ANALISIS PENYEBAB BANJIR KALI JUANA

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Teguh Marhendi

2017-04-01

Full Text Available Kali Juana yang berada di Kabupaten Pati dan Kudus serta sebagian kecil di Kabupaten Grobogan dan Blora, merupakan kawasan banjir. Kejadian banjir di Kali Juana, sudah menjadi rutinitas setiap musim hujan.Dari Januari sampai bulan Mei 2016tercatat terjadi 11 kejadian banjir dibeberapa wilayah, seperti Kecamatan Kaliwungu, Undaan dan Mejobo (Kab. Kudus serta Pati, Margorejo dan Juwana (Kab. Pati. Kali Juana merupakan bifurkasi Kali Serang pada Pintu Wilalung, yang berfungsi sebagai pintu pengatur banjir (dibangun pada zaman Belanda tahun 1918, melalui Kali Babalan menuju ke Kali Juana. Tulisan inidimaksudkan untuk menganalisis penyebab kejadian banjir di Kali Juana. Analisis dilakukan dengan melakukan kajani dan analisis hujan serta mekanisme aliran. Hasil analisis menunjukkan bahwa kondisi Kali Juana dari pertemuan Kali Logung di pintu Wilalung sampai hilir telah mengalami pendangkalan akibat kemiringan dasar atau topografi yang landai, dan mengakibatkan mudah terjadi sedimentasi sehingga mengurangi kapasitas pengaliran. Hal ini menyebabkan luapan banjir sering menggenangi wilayah Kabupaten Kudus dan Pati.

Analisi matematica

CERN Document Server

Canuto, Claudio

2014-01-01

Il presente testo intende essere di supporto ad un secondo insegnamento di Analisi Matematica in quei corsi di studio (quali ad esempio Ingegneria, Informatica, Fisica) in cui lo strumento matematico parte significativa della formazione dell'allievo. I concetti e i metodi fondamentali del calcolo differenziale ed integrale in più variabili, le serie di funzioni e le equazioni differenziali ordinarie sono presentati con l'obiettivo primario di addestrare lo studente ad un loro uso operativo, ma critico. L'impostazione didattica dell'opera ricalca quella usata nel testo parallelo di Analisi Matematica I. La modalità di presentazione degli argomenti ne permette un uso flessibile e modulare. Lo stile adottato privilegia la chiarezza e la linearità dell'esposizione. Il testo organizzato su due livelli di lettura. Uno, più essenziale, permette allo studente di cogliere i concetti indispensabili della materia, di familiarizzarsi con le relative tecniche di calcolo e di trovare le giustificazioni dei principali r...

ANALISIS SEBARAN RADIONUKLIDA PADA KONDISI NORMAL UNTUK REAKTOR AEC 1000 MW

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Sri Kuntjoro

2015-03-01

Full Text Available Telah dilakukan analisis sebaran radionuklida pada reaktor daya Atomic Energy Agency (AEC 3568 MWTh, setara dengan 1000 Mwe untuk kondisi operasi normal. Analisis dilakukan untuk dua reaktor yang terpisah sejauh 500 m dan sudut 90o satu dengan yang lain. Langkah awal dalam melakukan analisis adalah menentukan suku sumber reaktor menggunakan program komputer ORIGEN2 dan EMERALD NORMAL. ORIGEN2 digunakan untuk menentukan inventori radionuklida yang terdapat di reaktor. Selanjutnya dengan dengan menggunakan program EMERALD NORMAL dihitung suku sumber yang sampai ke cerobong reaktor. Untuk menganalisis dosis yang diterima penduduk dilakukan dengan menggunakan program PC-CREAM. Perhitungan dilakukan untuk satu dan dua PLTN di calon tapak PLTN. Hasil yang diperoleh adalah sebaran radionuklida terbesar untuk satu PLTN pada jarak 1 km dan kearah zona 9 (191,25o dan untuk dua PLTN pada jarak 1 km dan kearah zona 10 (213,75o. Radionuklida yang sampai ke penduduk melalui dua alur yaitu alur makanan dan hirupan. Untuk alur makanan berasal dari radionuklida I-131, dan terbesar melalui alur produk susu sebesar 53,40 % untuk satu maupun dua PLTN . Untuk alur hirupan ranionuklida pemberi kontribusi paparan terbesar berasal dari Kr-85m sebesar 53,80 %. Dosis total terbesar yang diterima penduduk terdapat pada jarak 1 Km untuk bayi yaitu sebesar 4,10 μSi dan 11,26 μSi untuk satu dan dua PLTN. Hasil ini sangat kecil dibandingkan dengan batas dosis yang diijinkan oleh badan pengawas (BAPETEN untuk penduduk yaitu sebesar 1 mSi. Kata Kunci : Reaktor daya, komputer code, radionuklida, alur makanan, hirupan   Analysis for radionuclide dispersion for the Atomic Energy Agency (AEC 3568 MWth Power Reactor, equal to the 1000 MWe at normal condition has been done. Analysis was done for two piles that is separated by 500 m distance and angle of 90o one to other. Initial pace in doing the analysis is to determine reactors source term using ORIGEN2 and EMERALD NORMAL

