktu dan tenaga khususnya pengendalian beberapa alat pendingin ruangan yang berada di beberapa ruangan. Penelitian ini merupakan penelitian lanjutan dari peneliti terdahulu dan menggunakan perangkat yang mempunyai teknolgi terbaru yaitu Raspberry Pi sebagai pengendali untuk membuat suatu sistem kontrol beberapa AC (Air Conditioning pada ruangan yang berbeda secara jarak jauh. Diharapkan dapat sebagai salah satu solusi untuk perkembangan gaya hidup dan dinamika sosial saat ini yang semakin mementingkan kepraktisan dan efisiensi. Metodologi penelitian yang akan digunakan menggunakan metodologi waterfall dengan tahap-tahapannya yaitu tinjauan pustaka, analisa kebutuhan pengguna, analisis sistem, perancangan sistem, implementasi dan pengujian. Hasil akhir dari penelitian adalah prototipe pengendali jarak jauh beberapa perangkat AC Raspberry Pi.

  2. PEMODELAN TOTALLY ASYMMETRIC EXCLUSION PROCESS DUA DIMENSI UNTUK LALU LINTAS KENDARAAN PADA PERTIGAAN JALAN YANG SEARAH

    Directory of Open Access Journals (Sweden)

    R Septiana

    2014-06-01

    Full Text Available Abstrak __________________________________________________________________________________________ Penelitian ini mengkaji model dinamik yaitu Totally Asymmetric Exclusion Process (TASEP khususnya dalam dua dimensi (2D. Selain itu akan dibahas pula mengenai syarat batas dan aturan dinamika yang digunakan dalam pemodelan ini. TASEP telah diaplikasikan dalam berbagai bidang, salah satunya ialah pemodelan lalu lintas kendaraan (traffic flow. Sistem dua dimensi yang akan dikaji adalah sistem yang diskrit, yakni sistem ke kisi dua dimensi. Sistem ini dimodifikasi menjadi bentuk pertigaan (junction yang searah. Lebih jauh lagi, kendaraan yang melalui pertigaan dimodelkan sebagai partikel yang melompat dari satu kisi ke ke kisi yang lain. Nilai kepadatan dan rapat arus partikel dalam sistem tersebut ditentukan secara numerik. Persamaan kontinuitas untuk menggambarkan dinamika partikel dalam TASEP diselesaikan menggunakan metode Euler. Profil kepadatan dan rapat arus partikel dipengaruhi oleh laju masukan (input rate dan laju keluaran (output rate lompatan partikel.   Abstract __________________________________________________________________________________________ The research analyzed a dynamic model of Totally Asymmetric Exclusion Process (TASEP, especially in two dimensions (2D and  also the boundary and rules dynamic conditions  used in this modeling. TASEP has been applied in various fields, one of them is the modeling of vehicle traffic. Two-dimensional system that will be studied is the discrete system of two-dimensional lattice system. The system is modified into the form of unidirectional T-junction . Furthermore, the vehicles that pass the junction are modeled as particles that jump from one lattice to another lattice. The value of the density and current density of particles in the system is determined numerically. The continuity equation to describe the dynamics of particles in TASEP is solved by using Euler's method. The profiles of

  3. The History of the Labour Movement in South Korea 1947-1997: The Role of Blue Collar and White Collar Workers

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    Cahyo Pamungkas

    2011-07-01

    Full Text Available Tulisan ini membahas mengenai perkembangan gerakan buruh di Korea Selatan sejak awal kemerdekaan hingga kini. Menurut saya, saat gerakan buruh kuat, ia memiliki efek yang lebih kuat pula pada proses demokratisasi karena adanya akar sejarah gerakan buruh dalam melawan feodalisme dan imperialisme. Temuan lainnya adalah bahwa kehadiran rezim demokratis tidak berarti bahwa aspirasi kelompok buruh dapat terakomodasi. Tekanan kekuatan neo-liberal, baik pada level nasional maupun internasional, dapat menekan pemerintahan yang demokratis untuk mengikuti kepentingan pemilik modal besar, khususnya dalam memaksakan sistem kerja kontrak. Namun, aliansi antara gerakan buruh dengan elemen masyarakat sipil dapat melawan dan menolak kebijakan ini. Faktor lain yang penting yang memengaruhi gerakan buruh adalah demokratisasi dan globalisasi. Jika demokratisasi memperkuat gerakan buruh, maka globalisasi berusaha mengontrolnya. Namun demikian, dinamika relasi antara pemerintah dan gerakan buruh di Korea Selatan menunjukkan bahwa aliansi antara buruh, mahasiswa, dan gereja dapat mempersatukan masyarakat sipil melawan baik pemerintah maupun kekuatan neo-liberal.Tulisan ini membahas mengenai perkembangan gerakan buruh di Korea Selatan sejak awal kemerdekaan hingga kini. Menurut saya, saat gerakan buruh kuat, ia memiliki efek yang lebih kuat pula pada proses demokratisasi karena adanya akar sejarah gerakan buruh dalam melawan feodalisme dan imperialisme. Temuan lainnya adalah bahwa kehadiran rezim demokratis tidak berarti bahwa aspirasi kelompok buruh dapat terakomodasi. Tekanan kekuatan neo-liberal, baik pada level nasional maupun internasional, dapat menekan pemerintahan yang demokratis untuk mengikuti kepentingan pemilik modal besar, khususnya dalam memaksakan sistem kerja kontrak. Namun, aliansi antara gerakan buruh dengan elemen masyarakat sipil dapat melawan dan menolak kebijakan ini. Faktor lain yang penting yang memengaruhi gerakan buruh adalah demokratisasi

  4. Research nuclear reactor RA - Annual Report 1997; Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Reaktor RA nije u pogonu od 1984, aktivnosti na revitalizaciji, rekostrukciji i modernizaciji reaktorski sistema zapocete su 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Do septembra 1991. godine isporuceno svega 80% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju usled sankcija uvedenih od strane organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane safeguard inspektora MAAE obavljana

  5. Research nuclear reactor RA - Annual Report 1996; Istrazivacki nuklearni reaktor RA - Izvestaj za 1996. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1996-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U toku 1996. godine nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom

  6. Research nuclear reactor RA - Annual Report 1995, with comparative review for period 1991-1995; Istrazivacki nuklearni reaktor RA - Izvestaj za 1995. godinu, uz uporedni pregled za period 1991-1995

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1995-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued during period 1991-1995. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved during the period 1991-1995. This research reactor RA Annual is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U periodu 1991-1995. godina nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom

  7. RA reactor operation and maintenance in 1992, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktoro RA u 1992. Godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Cupac, S; Sulem, B; Zivotic, Z; Majstorovic, D; Tanaskovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-12-01

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems. [Serbo-Croat] U toku 1992 godine poslovi u okviru projekta 'Istrazivacki nuklearni reaktor RA' obavljani su u skladu sa programom i planom rada. Osnovne aktivnosti na kojima je radjeno odnosile su se na revitalizaciju reaktora RA, kao i na odrzavanje opreme. U ovom periodu reaktor nije bio u pogonu. Svo osoblje je bilo angazovano na poslovima rekonstrukcije i modernizacije postojecih i dogradnje novih reaktorskih sistema, na odrzavanju opreme a deo tehnickog osoblja je bio obucavan za vrsenje odgovarajucih poslova u pogonu i odrzavanju opreme.

  8. Heat conductance of sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    Phenomena influencing the heat conductance of the sintered UO{sub 2} were analyzed, first of all when used as nuclear fuel. Influence of temperature, density and porosity, additives and irradiation in the reactor are shown. Based on the available literature, the measured heat conductance values were analyzed for the sintered UO{sub 2} outside the reactor and in the reactor during irradiation. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

  9. A review of calculation methods for fast and intermediate reactors; Expose des methodes pour le calcul de reacteurs a neutrons rapides et intermediaires; Obzor metodov rascheta reaktorov na promezhutochnykh i bystrykh nejtronakh; Estudio panoramico de los metodos de calculo de los reactores rapidos e intermedios

    Energy Technology Data Exchange (ETDEWEB)

    Marchuk, G I [Akademiya Nauk, Moskva, Union of Soviet Socialist Republics (Russian Federation)

    1962-03-15

    de ecuaciones fundamentales y conjugadas de la teoria de los multigrupos. Expone luego diversas aplicaciones de la teoria de la perturbacion a los problemas del calculo fisico del reactor. Examina los metodos numericos de resolucion de las ecuaciones fundamentales y conjugadas que expresan el funcionamiento del reactor sobre la base del metodo de los armonicos esfericos. Explica asimismo como se utiliza el metodo de las caracteristicas en la solucion de problemas relativos a la masa critica del reactor. Describe los metodos de calculo de los reactores con moderadores que contienen hidrogeno y, por fin, expone las bases de un modelo efectivo fundado en la teoria de un solo grupo, aplicable al reactor. (author) [Russian] Obsuzhdaetsya razvitie metodov rascheta yadernykh reaktorov na promezhutochnykh i bystrykh nejtronakh. Rassmatrivayuts ya razlichnye postanovki zadach fizicheskogo rascheta. Obsuzhdaetsya uchet rezonansnykh ehffektov. Vvodyatsya v rassmotrenie mnogogruppovy e sistemy 'osnovnykh i sopryazhennykh uravnenij. Daetsya razlichnoe primenenie teorii vozmushchenij k zadacham fizicheskogo rascheta reaktora. Rassmatrivayuts ya chislennye metody resheniya osnovnykh i sopryazhennykh uravnenij reaktora v priblizhenii metoda sfericheskikh garmonik. Daetsya primenenie metoda kharakteristik k resheniyu zadach na kriticheskuyu massu reaktora. Izlagayutsya metody rascheta reaktorov s vodorodsoderzhashchim i zamedlitelyami . Izlagayutsya osnovy ehffektivnoj odnogruppovoj modeli reaktora. (author)

  10. Annex 3 - Testing the microstructure of the fuel element with metal uranium with aluminium cladding; Prilog 3 - Ispitivanje mikrostrukture gorivnog elementa na bazi metalnog urana sa aluminijumskom kosuljicom

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, S; Momcilovic, I [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    Based on the uranium microstructure in the fuel element, i.e. grain size, presence of other phases, porosity and the position of metal connections, some data could be obtained about the mechanical and thermal treatment of the uranium during fuel element fabrication. The mentioned characteristics could indicate the behaviour of the fuel under reactor operating conditions taking into account its stable dimensions and roughness of its surfaces. Na osnovu mikrostrukture urana u gorivnom elementu, odnosno velicine i oblika njegovih kristalnih zrna, prisustva drugih faza, pozoziteta kao i rasporeda metalnih ukljucaka, mogu se dobiti izvesni podaci o tome koje je postupke mehanickog i termickog tretiranja pretrpeo uran u pripremi za gorivni elemenat. Prethodne karakteristike takodje mogu da daju predstavu o tome kako ce se gorivo ponasati u uslovima rada reaktora, s obzirom na njegovu dimenzionu stabilnost i ogrubljivanje njegove povrsine (author)

  11. Definition of task (Phase II) B, 'Leak testing'; Definicija zadatka (II faza) B, 'Ispitivanje hermeticnosti'

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    In order to ensure safe Ra reactor operation and fulfilling the conditions for performing irradiation experiments it was necessary to test and verify the leak tightness of the sample containers and thermocouples, as well as the irradiation capsule before it was placed in the VISA-2 channel. Leak testing of VISA-2 channel with capsules and thermocouples was done before and after it was built-in the reactor. [Serbo-Croat] U cilju bezbednosti i sigurnosti rada reaktora RA i ispunjavanja uslova ozracivanja izvrsena je provera hermeticnosti kenera sa uzorcima i termoparovima, kao i hermeticnost kapsule pre ugradjivanja kapsule u kanal VISA-2. Izvrseno je i ispitivanje hermeticnosti kanala VISA-2 sa kapsulama i termoparovima pre ugradjivanja u reaktor i posle montaze.