Split core experiments; Part I. Axial neutron flux distribution measurements in the reactor core with a central horizontal reflector

Energy Technology Data Exchange (ETDEWEB)

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

1965-05-01

A series of critical experiments were performed on the RB reactor in order to determine the thermal neutron flux increase in the central horizontal reflector formed by a split reactor core. The objectives of these experiments were to study the possibilities of improving the thermal neutron flux characteristics of the neutron beam in the horizontal beam tube of the RA research reactor. The construction of RA reactor enables to split the core in two, to form a central horizontal reflector in front of the beam tube. This is achieved by replacing 2% enriched uranium slugs in the fuel channel by dummy aluminium slugs. The purpose of the first series of experiments was to study the gain in thermal neutron component inside the horizontal reflector and the loss of reactivity as a function of the lattice pitch and central reflector thickness.

ANALISIS VARIABILITAS CURAH HUJAN DAN SUHU DI BALI

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Ogi Setiawan

2017-01-01

Full Text Available Indonesia sebagai negara kepulauan yang terdiri dari pulau-pulau besar dan kecil menjadi sangat rentan terhadap dampak perubahan iklim. Salah satu pulau yang juga rentan terhadap perubahan iklim adalah pulau Bali. Dampak potensial adanya perubahan iklim adalah perubahan pola hujan, peningkatan suhuudaradankenaikanpermukaanlaut. Sektoryangakanmenerimadampakperubahaniklimdengan serius adalah sektor kehutanan dan pertanian. Untuk mendukung upaya mitigasi dan adaptasi maka diperlukan informasi perubahan iklim yang terjadi. Penelitian ini bertujuan untuk mengetahui variabilitas iklim di Bali. Metode yang digunakan adalah analisis kecenderungan curah hujan, analisis perubahan suhu udara, analisis perubahan tipe iklim dan analisis pergeseran bulan basah, lembab dan kering. Data hujan yang digunakan adalah data hujan dari GPCC (1961-1998 dan BMKG Bali (19992008, sedangkan data suhu berasal dari BMKG Bali (2004-2008. Hasil analisis menunjukkan bahwa di pulau Bali secara umum sudah mengalami perubahan iklim. Tipe iklim berdasarkan Schmidt-Ferguson mengalami perubahan dari relatif basah menjadi agak kering. Suhu udara rata-rata bulanan serta curah hujan bulanan dan tahunan memiliki kecenderungan yang semakin meningkat. Bulan basah dan bulan kering telah mengalami pergeseran dan perubahan jumlahnya. Dampak perubahan iklim terhadap ekosistem hutan di Bali belum diketahui dengan pasti, namun terdapat beberapa implikasi perubahan iklim terhadap sektor kehutanan diantaranya kebakaran hutan dan perubahan jadwal penanaman.