  12. Technical realisation of the VISA-II Project, Phase II, Chapter X, Vol. VI; Tehnicka realizacija projekta VISA-II, II faza, Glava X, Album VI

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    The second phase of the 'Project VISA-2 described in this chapter of Vol. VI includes the project specifications and technical drawings of the 'measuring system of VISA-2 for testing the VISA-2 channels outside and in the reactor'. In addition to the task objective, description of the measuring system, action plan, description of the work done it contains the definition of the task 'Leak testing' and instructions for the instrumentation personnel on duty. [Serbo-Croat] Druga faza zadatka {sup T}ehnicka realizacija projekta VISA-2' opisana u ovom poglavlju Albuma VI, sadrzi tehnicki opis i crteze 'Mernog sistema VISA-2 i ispitivanje kanala VISA-2 van reaktora i u reaktoru'. Pored definicije zadatka, opisa mernog sistema VISA-2, razrade zadatka, tekstualnog dela projekta i opisa izvedenih radova, ovo poglavlje obuhvata definiciju i razradu podzadatka 'Ispitivanje hermeticnosti' i dodatak sa instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2.

  13. Determination of the tritium content in the reactor heavy water; Odredjivanje porasta kolicine tritijuma u reaktorskoj teskoj vodi

    Energy Technology Data Exchange (ETDEWEB)

    Ribnikar, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    Quantity of tritium was measured in the heavy water, in the heavy water vapour and radiolyzed deuterium from the helium cover gas of the RA reactor. It has been shown that isotopic equilibrium D{sub 2}O+DT{r_reversible}DTO+D{sub 2} exists and that it is catalyzed by irradiation. Small quantities of ammonium in the reactor cover gas are inhibiting the migration of tritium from the heavy water. Izmerena ja sadrzina tritijuma u tecnoj teskoj vodi, njenoj pari i radiolizovanom deuterijumu iz helijumske atmosfere reaktora RA. Pokazano je da postoji izotopska ravnoteza D{sub 2}O+DT{r_reversible}DTO+D{sub 2}, koja je katalizovana zracenjem. Male kolicine amonijaka reaktorske atmosfere deluju u smislu otezavanja migracije tritijuma iz teske vode (author)

  14. Possibilities of using metal uranium fuel in heavy water reactors; Mogucnosti upotrebe metalnog urana kao goriva za teskovodne reaktore

    Energy Technology Data Exchange (ETDEWEB)

    Djuric, B; Mihajlovic, A; Drobnjak, Dj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    There are serious economic reasons for using metal uranium in heavy water reactors, because of its high density, i.e. high conversion factor, and low cost of fuel elements production. Most important disadvantages are swelling at high burnup and corrosion risk. Some design concepts and application of improved uranium obtained by alloying are promising for achievement of satisfactory stability of metal uranium under reactor operation conditions. Postoje ozbiljni ekonomski razlozi za primenu metalnog urana u teskovodnim reaktorima, pre svega zbog njegove velike gustine, odnosno visokog konverzionog faktora, i zbog niskih troskova proizvodnje gorivnih elemenata. Glavne prepreke su bubrenje pri velikim stepenima sagorevanja i opasnost od korozije. Postoje veliki izgledi da se primenom odredjenih projektnih koncepcija i upotrebom legiranjem poboljsanog urana postigne zadovoljavajuca stabilnost metalnog urana u uslovima rada reaktora (author)

  15. Thermal conductivity of the sintered UO{sub 2}; Toplotna provodljivost sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Katanic-Popovic, J; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1967-04-15

    Phenomena influencing the thermal conductivity of the sintered UO{sub 2} fuel were analyzed. Influence of temperature, density and porosity, additives and irradiation in the reactor core are presented. Thermal conductivity of sintered UO{sub 2} was measured both outside the reactor and during the irradiation in the reactor. Results are discussed and analyzed based on the available literature. Analizirane su pojave koje uticu na toplotnu provodljivost sinterovanog UO{sub 2}, pre svega, sa aspekta njegove primene kao goriva. Izlozen je uticaj temperature, gustine i poroznosti, aditiva i ozracivanja u reaktoru. Na osnovu pregleda dostupne literature kriticki su prikazani rezultati merenja toplotne provodljivosti sinterovanog UO{sub 2} van reaktora i u reaktoru pri ozracivanju (author)

  16. Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste; Deo 2 - Prilog 2 - Dekontaminacija i intervencije, skupljanje tecnih efluenata i cvrstih radioaktivnih otpadnih materijala

    Energy Technology Data Exchange (ETDEWEB)

    Mandic, M; Vukovic, Z; Lazic, S; Plecas, I; Voko, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1995-12-01

    Certain amount of solid waste results from RA reactor operation, the mean quantity of which depends on the duration of reactor operation and related activities. During repair, when reactor is not operated as well under accidental conditions, the quantity of waste is higher, dependent on the type of repair and comprehensiveness of decontamination of the working surface, contaminated tools and components. The waste is sorted and packed on the spot where they appeared according to the existing regulations and principles of radiation protection with aim to minimize unnecessary exposure of the radiation protection personnel who deals with control, transport, radioactive waste treatment and decontamination. During exceptional operations (decontamination, repair, bigger volume of contaminated material, etc.) professional staff of the Radiation protection department gives recommendations and helps in planning the actions related to repair, sorting and packaging of radioactive waste in special containers, identification of the contaminants, etc. [Serbo-Croat] Tokom rada reaktora RA dolazi do stvaranja odredjenih cvrstih otpadnih materijala cija prosecna kolicina zavisi od vremena rada reaktora i aktivnosti koje se tamo obavljaju. Tokom remonta, kada reaktor ne radi kao i pri akcidentalnim situacijama nastaju vece kolicine otpadnih materijala koje zavise od obima i vrste remontnih operacija i obima dekontaminacije kontaminirane radne povrsine i kontaminiranog alata, predmeta, opreme, itd. Nastali otpadni materijali se razvrstavaju i pakuju na mestu nastanka prema odgovarajucim propisima u skladu sa principima zastite od zracenja i aspekta bezbednosti u cilju minimiziranja nepotrebnog ozracivanja ljudstva za preuzimanje, kontrolu, transport, naknadnu obradu RAO i dekontaminaciju. Pri nerutinskim operacijama (dekontaminacija, remont, kontaminiarni otpadni materijal velike zapremine i sl.), strucna sluzba Institita ZASTITA pruza strucne konsultacije i pomaze pri planiranju

  17. RA Research nuclear reactor - Annual report 1987; Istrazivacki nuklearni reaktor RA - Izvestaj o radu za 1987. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1987. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3509/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  18. RA Research reactor, Annual report 1988; Istrazivacki nuklearni reaktor RA - Izvestaj za 1988. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  19. Research nuclear reactor RA - Annual Report 1989; Istrazivacki nuklearni reaktor RA - Izvestaj za 1989. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  20. Research nuclear reactor RA - Annual Report 1990 with the comparative evaluation for the period 1986-1990; Istrazivacki nuklearni reaktor RA - Izvestaj za 1990. godinu uz uporedni pregled za period 1986 - 1990

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1990, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1990. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  1. Influence of the neutron flux shape on the value of absorbed neutron dose; Uticaj oblika neutronskog spektra na vrednost apsorbovane doze neutrona

    Energy Technology Data Exchange (ETDEWEB)

    Miric, I; Miric, P [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1974-07-01

    This paper deals with the study od specific doses dependence on the type and approximation procedures of neutron spectra. Values of specific dose rates (dose per neutron cm{sub 2}) were analysed for neutron spectra from RB reactor in Vinca, Crac facility in Valduc (France) and HPRR reactor in Oak Ridge (USA). Data used in this analysis were obtained by methods used in Harwell (AERE), Oak Ridge (ORNL), Chalk River (AECL), CEN de Cadarache (CEA) and in the Boris Kidric Institute (IBK). Specific absorbed neutron doses were determined for each of the estimated spectra and presented in the form of kerma/(n.cm{sup -2}) and rad/((n.cm{sup -2}) units. The obtained results have shown the influence of the flux approximation procedure on the values of conversion factors for obtaining neutron doses from neutron flux. U okviru ovog rada radjeno je na ispitivanju zavisnosti specificnih doza od vrste i nacina aproksimacije neutronskog spektra. U radu su analizirane vrednosti specificnih doza (doza po n.cm{sup -2}) za neutronske spektre koji se dobijaju oko sledecih nuklearnih postrojenja: reaktora RB u Vinci, postrojenja CRAC u Valduc-u (Francuska), reaktora HPRR u Oak Ridge-u (SAD). Za analizu su korisceni podaci dobijeni metodama koje se koriste u nuklearnim centrima Harwell (AERE), Oak Ridge-u (ORNL), Chalk River-u (AECL), CEN de Cadarache (CEA) i Institutu Boris Kidric (IBK). Za svaki procenjeni spektar odredjene su specificne apsorbovane doze neutrona izrazene u kerma/(n.cm{sup -2}) i rad/(n.cm{sup -2}) jedinicama. Dobijeni rezultati su pokazali koliko nacin aproksimacije spektra utice na vrednost konverzionih faktora koji sluze za prelazak sa fluksa na dozu neutrona (author)

  2. RA Research reactor, Annual report 1971; Istrazivacki nuklearni reaktor RA - Izvestaj za 1971. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1971-12-15

    effects. In the introduction of this report it has been emphasised that the decision makers should have in mind the negative effects of low budget on the reactor safe and reliable operation. For the sake of reactor, decision about the future operation and financing should be done as soon as possible, either to cease operation or continue with adequate financial support. [Serbo-Croat] Reaktor RA je u 1971. godini radio na nominalnoj snazi 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31606 MWh odnosno 5,3% vise od planiranog, sto je najvisa vrednost od kako je reaktor pusten u rad. Reaktor je koriscen za ozracivanja i eksperimente za 425 korisnika od cega 370 iz Instituta i 55 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Odstupanja od plana, odnosno veceg ostvarenog rada bilo je u junu i decembru usled posebnih zahteva korisnika. Ukupni broj prekida rada bio je manji od svih prethodnih godina, uglavnom zbog manjeg broja nestanka napona u vreme rada reaktora. U toku godine bilo je samo jedno sigurnosno zaustavljanje, ciji je uzrok bila pojava laznog signala opreme za zastitu reaktora. Nijednog duzeg prekida rada nije bilo zbog neispravnosti opreme. Kracih prekida bilo je usled kidanja spojki na potisnom cevovodu tehnicke vode, sto je bilo izazvano klizanjem zemljista u podrucju crpne stanice na Dunavu. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta niti slucaja koji bi se mogao nazvati akcidentom. Dekontaminirano je znatno manje povrsina nego ranijih godina. Zakljuceno je da je uspesan rad reaktora u 1971. godini rezultat valjanog rada u prethodnim godinama. Medjutim usled jos nedefinisane politike u pogledu buduceg rada, odnosno neizvesnosti u vezi finansiranja, neki poslovi su obustavljeni. Tu spada proucavanje mogucnosti prelaska na koriscenje visokoobogacenog goriva sto bi povecalo korisni neutronski fluks i ucinilo reakor konkurentnim za

  3. Estetika Bawa dalam Karawitan Gaya Surakarta

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    Timbul Haryono

    2016-02-01

    Full Text Available Penelitian ini difokuskan pada garap vokal terutama estetika båwå untuk mencapai keselarasanbåwå atau carem.  Penelitian ini menggunakan perpektif musikologis dengan menganalisis berbagaiaspek yang berkaitan dengan estetika båwå dalam karawitan meliputi (1 teknik penyuaraan,pernafasan, dinamika, laya, dan kepekaan pathet; (2 jenis-jenis suara yang mendukung capaiankeselarasan sajian båwå; dan (3 pelarasan. Hasil penelitian ini menunjukkan bahwa caremmerupakan perpaduan dari beberapa unsur musikal membentuk  satu  kesatuan yang utuh (atut, sehinggamenimbulkan keselarasan (runtut. Dengan demikian untuk mencapai båwå pada tataran carem harus memiliki unsur-unsur estetika: suara baik, larasan pleng, menguasai teknik penyuaraan, menguasai teknik pernafasan, mampu mengatur dinamika, mampu mengatur laya, memiliki kepekaan pathet,dan mampu memilih céngkok, sesuai dengan jenis suara. Pelantun båwå yang memenuhi persyaratanini dapat dipastikan telah mencapai carem.. The Aesthetics of Bawa in Karawitan Style of Surakarta. This study focuses on the vocal creation,especially on the aesthetic of båwå, to achieve the harmony of båwå, which is called carem. This study isconducted by employing the musicological perspective, by which analyzing the various aspects related to theaesthetics of båwå karawitan style of Surakarta which include the followings: (1 the techniques of voicing,breathing, dynamics, laya, and sensitivity of pathet; (2types of sounds that support the achievement of Båwå presentation; and (3 sound tunings. The results of this study show that carem is the combination ofseveral musical elements which form a whole unity (atut, so that it will create a sense of harmony (runtut.Therefore, in order to achieve carem, the singer of the båwå must at least have the aesthetics elements, suchas: 1 a good voice and accurate intonation, 2 a good command of vocal techniques, 3 a good commandof breathing techniques, 4 the ability

  4. Cosmology Design Products Wears To Pura In Bali

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    I Nyoman Dana

    2017-10-01

    Full Text Available Bali is one of the areas in Indonesia that still upholds the customs and arts of traditional culture and is admired by the world community. Customary products to the temple are part of the struggle to keep local wisdom. Design cosmology is a transcendental dimension that has a very complex exploration. Life is deep, also full of uncertainty. Ideas, creativity, passion, and ideals, creativity, concepts that overlap, whether intangible or not. The style in the design is a reflection of the behavior and attitude of human life at a certain time, and in line with the dynamics of life, such as social dynamics, cultural development and value. Design can be a reflection of the times in each period. Designer style can be a product trend if he is able to meet the needs and tastes of society. If the design word would be made to satisfy the needs of the community or the person who would carry out a customary and cultural activity for example, then the draft concept should begin from who and when it will be used, it should be considered as a considerate consideration by a designer, so that what they are designed to be acceptable to users of the design. Bali adalah salah satu daerah di Indonesia yang masih menjunjung budaya adat dan budaya kesenian yang masih dikagumi oleh masyarakat dunia. Produk adat tradisional ke pura merupakan bagian dari perjuangan untuk menjaga kearifan lokal. Desain kosmologi adalah dimensi transendental yang memiliki eksplorasi yang sangat kompleks. Gaya dalam desain merupakan cerminan dari perilaku dan sikap budaya manusia pada waktu tertentu, sejalan dengan dinamika kehidupan, seperti dinamika sosial, perkembangan budaya dan nilai. Desain bisa menjadi cerminan zaman di setiap periode. Gaya perancang bisa menjadi tren jika ia mampu memenuhi kebutuhan dan selera konsumen. Anadai mengatakan, desain akan dibuat untuk memenuhi kebutuhan masyarakat atau orang yang akan melakukan kegiatan adat dan budaya, maka draf konsep harus dimulai

  5. ANALISIS PERKEMBANGAN WILAYAH, PEMUSATAN PERUBAHAN PENGGUNAAN LAHAN HUTAN DAN KAITANNYA DENGAN KEHIDUPAN SOSIAL BUDAYA MASYARAKAT MERAPI (The Analysis of Area Development, Change Decentralization, Forest Use, and Their Relationship with Social

    Directory of Open Access Journals (Sweden)

    Setiaji Setiaji

    2016-02-01

    Full Text Available ABSTRAK Dinamika wilayah desa tercermin dari perubahan terus menerus yang berkaitan dengan berbagai faktor lingkungan hidup.Tujuan penelitian ini untuk mengidentifikasi perubahan dan dinamika perubahan penggunaan lahan, pemusatan dan pertumbuhan penggunaan lahan, serta dampak sosial budaya masyarakat petani hutan rakyat di Kecamatan Cangkringan. Metode yang digunakan analisis loqation quotient (LQ, skalogram, korelasi, observasi, dan kuisioner. Hubungan LQ dengan indeks perkembangan desa (IPD menggunakan analisis korelasi, dengan parameter nilai LQ, jumlah sarana prasarana, jumlah penduduk, serta nilai IPD. Berdasar nilai IPD, kelurahan yang mempunyai nilai IPD tertinggi adalah Argomulyo (72,952, nilai IPD sedang adalah Umbulharjo (50,971, Kepuharjo (48,781, Wukirsari (40,695 dan Glagaharjo (36,599, sedangkan kelurahan dengan nilai IPD terendah tidak ada. Berdasar hirarki wilayah dan nilai IPD tahun 2011 kelurahan di dataran bagian atas umumnya mempunyai hirarki yang lebih rendah. Hanya variabel IPD yang signifikan berpengaruh terhadap LQ pemukiman. Budaya, regulasi, dan kesepakatan masyarakat menjadi modal sosial untuk menangani perubahan. ABSTRACT The dynamics of rural areas is reflected in the continuous changes associated with various environmental factors. The purpose of this research is to identify the changes and the dynamics of land use changes, the centralization and the growth in land use, as well as the social and cultural impacts of community forest farmers in Cangkringan. The method used in the analysis stage was Loqation Quotient (LQ, schallogram, correlation, observation, and questionnaires. The relationship LQ with rural development index (IPD used correlation analysis, with parameter values LQ, the amount of infrastructure, population, and the value of IPD. Based on the IPD value, villages that had the highest IPD value was Argomulyo (72.952, the average IPD value was Umbulharjo (50.971, Kepuharjo (48.781, Wukirsari (40.695, and

  6. Instructional Materials Physics High School with Multi Representation Approach

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    Yuvita Widi Astuti

    2014-06-01

    Full Text Available Bahan Ajar Fisika SMA dengan Pendekatan Multi Representasi Abstract: One effort to improve understanding of concepts and problem-solving skills in learning physics is to provide instructional materials in accordance with the characteristics of the students and help students learn. The purpose of this study are: (1 developing a high school physics teaching materials especially materials Rotation Dynamics and Equilibrium Rigid objects using multiple representations approach to improve the understanding of physics concepts, (2 test the effectiveness of instructional materials development results. This research method is the development of research using Dick & Carey model tailored to the needs of research. The research instrument used in the form of feasibility questionnaire. The type of data that is obtained is quantitative data and qualitative data. Experimental results show that the result of the development of teaching materials can be categorized as very feasible. Results of field trials showed that: (1 most of the students in the experimental class above KKM obtain test results, (2 the results of the experimental class postes greater than the control class, so that teaching materials said to be effective, but not significant to improve the understanding of physics concepts. Key Words: teaching materials, multi-representation, the rotational dynamics Abstrak: Salah satu upaya untuk meningkatkan pemahaman konsep dan kemampuan memecahkan masalah dalam pembelajaran fisika adalah dengan menyediakan bahan ajar yang sesuai dengan karakteristik siswa dan memudahkan siswa dalam belajar. Tujuan dari penelitian ini adalah: (1 mengembangkan bahan ajar fisika SMA khususnya materi Dinamika Rotasi dan Kesetimbangan Benda Tegar menggunakan pendekatan multi representasi untuk meningkatkan pemahaman konsep fisika, (2 menguji efektifitas bahan ajar hasil pengembangan. Metode penelitian ini adalah penelitian pengembangan menggunakan model Dick & Carey yang