ANALISIS POSITIONING RESTORAN CEPAT SAJI

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Osa Omar Sharif

2017-04-01

Full Text Available Penelitian ini bertujuan untuk meneliti positioning restoran cepat saji McDonald's, Kentucky Fried Chicken, California Fried Chicken, A&W, dan Texas Chicken. Penelitian dilakukan di Kota Bandung dengan mengambil sebanyak 400 responden. Analisis yang digunakan dalam penelitian ini adalah analisis multidimensional scaling, analisis memberikan gambaran positioning dari restoran cepat saji yang ditampilkan dalam perceptual map. Restoran cepat saji yang memiliki layanan paling baik adalah McD dan yang memiliki layanan paling buruk adalah CFC. Restoran cepat saji yang memiliki rasa makanan paling enak adalah McD dan yang memiliki rasa makanan tidak enak adalah CFC. KFC dinilai paling ideal karena selalu berhasil menduduki peringkat satu dan dua jika dilihat dari sudut pandang restoran cepat saji yang lain. Pesaing terdekat McD adalah KFC. McD mendapatkan ranking pertama dari segi atribut layanan, kebersihan, variasi makanan, dan rasa makanan. Dengan posisi seperti ini McD seharusnya tetap menjaga kualitas layanan, kebersihan, variasi makanan, dan rasa makanan agar konsumen tetap memilih untuk datang ke McD. KFC sebaiknya tetap menjaga suasana yang membuat konsumen nyaman akan suasana di dalam atau diluar restoran

Maintainability considerations for the central cell in WITAMIR-I, a conceptual design of a tandem mirror fusion power reactor

International Nuclear Information System (INIS)

Sviatoslavsky, I.N.

1980-10-01

The concepts for maintaining the central cell reactor components for WITAMIR-I are described. WITAMIR-I is a conceptual tandem mirror fusion power reactor utilizing thermal barriers designed by the University of Wisconsin-Madison. Unique solutions to the difficult problems of routine blanket replacement and maintenance are proposed. Solutions are also proposed for maintaining the central cell coils and the shield

IDENTIFIKASI MISKONSEPSI SISWA SMP PADA KONSEP FOTOSINTESIS MELALUI ANALISIS GAMBAR

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Devi Ariandini

2014-01-01

Full Text Available Tujuan dari penelitian ini adalah untuk mengidentifikasi miskonsepsi siswa dengan analisis menggambar. Tiga puluh empat siswa di kelas 8 di sekolah menengah pertama digunakan sebagai subyek dalam penelitian ini. Teknik sampel menggunakan teknik purposive sampling. Data yang diperlukan untuk penelitian ini dikumpulkan melalui kuesioner, menggambar analisis rubrik, dan wawancara. Identifikasi Kesalahpahaman ditentukan dengan menggambar siswa berdasarkan menggambar kriteria klasifikasi oleh Kose (2008. Siswa diperintahkan untuk menarik tentang konsep fotosintesis setelah proses pembelajaran. Gambar siswa dianalisis dengan rubrik dan setelah itu mereka diwawancarai. Hasil penelitian menunjukkan tidak semua tingkat kriteria menggambar dari tingkat 1 sampai 5 diidentifikasi. Dari hasil analisa, gambar paling banyak ditemukan adalah pada tingkat 4. Gambar pada tingkat 4 dikategorikan sebagai gambar lengkap konsep fotosintesis dan tidak ada kesalahpahaman ditemukan. Berdasarkan gambar mereka, ada siswa 2,9% diidentifikasi yang diselenggarakan kesalahpahaman. Ada perbedaan jumlah siswa yang diadakan kesalahpahaman antara gambar hasil analisis dan hasil wawancara. Dari hasil wawancara, ada siswa 35,2% dimiliki kesalahpahaman, lebih dari menggambar hasil analisis. Ini berarti bahwa identifikasi kesalahpahaman melalui analisis gambar tidak efektif. Kesalahpahaman siswa yang paling sering terjadi pada konsep fotosintesis adalah tempat berlangsungnya fotosintesis. Faktor yang membuat kesalahpahaman siswa yaitu karena siswa itu sendiri dan lingkungannya. Kata Kunci: fotosintesis, kesalahpahaman, konsep, menggambar analisis

Modern concepts of thermodynamic optimization in Mexican thermoelectric stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

Energy Technology Data Exchange (ETDEWEB)

Cervantes-de Gortari, J; Vidal-Santo, A.; Mendez-Lavielle, F.; Bautista-Godinez, O. [Departamento de Termoenergia, from Facultad de Ingenieria UNAM (Mexico)

2002-03-01

In this paper, a summary review of the current thermodynamic concepts related to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia. De acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

Development of a central PC-based system for reactor signal monitoring and analysis

International Nuclear Information System (INIS)

Karim, A.; Ansari, S.A.; Rauf Baig, A.

1998-01-01

A personal computer based system was developed for on-line monitoring, signal processing and display of important reactor parameters of the Pakistan Research Reactor-1. The system was designed for assistance to both reactor operator and users. It performs three main functions. The first is the centralized radiation monitoring in and around the reactor building. The computer acquires signals from radiation monitoring channels and continuously displays them on distributed monitors. Trend monitoring and alarm generation is also done. In case of any abnormal condition the radiation level data is automatically stored in computer memory for detailed off-line analysis. In the second part the computer does the performance testing of nuclear instrumentation channels by signal statistical analysis, and generates alarm in case the channel standard deviation error exceeds the permissible error. Mean values of important nuclear signals are also displayed on distributed monitors as a part of reactor safety parameters display system. The third function is on-line computation of reactor physics parameters of the core which are important from operational and safety points-of-view. The signals from radiation protection system and nuclear instrumentation channels in the reactor were interfaced with the computer for this purpose. The development work was done under an IAEA research contract as a part of coordinated research programme. (author)

DESAIN TERAS PLTN JENIS PEBBLE BED MODULAR REACTOR (PBMR MENGGUNAKAN PAKET PROGRAM MCNP-5 PADA KONDISI BEGINNING OF LIFE

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Ralind Re Marla

2015-03-01

Full Text Available Telah dilakukan desain teras Pembangkit Listrik Tenaga Nuklir (PLTN untuk jenis Pebble Bed Modular Reactor (PBMR dengan daya 70 MWe untuk keperluan proses smelter pada keadaan beginning of life (BOL. Analisis ini bertujuan untuk mengetahui persen pengkayaan, distribusi suhu dan nilai keselamatan dengan koefisien reaktivitas teras yang negatif pada reaktor jenis PBMR apabila daya reaktor 70 MWe. Analisis menggunakan program Monte Carlo N-Particle-5 (MCNP5 dan dari hasil analisis ini diharapkan dapat memenuhi syarat dalam mendukung program percepatan pembangunan kelistrikan batubara 10.000 MWe khususnya untuk proses smelter, yang tersebar merata di wilayah Indonesia. Hasil penelitian menunjukkan bahwa, faktor perlipatan efektif (k-eff Reaktor jenis PBMR daya 70 MWe mengalami kondisi kritis pada pengkayaan 5,626 % dengan nilai faktor perlipatan efektif 1,00031±0,00087 dan nilai koefisien reaktivitas suhu pada -10,0006 pcm/K. Dari hasil analisis daat disimpulkan bahwa reaktor jenis PBMR daya 70 MWe adalah aman.   ABSTRACT The core design of Nuclear Power Plant for Pebble Bed Modular Reactor (PBMR type with 70 MWe capacity power in Beginning of Life (BOL has been performed. The aim of this analysis, to know percent enrichment, temperature distribution and safety value by negative temperature coefficient at type PBMR if reactor power become lower equal to 70 MWe. This analysis was expected become one part of overview project development the power plant with 10.000 MWe of total capacity, spread evenly in territory of Indonesia especially to support of smelter industries. The results showed that, effective multiplication factor (keff with power 70 MWe critical condition at enrichment 5,626 %is 1,00031±0,00087, based on enrichment result, a value of the temperature coefficient reactivity is - 10,0006 pcm/K. Based on the results of these studies, it can beconcluded that the PBMR 70 MWe design is theoritically safe.

Modern concepts of thermodynamic optimization in Mexican thermoelectric power stations; Conceptos modernos de optimacion termodinamica en centrales termoelectricas mexicanas

Energy Technology Data Exchange (ETDEWEB)

Cervantes de Gortari, J.; Vidal Santo, A.; Mendez Lavielle, F.; Bautista Godinez, O. [Facultad de Ingenieria, UNAM, Mexico, D.F. (Mexico)

2002-03-01

In this paper, a summary review of the current thermodynamic concepts to the maximum power generation and minimum entropy production are presented. The results of the analysis are considered in Mexican power stations using conventional cycles and are compared with other power stations around the world. [Spanish] En este trabajo se revisa el analisis de maxima generacion de potencia que implica la minimizacion de la produccion de entropia en centrales generadoras de potencia, de acuerdo con los lineamientos mas recientes publicados en la literatura. Los conceptos y resultados del analisis se aplican a varias centrales mexicanas y se comparan con otras centrales en el mundo.