  7. ORIENTASI GRUP VOKAL AWAN VOICE PADA IDEOLOGI PASAR MUSIK INDONESIA

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    Ari Widyaningrum

    2014-08-01

    Full Text Available Penelitian ini bertujuan memberikan gambaran ciri khas musik grup vokal Awan, dinamika perkembangan komposisi dan aransemen lagu Awan Voice, serta orientasi grup Awan Voice pada ideologi pasar musik Indonesia. Penelitian dilakukan dengan metode penelitian analisis kualitatif dengan lokasi penelitian di Kota Semarang, adapun wujud dan sumber data terdiri dari sumber dan wujud data tertulis maupun tidak tertulis. Instrumen dan teknik pengambilan data mengunakan observasi, wawancara dan studi dokumentasi. Teknik keabsahan data menggunakan teknik triangulasi data. Sedangkan teknik analisis dan pengolahan data pengumpulan, reduksi, klarifikasi dan verifikasi data. Ciri khas musik dari Awan Voice adalah musik yang berformat acapella dengan sentuhan beatbox. Selain itu dalam setiap performnya diselingi dengan guyonan sehingga menarik perhatian penikmatnya. Dinamika perkembangan komposisi dan arransemen karya Awan voice dapat dilihat dari aspek judul lagu, komposisi lagu, struktur lagu, melodi, harmonisasi, pangsa pasar dan motif lagunya. Sedangkan orientasi terhadap ideologi pasar musik Indonesia adalah musik Awan voice menerapkan melodi yang mudah diingat dan di mainkan fleksibel, lagunya mudah dinyanyikan dan diserap maknanya. Harmoni yang tidak terlalu muluk. Dapat dipadukan dengan instrumen atau jenis musik yang tidak biasa seperti classic, blues dan lain-lain. Karya mereka disesuaikan dengan waktu dan tempat atau pangsa pasar yang akan ditujunya, dan mempunyai profitabilitas.This study aims at describing vocal group Awan Voice characteristics, dynamic development of music composition, Awan Voice vocal arrangement and Awan Voice music market ideology. This study uses qualitative method in Semarang City. The data and data sources consist of written data and unwritten data. Data instruments and techniques of collecting data are observation, interview and documentation. The data validity uses triangulation. The analysis data consists of collecting

  8. PENGEMBANGAN VARIATIF RANCANGAN ANTENA PANEL MICROSTRIP TAPERED PATCH DALAM SISTEM KOMUNIKASI WI-FI

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    Putu Artawan

    2013-04-01

    Full Text Available Pada penelitian ini dilakukan pengembangan rancangan antena microstrip tapered patch untuk dilakukan pengukuran parameternya sebagai karakteristik dari antena Microstrip. Penelitian ini sebagai pengembangan variatif rancangan untuk memperoleh hasil yang lebih optimal. Metode eksperiment dilakukan dalam penelitian ini. Tahap pengerjaanya yaitu membuat desain rancangan antena sesuai persamaan yang ada yang kemudian dirancang dengan metode UV Photoresist laminate. Hasil rancangan antena diukur untuk mendapatkan karakteristik sebagai parameter antena meliputi frekuensi (bandwidth, SWR, VSWR, koofesien refleksi, pola radiasi dan penguatan (gain serta nilai HPBW. Nilai-nilai tersebut mencerminkan karakter dari sebuah antena sebagai parameter antena yang layak diimplementasikan dalam sistem komunikasi internet dengan sistem wi-fi. Hasil penelitian ini meliputi: nilai lebar pita (bandwidth = 0.21 GHz, VSWR = 1,23, SWR = 1,79,  return loss = -20,00 dB, koofesien refleksi = 0,10 dan grafik pola radiasi dengan penguatan (gain = 17 dB (polarisasi vertikal, 20 dB (polarisasi horizontal. Nilai Half Power Beamwidth (HPBW 820 untuk pola radiasi vertikal dan pola radiasi horizontal. Kesalahan (error hasil pengukuran 0,12% dengan keseksamaan 99,88%. Hasil ini memberikan indikasi sebagai rancangan antena yang layak untuk sistem komunikasi wi-fi. Penelitian ini sebagai salah satu aplikasi ilmu Fisika dalam dunia teknologi informasi dan diharapkan dapat bermanfaat sebagai dinamika wahana salah satu produk penerapan ilmu Fisika dalam bidang Teknologi Informasi.

  9. KONSEP PENULISAN JURNALISTIK MASA DEPAN DAN DESAIN STORYBOARD UNTUK ONLINE NEWS

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    Ido Priyana Hadi

    2003-01-01

    Full Text Available Entering this 21st century%2C press (on newspapers and magazines no longer count on physical printed edition to meet the readers demand on actual news. Press are required to provide online information in term of minutes or even seconds as soon as an event is occuring. Thus%2C speed has become an essential factor in journalism. News is associated to new-ness. Newspapers and magazines are competing one another to serve news fresh from the oven. Journalism has proceeds to an outstanding speed and dynamics which transforms its operation pattern%2C affiliated with the boost of information technology and communication especially the internet. Abstract in Bahasa Indonesia : Memasuki trend abad ke 21 pers cetak (koran dan majalah sekarang tidak saja mengandalkan edisi fisik cetak untuk menjumpai para pembaca setianya dengan sajian berita-berita aktualnya. Tetapi dituntut mampu memberikan sajian informasi online yang seketika%2C dalam hitungan menit atau bahkan detik atas peristiwa atau kejadian disuatu tempat. Karenanya unsur kecepatan (speed menjadi sesuatu yang esensial dalam jurnalistik. News yang berarti berita terkandung didalamnya makna kebaruan. Surat kabar dan majalah dengan sendirinya berkompetisi dalam menyampaikan kebaruan tersebut. Karenanya kehidupan jurnalistik mengalami percepatan serta dinamika yang luar biasa%2C yang pada akhirnya mengubah pola pengerjaan jurnalistik seiring dengan kemajuan di bidang teknologi informasi dan komunikasi khususnya internet. Writing%2C Journalism%2C Online News%2C Storyboard Design.

  10. PCA-based ANN approach to leak classification in the main pipes of VVER-1000

    International Nuclear Information System (INIS)

    Hadad, Kamal; Jabbari, Masoud; Tabadar, Z.; Hashemi-Tilehnoee, Mehdi

    2012-01-01

    This paper presents a neural network based fault diagnosing approach which allows dynamic crack and leaks fault identification. The method utilizes the Principal Component Analysis (PCA) technique to reduce the problem dimension. Such a dimension reduction approach leads to faster diagnosing and allows a better graphic presentation of the results. To show the effectiveness of the proposed approach, two methodologies are used to train the neural network (NN). At first, a training matrix composed of 14 variables is used to train a Multilayer Perceptron neural network (MLP) with Resilient Backpropagation (RBP) algorithm. Employing the proposed method, a more accurate and simpler network is designed where the input size is reduced from 14 to 6 variables for training the NN. In short, the application of PCA highly reduces the network topology and allows employing more efficient training algorithms. The accuracy, generalization ability, and reliability of the designed networks are verified using 10 simulated events data from a VVER-1000 simulation using DINAMIKA-97 code. Noise is added to the data to evaluate the robustness of the method and the method again shows to be effective and powerful. (orig.)

  11. New Trends in Islamic Political Parties in the Arab Spring Countries

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    Ibnu Burdah

    2014-12-01

    [Perkembangan mutakhir partai-partai politik Islam di sejumlah negara Arab “Musim Semi” menunjukkan adanya perubahan orientasi dan agenda baru, berupa penegasan kembali komitmen mereka terhadap nilai-nilai demokrasi, penguatan masyarakat sipil, dan adopsi prinsip-prinsip hak asasi manusia. Pada saat yang sama, mereka tampak kurang tertarik kepada agenda-agenda politik Islam lama seperti jihad bagi pendirian negara Islam dan pendirian pemerintahan Islam global di bawah satu khalifah yang tersentralisasi. Hal ini relevan terhadap kasus Partai Keadilan dan Pembangunan (Ḥizb al-‘Adālah wa’l-Tanmiyah di Maroko, Partai Kebebasan dan Keadilan (Ḥizb al-Ḥurriyyah wa’l-‘Adālah di Mesir, dan Partai Kebangkitan (Ḥizb al-Nahḍah di Tunisia. Artikel ini berupaya mengeksplorasi dan menjelaskan fakta baru ini. Berdasarkan kajian pustaka dan wawancara dengan sejumlah petinggi Partai Keadilan dan Pembangunan di Maroko, penulis berkesimpulan bahwa orientasi baru ini terjadi akibat dari gelombang demokratisasi dunia, “angin kencang musim semi” Arab yang begitu kuat, dan dinamika internal partai.

  12. KONSTRUKSI SOSIAL ANGGOTA GENG MOTOR DI KOTA BANDUNG

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    Purwanti Hadisiwi

    2013-06-01

    Full Text Available Tujuan penelitian ini adalah untuk mengidentifikasi makna diri anggota geng motor, pengharapan anggota geng motor akan diri yang ideal, dan dinamika pembentukan makna diri geng motor yang meliputi latar belakang komunikasi dengan keluarga, sesama anggota geng motor, dan lingkungan sekitar mereka. Kejahatan geng motor selalu meresahkan masyarakat karena kebrutalannya dalam merusak dan membunuh korban tanpa alasan yang jelas. Pola kejahatannya sama, yaitu dengan mengendarai sepeda motor, mereka merusak dan merampok mini market atau mengejar korban yang tidak bersalah, melukai atau bahkan membunuhnya. Melalui wawancara mendalam terhadap sembilan informan, penelitian ini mencoba membangun realitas geng motor di Kota Bandung. Hasil Penelitian menunjukkan bahwa sebelum bergabung dengan geng motor, mereka melihat dirinya biasa saja, namun setelah bergabung dengan geng motor mereka merasa diri “pang aingna”. Anggota geng motor secara kognitif sebenarnya menyadari kalau diri yang ideal adalah menjadi “pemuda baik-baik” seperti yang diharapkan masyarakat. Namun, interaksi dengan teman-teman dalam geng motornya membuat mereka berperilaku “ideal” versi kelompok itu. Selain itu, tidak sepenuhnya benar anggapan tentang anggota geng motor berasal dari keluarga “broken home” namun, komunikasi dalam keluarga memang sangat minim.

  13. Pertunjukan Sandhur Ttuban Refleksi Peralihan Masyarakat Agraris Menuju Budaya Urban

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    Rohmat -

    2017-03-01

    ABSTRAK Pertunjukan Sandhurmerefleksikan perubahan masyarakat agraris menuju budaya urban. Dalam Teks pertunjukan Sandhurterdapat kode  hermeneutik, kode proairetik/tindakan naratif dasar, kode semantik,  kode kultural, dan kode simbolik.  Teks pertunjukan dapat dimaknai sebagai tanda dan simbol meresapnya budaya urban dalam kehidupan masyarakat Tuban. Hubungan manusia, Tuhan, alam, dan kebudayaan melekat pada struktur pertunjukan Sandhur.  Kehidupan manusia menjadi bagian dari siklus kosmis yang utuh. Untuk membaca, mendeskripsikan pertunjukan Sandhurdigunakan pendekatan kualitatif, peneliti menjadi instrumen utama.  Untuk memotret  fenomena alamiah pertunjukan  mengacu pada model etnografi. Untuk memahami teks pertunjukan Sandhur peneliti mempertajam analisis  interpretatif  terhadap “sosially meaningfull action” digunakan pendekatan semiotik.             Struktur pertunjukan, medium pertunjukan, serta ekspresi pelaku pertunjukan Sandhurdapat diamati melalui refleksi simbolis yang melekat pada pola penandaan. Gejala simbolik yang terurai secara sistematik dalam dinamika pertunjukan mengungkapkan substansi perubahan budaya desa yang disebabkan oleh proses urbanisasi.  Perubahan tatanan hidup sesuai dengan kodrat alamiah dan hukum perubahan ruang dan waktu.   Kata kunci: Sandur, masyarakat agraris, pertunjukan, tradisi.

  14. PENGANTAR

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    Redaksi Jurnal Filsafat

    2016-09-01

    Full Text Available Suatu realitas yang tidak terelakkan bahwa manusia itu makhluk multi-dimensi. Hubungan antara berbagai dimensi mendinamisasi eksistensi manusia, melahirkan kebudayaan dan membentuk peradaban. Watak multi-dimensi manusia tersebut juga berimplikasi terhadap adanya potensi paradoksal, yang pada gilirannya akan memunculkan persoalan-persoalan dalam kehidupan. Harmonisasi watak paradoksal manusia dan upaya penyelesaian permasalahan yang ditimbulkannya diupayakan dengan mencari metode-metode dan norma-norma sebagai acuan legitimasinya. Segala usaha dan pemikiran manusia dalam mencari metode-metode dan norma-norma ini, serta implementasinya akan membentuk kebudayaan dan peradaban. Dalam konteks Indonesia, bangsa Indonesia yang mengalami beragam pertentangan dan persoalan dalam dirinya telah dan sedang mencari berbagai metodologi dan desain untuk menghadapinya. Setiap kali bangsa Indonesia dihadapkan pada tantangan baru maka ia akan selalu menggali kembali sumber kebudayaannya untuk dijadikan patokan. Jurnal Filsafat Volume 21, nomor 1 April 2011 ini menampilkan artikel-artikel yang terkait dengan tema manusia dan kebudayaan, yaitu kajian tentang pemikiran Sutan Takdir Alisyahbana, Sören Kierkegaard, dan J.J. Rousseau serta dinamika masyarakat Indonesia di Halmahera Utara dan pada Suku Bugis- Makasar dalam memecahkan problem kebudayaannya. Semoga dapat menjadi bahan pemikiran kritis.

  15. MEMAKNAI KERAGAMAN: The Others dalam Konstruksi Sosial Para Elit Kelompok-kelompok Keagamaan di Kota Mataram

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    Fawaizul Umam

    2016-12-01

    Bertolak dari urgensi pelibatan pandangan masing-masing kelompok tentang the others dalam setiap inisiasi perdamaian, studi ini mengkaji (1 konstruksi sosial para elit kelompok-kelompok keagamaan di Kota Mataram tentang the others sekaligus menentukan (2 tipologinya berdasar tiga model utama keberagamaan, yakni eksklusivisme, inklusivisme, dan pluralisme. Para elit dipilih sebagai subjek karena mereka berperan signifikan dalam kelompok masing-masing. Dalam dinamika sosial masyarakat Muslim Kota Mataram, mereka kurang-lebih adalah ulama yang berperan sebagai “makelar budaya” sekaligus kreator aktif perubahan sosial. Untuk memahami konstruksi sosial para elit tentang the others, studi ini menerapkan teori konstruksi sosial Berger. Data utama digali dari para informan yang dipilih secara purposif, yakni mereka yang secara formal maupun informal memimpin kelompok-kelompok keagamaan Islam seperti Ahmadiyah, Salafi, Jama’ah Tabligh, Syi’ah, dan juga kelompok tradisionalis (Nahdlatul Wathan dan modernis (Muhammadiyah. Hasil kajian menunjukkan bahwa konstruksi sosial mereka muncul lewat tiga momen dialektik yang membentuk realitas subjektif sekaligus objektif tentang the others. Hal itu menentukan cara mereka selaku elit kelompok dalam memaknai dan menyikapi the others. Tipefikasinya menunjukkan, penyikapan mereka tentang the others cenderung eksklusif, dalam batas-batas tertentu inklusif, sementara tendensi pluralistik cenderung absen. Berdasar itu solusi berupa format ideal pengelolaan keragaman bagi penciptaan koeksistensi antarkelompok keagamaan di Kota Mataram diajukan.

  16. PAGAR UNTUK MENGURANGI INTRUSI POLUSI DEBU HALUS KE DALAM BANGUNAN

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    Thomas J. Scanlon

    2001-01-01

    Full Text Available The effects of fence in reducing particulate matter concentration from street traffic to adjacent buildings (i.e. houses were studied by using computational fluid dynamics. A variety of fence property: porosity, height,positions relative to the house and wind direction were investigated related to a constant set of weather data of a hot-humid country (i.e. Indonesia. This investigation shows that a solid fence, which is close proximity to the building, will give a considerable particulate matter reduction carried by an oblique wind direction of up to 11%. Abstract in Bahasa Indonesia : Ide dasar bahwa penyebaran suatu zat dapat dikurangi atau dihalangi dengan sistem bloking diuji dengan menggunakan metode komputasi dinamika fluida (CFD. Keragaman kondisi fisik pembatas antara sumber zat dan penerima zat meliputi : kerapatan, besaran (tinggi dan panjang, perletakan terhadap bangunan/jalan dan arah angin diuji pengaruhnya terhadap kemampuan mengurangi penyebaran debu halus dari jalan raya ke dalam bangunan yang lokasinya berdekatan dengan jalan tersebut. Kondisi cuaca yang menyertai pengujian dikhususkan pada kondisi iklim tropis lembab. Hasil pengujian menunjukkan bahwa pagar pembatas yang terbuat dari bahan dengan kerapatan 100% mampu mengurangi penyebaran debu halus di balik pagar sampai 11 %. Kata kunci: konsentrasi debu halus, pagar pembatas, kerapatan, jarak halaman, bangunan, CFD.

  17. PEMAHAMAN KEBERAGAMAAN DAN GERAKAN KELOMPOK FPI SURABAYA

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    Syamsul Ma’arif

    2017-08-01

      Sikap-sikap FPI (Front Pembela Islam di Indonesia selama ini terkesan ‘frontal’ dan melawan setiap bentuk kemunkaran. Aksi mereka, sebenarnya bisa dikatakan sebagai salah satu bentuk ekspresi terdalam dari sekelompok orang muslim dalam mengartikulasikan ajaran-ajaran agama yang dipeluknya, atau sebagai bentuk sikap “kesalehan” dalam memandang setiap keyakinan yang berbeda dengan keyakinan yang diyakininya. Apalagi dalam memandang persoalan yang jelas-jelas dianggap sebagai bentuk kemaksiatan, kesesatan dan penodaan agama. Maka respons dan reaksi mereka, sebagaimana hasil penelitian yang telah dilakukan penulis di Surabaya adalah dalam rangka menegakkan prinsip keimanan yang dianggap “benar” tadi. Tulisan ini bertujuan untuk memberikan informasi yang komprehensif tentang faktor apa saja yang melatari lahirnya kelompok-kelompok keagamaan kontemporer—terutama sekali FPI di Surabaya. Sekaligus mengetahui pemahaman keagamaan, aktifitas dan gerakan-gerakan kelompok FPI di daerah tersebut. Gambaran hasil penelitian ini pada akhirnya diharapkan mampu mengeliminasi kemungkinan kesalahpahaman informasi yang menjadi sebab timbulnya prejudice, dan stereotype yang merupakan langkah awal terjadinya konflik atau mengatasi konflik antar komunitas agama secara komprehensif. Sebab, dengan diketahui keanekaragaman kelompok-kelompok keagamaan dengan dinamika gerakannya  akan lebih memudahkan masyarakat agama untuk saling belajar satu sama lain.

  18. ISP33 standard problem on the PACTEL facility

    Energy Technology Data Exchange (ETDEWEB)

    Purhonen, H.; Kouhia, J. [VTT Energy, Lappeenranta (Finland); Kalli, H. [Lappeenranta Univ. of Technology (Finland)

    1995-09-01

    ISP33 is the first OECD/NEA/CSNI standard problem related to VVER type of pressurized water reactors. The reference reactor of the PACTEL test facility, which was used to carry out the ISP33 experiment, is the VVER-440 reactor, two of which are located near the Finnish city of Loviisa. The objective of the ISP33 test was to study the natural circulation behaviour of VVER-440 reactors at different coolant inventories. Natural circulation was considered as a suitable phenomenon to focus on by the first VVER related ISP due to its importance in most accidents and transients. The behaviour of the natural circulation was expected to be different compared to Western type of PWRs as a result of the effect of horizontal steam generators and the hot leg loop seals. This ISP was conducted as a blind problem. The experiment was started at full coolant inventory. Single-phase natural circulation transported the energy from the core to the steam generators. The inventory was then reduced stepwise at about 900 s intervals draining 60 kg each time from the bottom of the downcomer. the core power was about 3.7% of the nominal value. The test was terminated after the cladding temperatures began to rise. ATHLET, CATHARE, RELAP5 (MODs 3, 2.5 and 2), RELAP4/MOD6, DINAMIKA and TECH-M4 codes were used in 21 pre- and 20 posttest calculations submitted for the ISP33.

  19. PEACEFUL JIHĀD DAN PENDIDIKAN DERADIKALISASI AGAMA

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    Sulasman Sulasman

    2015-06-01

    *** Pondok Pesantren Miftahul Huda semula identik dengan gerakan “radikal” baik karena pandangan eksklusivismenya dalam beragama, kritisisme terhadap Pemerintah, maupun karena keidentikkan beberapa personalnya dengan gerakan DI/TII dan FPI. Sejalan dengan dinamika internal dan eksternal, pondok pe­santren ini pun mereorientasi gerakannya dari jihād fisik ke jalur pendidikan dan dakwah damai atau dalam perspektif Lukens-Bull dikenal sebagai jihad damai (peaceful jihād. Proses menjinakkan diri dan gerakannya, yang dikenal dengan deradikalisasi, dilalui oleh pondok pesantren ini dengan enam cara, yakni inter­nali­sasi nilai-nilai pesantren, perluasan perspektif keislaman, adopsi sistem sekolah, pendidikan hubb al-waṭan, penggunaan local wisdom, dan pendidikan keterampilan. Upaya deradikalisasi yang dilakukan Pondok Pesantren Miftahul Huda berkisar pada tiga strategi, yakni pencegahan, pemeliharaan budaya damai, dan pemulihan bagi yang terdampak radikal. Hasilnya, para santri, alumni, dan pesantren yang tergabung dalam sistem jaringan Pondok Pesantren Miftahul Huda muncul dalam wajah damai, moderat, dan toleran.

  20. PENGANTAR

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    Redaksi Jurnal Filsafat

    2016-09-01

    Full Text Available Kebudayaan itu bersifat cair dan dapat berubah. Sejarah mencatat, telah terjadi imperialisme budaya (cultural imperialism. Hegemoni budaya Barat telah “menyerbu” ke segala lapisan dunia, termasuk Indonesia. Imperialisme budaya ini dalam kurun waktu tertentu telah membuat manusia Indonesia melupakan keunggulan budaya Indonesia yang beranekaragam dan sarat dengan nilai-nilai spiritualitas. Manusia Indonesia mengalami krisis percaya diri. Dinamika manusia Indonesia telah melupakan historisitas dan karakateristik kultural Indonesia. Akibatnya, bukan kemajuan yang diperoleh, tetapi justru “tergagap-gagap” dengan budaya Barat. Terkait dengan hal di atas, Jurnal Filsafat Volume 19, nomor 1, April 2009 ini menyajikan artikel-artikel tentang dua corak budaya yang diilhami oleh nilai berbeda. Pertama, corak budaya Barat baik dalam ranah keilmuan, teknologi, dan ekspresi budaya. Representasi corak pertama ini ditampilkan dalam artikel pemikiran ekonomi Adam Smith, pengaruh kemajuan teknologi komunikasi televisi, dan artikel tentang satu bentuk ekspresi budaya Barat yakni simbol-simbol satanisme yang digandrungi generasi muda. Kedua, corak budaya khas Indonesia, yakni kearifan lokal Indonesia. Corak budaya ini direpresentasikan dalam artikel Kawruh Bimosuci yang sarat dengan nilai-nilai spiritual, dan refleksi kritis atas gagasan Prof. Mubyarto tentang Filsafat Ilmu Ekonomi Pancasila. Tim penyunting berharap, dengan menampilkan artikelartikel tersebut di atas, Jurnal Filsafat ini dapat memperkaya khasanah pemikiran para pembaca dan menjadi inspirasi dalam berkehidupan, serta dapat menjadi bahan pemikiran dalam menata ulang kebudayaan Indonesia.

  1. Teori Adult Learning, Ekspriental Learning Cycle Dan Perubahan Performance Individu Dalam Pendidikan Dan Pelatihan

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    Moh. Dannur

    2017-07-01

    Full Text Available Teori belajar merupakan hal yang sangat penting dalam Manajmen Pendidikan dan Pelatihan apabila ingin meraih hasil yang maksimal dalam proses transformasi pengetahuan. Adult Learning dan Ekspriental Learning Cycle salah satu teori yang paling masyhur di dalamnya. Dalam upaya meraih hasil yang maksimal juga perlu adanya pengetahuan tentang motivasi dan faktor-faktor dalam pengembangan individu, perubahan performanya, serta dinamika individu kelompok. Sehingga dengan pengetahuan yang dimilikiakan dengan mudah merealisasikan yang diinginkan. Kata kunci: Adult learning, expriental learning cycle, performance.  Learning theory is very important in Management of Education and Training if you want to achieve the maximum results in the transformation process of knowledge. Adult Learning and Expriental Learning Cycle are the most famous theories within it. In the effort to achieve the maximum results also needs the knowledge about motivation, the factors in the development of individuals, the changes of performance, and the dynamics of individual groups. So with this knowledge you will easily realize the thing you desired. Keywords: Adult learning, expriental learning cycle, performance.

  2. Wacana Apec: Legitimasi Dan Signifikasi Perekonomian Bali (Kajian Wacana Kritis Parawisata

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    Hugo Warami

    2015-04-01

    Full Text Available Wacana APEC dalam kajian ini akan dieskplorasi melalui paradigma kritis untuk melakukan konstruksi refleksif terhadap pengalaman wacana-wacana pariwisata yang tumbuh dan berkembang pada masyarakat pelaku pariwisata di Bali. Fokus kajian pada wacana APEC ini mencakup (1 legitimasi dan (2 signifikasi konstruksi wacana yang berdampak langsung pada perekonomian Bali melalui perspektif critical discourse analysis (CDA. Perspektif ini memberikan penekanan pada determinasi pariwisata dan ekonomi kreatif, yakni segala sesuatu yang sedang, akan, dan nanti terjadi melalui wacana APEC, dan berdampak langsung pada kekuatan-kekuatan ekonomi. Legitimasi akan membantu membuat objektivasi yang sudah dilembagakan menjadi tersedia secara objektif dan masuk akal secara subjektif. Sedangkan signifikasi merupakan salah satu struktur wacana yang mengacu pada sistem, mengharuskan adanya relasi yang tidak dapat dipisahkan antara sebuah tanda dan realitas yang menjadi rujukannya serta bersifat ikonis. APEC 2013 yang diwacanakan berlangsung di Bali, akan berdampak besar pada pembangunan sektor pariwisata. Setidaknya, signifikasi perubahan dan dinamika yang terjadi di tingkat nasional, regional dan internasional akan dikonstruksi dan didayagunakan secara bersama dalam menyelesaikan berbagai persoalan yang sama pada sesama negara anggota APEC. Untuk analisis CDA, fakta bahasanya diperoleh dari media massa (surat kabar lokal Bali, yakni (1 Bali Post dan (2 Media Bali Promosi.

  3. Desain Kontrol Tracking Underactuated Autonomous Underwater Vehicle (AUV dengan Pengaruh Gangguan Arus Laut

    Directory of Open Access Journals (Sweden)

    Ilmi Rizki I

    2016-11-01

    Full Text Available Paper ini membahas masalah gerak AUV pada bidang horizontal yang dipengaruhi oleh arah sudut yaw. Arah sudut yaw merupakan ukuran utama dalam mengatur gerak horizontal pada AUV. Pengaturan gerak pada AUV berupa perubahan arah sudut yaw merupakan permasalahan kontrol tracking AUV. Kontrol tracking pada paper ini digunakan untuk kebutuhan heading control. Heading control tersebut digunakan untuk mengatur arah sudut yaw AUV agar sesuai dengan sinyal referensi yaw yang diberikan. Kompleksitas dalam mendesain heading control akibat karakteristik-karakteristik dari dinamika AUV yang high nonlinear dan uncertainty parameter yang ditentukan oleh hydrodynamic forces dan environmental forces berupa gangguan ocean current menjadi permasalahan yang tidak mudah dipecahkan. Oleh karena itu dibutuhkan sebuah metode untuk mengatasi permasalahan tersebut, yaitu menggunaan metode State Dependent Riccati Equations berdasarkan Linear Quadratic Tracking (SDRE-LQT. Algoritma ini menghitung perubahan permasalahan tracking pada sudut yaw dan dapat mengatasi gangguan ocean current melalui perhitungan perubahan parameter dari AUV secara online melalui algebraic Riccati equation.sehingga sinyal kontrol yang diberikan ke plant dapat mengikuti perubahan kondisi dari plant itu sendiri, termasuk perubahan parameter akibat gangguan berupa ocean current. Hasil simulasi menunjukkan bahwa metode kontrol yang digunakan mampu membawa sudut yaw pada nilai yang diharapkan dan gangguan arus dapat diatasi dengan memberikan nilai sinyal kontrol yang baru secara online, sehingga AUV dapat melakukan  tracking secara otomatis pada kondisi ada atau tanpa gangguan ocean current dengan dengan nilai error steady state . Kata kunci — AUV, Tracking Control, SDRE-LQT, Ocean Current Disturbance

  4. THE RECONSTRUCTION OF ISLAMIC THEOLOGY IN THE UNITY OF SCIENCES

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    Yusriyah Yusriyah

    2015-12-01

    Sebagai hasil dari pemikiran konsep teologis teologi Islam dapat berubah sesuai dengan dinamika sosial. Dalam era kontemporer teologi dapat dikaji oleh ilmu-ilmu interdisipliner, yang akhirnya teologi merupakan sumber lahirnya beberapa ilmu sehingga ilmu yang dihasilkan oleh pemahaman tawḥīd akan menghasilkan agama damai bagi alam semesta (raḥmatan li ’l-‘ālamīn. Data yang disajikan dalam artikel ini berasal dari penelaahan terhadap literatur yang terkait dengan topik penulisan. Dengan pendekatan kualitatif artikel ini menunjukkan bahwa agama dan sains memiliki titik singgung. Ilmu membantu memfasilitasi manusia dalam kehidupan keagamaannya. Dengan iman, kegiatan ilmiah dapat memper­kuat iman dan mem­buat motivasi untuk mengekspresikan sesuatu yang dapat menambah peng­akuan terhadap Allah sebagai pusat kesatuan eksistensi (tawḥīd. Untuk me­wujudkan ketersinggungan antara iman dan ilmu maka perlu islamisasi ilmu pengetahuan dan juga dalam upaya untuk merekonstruksi teologi ke format yang dapat berdialog dengan realitas perkembangan pemikiran yang berlangsung hari ini.

  5. Team building from a psychodynamic perspective

    Directory of Open Access Journals (Sweden)

    F. v. N. Cilliers

    2000-06-01

    Full Text Available The aim of this research is to measure the impact of a psychodynamic, Tavistock stance, team building event. Its task is to provide opportunities for learning about team behaviour and dynamics. Consultants offer interpretations in the form of working hypotheses about what is happening in the here-and-now. This refers to the basic assumptions (dependency, fight/flight, pairing and its relevant dynamic concepts. Post measured, qualitative research findings, indicate an increase in knowledge about the teams unconscious behaviour, a realisation of own identity, boundaries, potential and a strong sense of empowerment to act collectively in problem solving. Opsomming Die doel van die navorsing is om die impak van'n psigodinamiese, Tavistock beskouing, spanbou gebeurtems, te meet. Die taak is om leergeleenthede beskikbaar te stel oor eie spangedrag en -dinamika. Konsultantc bicd interpretasies aan in die vorm van werkshipoteses oor die gebeure in die hier-en-nou. Dit verwys na die basiese aannames (afhanklikheid, veg/vlug, afparing en die relevante dinamiese konsepte. Post-gemete, kwalitatiewe navorsingsresultate, dui op n toename in kennis oor die span se onbewuste gedrag, n beset van eie identiteit, grense, potensiaal en 'n sterk sin van bemagtiging om op 'n kollektiewe wyse op te tree in probleemoplossing.

  6. Perancangan dan Implementasi Kontroler PID untuk Pengaturan Heading dan Pengaturan Arah pada Fixed-Wing Unmanned Aerial Vehicle (UAV

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    Hery setyo widodo

    2012-09-01

    Full Text Available UAV (Unmanned Aerial Vehicle merupakan kendaraan udara tanpa awak yang dikendalikan dari jarak jauh oleh atau tanpa seorang pilot (Autopilot. Kontrol pesawat UAV ada dua variasi utama, variasi pertama yaitu dikontrol melalui pengendali jarak jauh dan variasi kedua adalah pesawat yang terbang secara mandiri berdasarkan program yang dimasukan. Sebuah fixed-winng UAV harus mampu mempertahankan posisinya pada lintasan yang sudah ditentukan selama melakukan tracking lintasan. Keakuratan dalam tracking arah dan heading pesawat sangat berpengaruh terhadap keberhasilan misi penerbangan pesawat UAV dalam memperthankan lintasannya untuk mencapai target. Oleh karena itu pada Tugas Akhir ini dirancang sistem pengaturan dengan menggunakan metode kontrol PID untuk mengatasi kesalahan dalam menjaga lintasan pesawat. Pengaturan arah dan heading pesawat UAV dilakukan dengan memanfaatkan dinamika gerak lateral yang meliputi gerak roll dan yaw dan input dari GPS (Global Positioning System. Dari simulasi diperoleh proses tracking dapat mengikuti rancangan gerak yang diinginkan Pergeseran lintasan pesawat pada saat implementasi kontroler PID disebabkan akurasi GPS yang masih rendah yaitu 3 meter.

  7. Kaum Muda, Meme, dan Demokrasi Digital di Indonesia

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    Sandy Allifiansyah

    2017-01-01

    Full Text Available Abstract: Internet appears as a new medium for youth generation to shape and to articulate discourses in a unique ways known as internet meme. In Indonesia, internet meme is not an expression of youth jokes, but also their reflection through everday lives issues, like democracy, social, and politics. The discourse battleground in particular internet memes expands the democracy itself. This research examines the dynamics of discourse in two biggest Indonesian political controversy in 2014 by using Anthony Giddens’ structuration. Abstrak: Internet menjadi medium baru kaum muda untuk membentuk wacana dan mengartikulasikannya ke dalam sebuah bentuk yang unik, yakni internet meme. Di Indonesia, meme digunakan sebagai ekspresi lelucon sekaligus refleksi kaum muda terhadap kehidupan sehari-hari menyangkut aspek-aspek demokrasi, sosial, dan politik. Adu wacana antar kaum muda via meme yang tersebar di internet mengenai isu-isu sosial politik, memperluas spektrum demokrasi. Riset ini melihat dinamika wacana dalam internet meme mengenai dua isu politik besar di Indonesia pada tahun 2014 dengan menggunakan pendekatan stukturasi milik Anthony Giddens.

  8. Intensitas Budaya dalam Dunia Kepenarian

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    I Nyoman Chaya

    2014-09-01

    ABSTRAK   Penelitian ini bertujuan untuk mengungkap pemaknaan budaya yang terbangun dalam suatu fenomena ketika seseorang larut dalam petualangan dirinya dalam dunia kepenarian. Permasalahannya menyangkut proses kehidupan manusia yang menjelma ke dalam ber- bagai aktivitas yang dilampauinya sepanjang ia menekuni profesinya sebagai seniman tari (penari. Hal yang menjadi pertanyaan adalah sejauh mana konsistensi petualangan dunia kepenarian tersebut dapat memberikan kontribusi bagi nilai-nilai kehidupan membudaya, khususnya nilai-nilai yang melekat pada kehidupan pribadi manusia dalam rangka mem- bangun kesadaran atas jati dirinya sebagai seorang penari. Untuk memecahkan permasa- lahan tersebut digunakan pendekatan budaya dengan mengaplikasikan teori ideologi de- ngan perolehan data yang kemudian dicermati melalui analisis terhadap proses kehidupan penari pada umumnya serta didukung dengan pengalaman pribadi penulis yang sampai saat ini aktif berkecimpung selaku penari.  Melalui suatu kajian  terhadap aktivitas dalam kepenarian serta kesadaran terhadap dinamika kehidupan yang dialami, dipahami, dan dihayati oleh seorang penari maka terungkap suatu pemaknaan yang mengindikasikan munculnya intensitas budaya. Intensitas budaya tersebut terpatri menjadi sebuah potensi atau kekuatan yang melekat pada pribadi manusia (penari. Hal ini memberikan arti pada kehadiran suatu nilai yang dapat diidentifikasi sebagai eksistensi diri manusia.   Kata kunci: intensitas budaya, dunia kepenarian, eksistensi diri

  9. Validation of the high performance leadership competencies as measured by an assessment centre in-basket

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    H. H. Spangenberg

    2003-10-01

    Full Text Available The purpose of this study was to validate Schroder’s High Performance Leadership Competencies (HPLCs, measured by a specially designed In-basket, against multiple criteria. These consisted of six measures of managerial success, representing managerial advancement and salary progress criteria, and a newly developed comprehensive measure of work unit performance, the Performance Index. An environmental dynamism and complexity questionnaire served as moderator variable. Results indicated disappointing predictive validity quotients for the HPLCs as measured by an In-basket, in contrast to satisfactory predictive and construct validity obtained in previous studies by means of a full assessment centre. The implications of the findings are discussed and suggestions are made for improving the validity of the In-basket. Opsomming Die doel van hierdie studie was die validering van Schroder se Hoëvlak Leierskapsbevoegdhede, gemeet deur ‘n spesiaal ontwerpte Posmandjie, teen veelvoudige kriteria. Dit behels ses metings van bestuursukses wat bestuursbevorderings- en salarisvorderingskriteria insluit, sowel as ‘n nuutontwikkelde, omvattende meting van werkeenheidsprestasie, die Prestasie indeks. ‘n Vraelys wat die dinamika en kompleksiteit van die omgewing meet, het as moderator veranderlike gedien. Resultate dui op teleurstellende geldigheidskwosiënte vir die Hoëvlak Leierskapsbevoegdhede soos gemeet deur ‘n posmandjie, in teenstelling met bevredigende voorspellings- en konstrukgeldigheid wat in vorige studies deur middel van ‘n volle takseersentrum verkry is. Die bevindinge word bespreek en voorstelle word gemaak om die geldigheidskwosiënte te verbeter.

  10. Research nuclear reactor RA - Annual Report 1994; Istrazivacki nuklearni reaktor RA - Izvestaj za 1994. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1994-12-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Activities related to improvement of Russian project were continued in 1994. Control and maintenance of the reactor components was done regularly and efficiently. Extensive repair of the secondary coolant loop is almost finished and will be completed in the first part of 1995 according to existing legal procedures and IAEA recommendations. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1994. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i

  11. RA Research reactor, Annual report 1973; Istrazivacki nuklearni reaktor RA - Izvestaj za 1973. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1973-12-15

    podatke o radu i eksperimentima koji su obavljani. U toku godine bilo je 12 sigurnosnih zaustavljanja, od cega 7 zbog zbog elektricnog napona. Od tri zaustavljanja ciji je uzrok bila oprema, dva su bila zbog otkazivanja novih elektronskih cevi. Od dva zaustavljanja koja je izazvalo pogonsko osoblje, jedno je bilo usled nepazljivog ukljucivanja pomocnog potrosaca, a drugo je ucinio operator jer se cinilo da snaga reaktora naglo raste. Kracih prekida rada bilo je tri, usled najavljenog iskljucenja napona. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta. Dekontaminirano je znatno manje povrsina nego ranijih godina, i sakupljeno manje otpada nego prethodnih godina, dok tecnih efluenata nije bilo. Zakljuceno je da uspesan rad reaktora u 1973. godini ima poseban znacaj kada se ima na umu kriza finansiranja izazvana neblagovremenim resavanjem statusa reaktora. Mnogi goruci problemi nisu reseni: kompletiranje rezervnih delova, zamena nekih elemenata opreme, zamena nekih instrumenata, i nabavka visokoobogacenog goriva.

  12. Ventilation system in the RA reactor building - design specifications; Sistem ventilacije u objektu 'RA' - Tehnicki opis

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1984-09-15

    Protective role of the ventilation system of nuclear facilities involve construction of ventilation barriers which prevent release of radioactive particulates or gases, elimination od radioactive particulates and gases from the air which is released from contaminated zones into the reactor environment. Ventilation barriers are created by dividing the building into a number of ventilation zones with different sub pressure compared to the atmospheric pressure. The RA reactor building is divided into four ventilation zones. First zone is the zone of highest risk. It includes reactor core with horizontal experimental channels, underground rooms of the primary coolant system (D{sub 2}O), helium system, hot cells and the space above the the reactor core. Second zone is the reactor hall and the room for irradiated fuel storage. The third zone includes corridors in the basement, ground floor and first floor where the probability of contamination is small. The fourth zone includes the annex where the contamination risk is low. There is no have natural air circulation in the reactor building. Ventilators for air input and outlet maintain the sub pressure in the building (pressure lower than the atmospheric pressure). This prevents release of radioactivity into the atmosphere. Zastitne uloge ventilacionog sistema kod nuklearnih postrojenja obuhvataju formiranje ventilacionih barijera koje onemugucavaju sirenje radioaktivnih cestica ili gasova putem cirkulacije vazduha; eliminaciju radioaktivnih cestica i gasova iz vazduha koji se evakuise iz kontaminiranih prostora u okolinu reaktorskog postrojenja. Formiranje zastitnih ventilacionih barijera ostvaruje se obicno podelom unutrasnjosti objekta na vise ventilacionih zona razlicitih podpritisaka u odnosu na spoljni atmosferski pritisak. Celi prostor zgrade reaktora RA podeljen je u cetiri ventilacione zone. Prva zona je zona najveceg rizika, u koju spadaju reaktorsko jezgro sa horizontalnim eksperimentalnim kanalima, tehnoloske

  13. Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I; Tehnicka realizacija projekta VISA-2, ugovor: 2.01/I faza, Album br. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis. [Serbo-Croat] Saradnja izmedju Instituta u Vinci i Saclay-u zapoceta je realizacijom zadatka 'Tehnicka realizacije projekta VISA-2' koji treba da omoguci: dobijanje novih eksperimentalnih prostora u reaktoru RA sa visokom vrednoscu fluksa brzih neutrona za ozracivanje uzoraka; sticanje pogonskih iskustava u visemesecnom kontilualnom radu na nominalnoj snazi od 6,5 MW i povecanje stepena koriscenja reaktora RA; resenje pitanja transporta aktivnih kanala i uzoraka, problema rada u vrucim celijama; dobijanje ozracenih uzoraka za izucavanje, u prvo vreme u Saclay-u, a kasnije i u Vinci

  14. One procedure for determination of the neutron flux in the nuclear reactor fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V; Krtil, J; Maksimovic, Z; Martinc, R [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1979-09-15

    Possibility of determination of the neutron flux in the fuel of a heavy water reactor has been examined. In determination of the flux an iterative procedure was used to compare calculated and measured contents of several fission products. The former contents were determined by calculation of the burning process balance and the latter by non-destructive gamma-spectrometric analysis of fuel. The obtained results prove the possibility of such determination of not only the average value of the flux but also of the change of its intensity during utilization of fuel (author) U radu je ispitivana mogucnost odredjivanja fluksa neutrona u gorivu teskovodnog nuklearnog reaktora. Pri odredjivanju fluksa koriscen je iterativni postupak, u kome se porede izracunati i izmereni sadrzaji nekoliko gama-radioaktivnih fisionih produkata. Prvi sadrzaji su odredjivani preko proracuna bilansa procesa sagorevanja, a drugi - nedestruktivnom gama-spektrometrijskom analizom goriva. Dobijeni rezultati potvrdjuju mogucnost ovakvog odredjivanja ne samo srednje vrednosti fluksa, vec i promene njegovog intenziteta u toku koriscenja goriva (author)

  15. Investigation of corrosion of materials of the irradiation device in the RA reactor; Ispitivanje korozije materijala uredjaja za ozracivanje na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Zaric, M; Mance, A; Vlajic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Devices for sample irradiation in the vertical RA reactor channels will be made of aluminium alloys. According to the regulations concerned with introducing materials into the RA reactor core, corrosion characterisation of these materials is an obligation. Corrosion properties of four aluminium alloys were investigated both in contact with stainless steel and without it. First part of this report deals with the corrosion testing of aluminium alloys in water by gravimetric and electrochemical methods. Bi-distilled water at temperatures less than 100 deg C was used. Second part is related to aluminium alloys corrosion in carbon dioxide gas under experimental conditions. The second part of research was initiated by the design of the head of the independent CO{sub 2} loop for samples cooling. [Serbo-Croat] Uredjaji za ozracivanje u vertikalnim kanalima reaktora RA, bice napravljeni od legura aluminjuma. Prema propisima o unosenju materijala u RA reaktor materijali se moraju prethodno ispitati i sa stanovista korozije. Ispitivane su korozione pojave na cetiri aluminjumske legure sa i bez kontakta sa nerdjajucim celikom. Prvi deo ovog rada tretira pitanje korozije legura aluminijuma u vodi gravimetrijskim i elektrohemijskim metodama. Koriscena je bidestilovana voda na temperaturi do 100 deg C. Drugi deo se odnosi na ispitivanje ponasanja legura aluminijuma u gasovitom ugljen dioksidu pod uslovima eksperimenta. Drugi deo istrazivanja izvrsen je za potrebe izgradnje glave petlje nezavisnog kola za hladjenje uzoraka gasovitim CO{sub 2}.

  16. RA reactor building and installations; Zgrada 'RA' i instalacije

    Energy Technology Data Exchange (ETDEWEB)

    Badrljica, R; Sanovic, V; Skoric, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1985-08-15

    RA reactor building is made of reinforced concrete and bricks. It is closed facility with a limited number of controlled openings, doors and windows. The site of the building is 100 m above the sea level, 20 m above the mean Danube level and 8 m above the level of the neighbouring stream Mlaka. The building consists of three parts: central prismatic part, annex - surrounding the central part and the sanitary corridor. The biggest space is the reactor hall. In addition to the detailed description and drawings of the reactor building this documents includes design specifications of: electrical installation, water supply system, sewage system, ventilation and heating, gas and compressed air systems. A separate chapter is devoted to fire protection. Zgrada reaktora RA izgradjena je od armiranog betona i opeke, kao zatvoreni objekat ogranicenog broja kontolisanih otvora, sa ogranicenim brojem vrata i prozora. Plato na kojem je zgrada izgradjena nalazi se na 100 m nadmorske visine, na 20 m iznad srednjeg vodostaja Dunava i 8 m iznad nivoa obliznjeg potoka Mlaka. Zgrada se sastoji iz tri dela: sredisnjeg prizmaticnog dela, aneksa - prstenastog okvira sredisnog dela i sanitarnog propusnika. Pojedinacno najveci prostor zauzima reaktorska hala. Pored detaljnog opisa i plana zgrade, ovaj dokument sadrzi projekat elektricne instalacije, projekat vodovoda i kanalizacije, ventilacije i grejanja, instalacije gasa i komprimovanog vazduha. Posebno poglavlje posveceno je protivpozarnoj zastiti.

  17. RA Research reactor, Annual report 1969; Istrazivacki nuklearni reaktor RA - Izvestaj za 1969. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-12-15

    years of operation as well as purification of heavy water. [Serbo-Croat] Reaktor RA je u 1969. godini radio na nominalnoj snazi 200 dana i 15 dana na manjim snagama. Ukupni rad iznosio je 31131 MWh odnosno 3.77% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimenta prema zahtevima 463 korisnika iz Instituta i 63 izvan Instituta. Ovaj izvestak sadrzi detaljne podatke o snazi na kojoj je reaktor radio tokom 1969. godine i o uradjenim eksperimentima. Zakljuceno je da je reaktor RA uspesno radio prema planu rada. Da nije bilo problema sa napajanjem elektricnom energijom tokom poslednja tri meseca i niskog vodostaja Dunava u septembru i oktobru protekle godine bila bi to najuspesnija godina od pustanja reaktora u pogon. Broj sigurnosnih zaustavljanja nije bio veci u odnosu na prethodne dve godine i pored poteskoca u poslednjem kvartalu. Osoblje je bilo izlozeno povecanim dozama zracenja usled tri incidenta. Jedan je bio raspadanje kenera sa srebrom (zbog duzeg stajanja u aktivnoj zoni), sto je uzrokovalo kontaminaciju radne platforme, tako da je fon porastao za 10 do 100 puta od normalnohg Druga dva slucaja su bila otkazivanje uredjaja za mesanje goriva u tehnoloskim kanalima. Zamena goriva je radjena cetiri puta u toku godine, utroseno je 499 svezih gorivnih elemenata. Primenjena je metoda mesanja svezih gorivnih elemenata sa koriscenim gorivnim elementima u gorivnom kanalu. Dekontaminacija povrsina bila je na nivou prethodnih godina i pored problema sa srebrom. Kako su sa reaktora tokom godine otisla dva saradnika sa visokom spremom broj ljudi je opao na neophodan minimum za pogon i odrzavanje reaktora. Navrsavajuci u ovoj godini deset godina rada moze se reci da su rad i stanje opreme na tehnicki solidnom nivou. Kako bi se posle deset godina rada izvrsila kontrola vaznih komponenti reaktora i obavila rekoncentracija teske vode, za 1970. godinu je planirano da se proizvodnja smanji na 25000 MWh, a baziran je na istim principima kao i planovi za prethodne

  18. Neutron Diffractometer; Neutronski difraktometar

    Energy Technology Data Exchange (ETDEWEB)

    Zivadinovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-12-15

    RA nuclear reactor is considered as a relatively strong neutron source producing the thermal neutron flux of about 3x10{sup 13} n/cm{sup 2} sec when operating at nominal power of 6.5 MW. Neutron diffraction method is applied in the field of solid state physics, material science, crystallography, magnetism, nuclear physic. Neutron diffractometer at the RA reactor consists of: system for obtaining collimated neutron beam from the horizontal experimental channel neutron monochromator; goniometer and electronic equipment for measurements and collecting the the measurement data. Nuklearni reaktor RA koji pri radu na snazi od 6,5 MW ima fluks termalnih neutrona oko 3x10{sup 13} n/cm{sup 2} sec predstavlja relativno jak izvor neutrona. Tehnika difrakcije neutrona primenjuje se u istrazivanjima fizike crvstog stanja, strukture materijala, kristalografije, magnetizma, nuklearne fizike. Neutronski difraktometar na reaktoru RA sastoji se od sistema za dobijanje kolimisanog snopa neutrona kroz horizontalni kanal reaktora; neutroskog monohromatora; goniometra i elektronskih uredjaja za merenja i registrovanje rezultata. Ovaj izvestaj sadrzi detaljan opis i seme neutronskog difraktometra sa pratecom opremom i elektronskim komponentama.

  19. Dosimetry and radiation shielding at the RA reactor, Annual report 1975, Annex 5; Prilog 5 - Dozimetrija i tehnicka zastita

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    In the working environment at the RA reactor, the level of gamma radiation is measured continuously by the built-in stationary system. According to the needs, measurement are done in the reactor hall every day. The level of gamma radiation is measured separately in typical points