Analisis Tingkat Kepentingan Dan Kinerja Layanan Automated Teller Machine (Atm) Bank Mandiri

OpenAIRE

Setiawati, Lenny; Sugiharto, Toto

2008-01-01

Penelitian ini ditujukan untuk menganalisis tingkat kepentingan dan kinerja layananATM Bank Mandiri. Analisis Servqual yang terdiri atas dimensi tangible, realibility,responsiveness, assurance,dan empathy digunakan untuk menganalisis kinerjalayanan ATM. Sementara itu, Customer Satisfaction Index dan ImportancePerformance Analysis yang terdiri atas analisis kuadran dan analisis kesenjangandigunakan untuk menginvestigasi kepuasan pelanggan dan untuk mengidentifikasikandimensi layanan yang kiner...

ANALISIS SPASIAL KEJADIAN DEMAM BERDARAH DENGUE BERDASARKAN KEPADATAN PENDUDUK

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Agcrista Permata Kusuma

2016-01-01

Full Text Available Abstrak Puskesmas Kedungmundu merupakan wilayah endemis DBD dengan kasus yang tinggi. Diperlukan upaya dalam menentukan kebijakan strategi pengendalian vektor secara efektif dan efisien. Analisis spasial dalam SIG dapat digunakan untuk mengetahui pola penyebaran dan daerah potensi penularan DBD. Jenis penelitian ini adalah penelitian deskriptif analitik menggunakan pendekatan cross sectional. Teknik pengambilan sampel menggunakan sampel wilayah memperhatikan proporsi sampel dengan jumlah sampel 146 responden. Pengambilan titik koordinat menggunakan GPS. Analisis data menggunakan analisis univariat dan analisis spasial. Hasil perhitungan statistik spasial ANN diperoleh nilai Z-score = -11,054 terdapat pola spasial kasus DBD di wilayah kerja Puskesmas Kedungmundu. Nilai ANN = 0,52 < 1, artinya pola penyebaran kejadian DBD yang terjadi adalah berkerumun. Kesimpulan dalam penelitian ini sebaran kasus DBD memiliki keterkaitan secara spasial dengan kepadatan penduduk. Abstract Kedungmundu PHC is an endemich region with a high case. Be required to determine policy of vector control strategies effectively and efficiently. Spatial analsys in GIS can be used to determine the pattern of distribution and areas of DHF potential transmission. The type this research was analysis descriptive with cross sectional approach. The sampling technique used a sample area of attention to the proportion of the sample with 146 respondents of total sample. Capturing the coordinates used GPS. Data analisys used univariat and spatial analisys. Result of ANN obtained a Z-score= -11,054, there was a spatial pattern of dengue cases in Kedungmundu PHC. ANN value = 0,52 < 1, it meant that the pattern of DHF distribution was clustered. The conclution of this research was DHF distribution cases has spatial correlation with density population.

Analisis Semiotik Sajak Bulang Cahaya

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Junaidi Junaidi

2014-11-01

Full Text Available Penelitian ini bertujuan menggali makna tanda yang terdapat dalam sajak Bulang Cahaya karya Rida K Liamsi. Untuk menggali makna itu, pendekatan analisis semiotik Roland Barthes digunakan. Hasil penelitian menunjukkan bahwa sajak ini berisi tanda-tanda bersumber dari kosa kata Melayu lama. Sajak ini juga berisi simbol-simbol yang berkaitan dengan kehidupan orang Melayu. Penggunaan kata-kata Melayu lama dan simbol Melayu memperkuat setting Melayu dalam sajak ini. Analisis makna menunjukkan bahwa seseorang merasakan kedukaan sangat mendalam ketika cintanya harus berakhir, tetapi ia terus merasakan kerinduan dengan kekasihnya yang telah pergi. Mitos cinta yang terdapat dalam pusinya adalah orang tahu bahwa putus cinta itu menyakitkan tetapi orang tetap saja jatuh cinta.

Development of a central PC-based system for reactor signal monitoring and analysis

International Nuclear Information System (INIS)

Karim, A.; Ansari, S.A.; Baig, A.R.

1996-05-01

A personal computer based system was developed for on-line monitoring, signal processing and display of important parameters of the Pakistan Reactor-1. The system was designed for assistance to both reactor operator and users. It performs three main functions. The first is the centralized radiation monitoring in and around the reactor building. The computer acquires signals from radiation monitoring channels and continuously displays them on distributed monitors. Trend monitoring and alarm generation is also done. In case of any abnormal condition the radiation level data is automatically stored in computer memory for detailed off-line analysis. In the second part the computer does the performance testing of nuclear instrumentation channels by signal statistical analysis and generates alarm in case the channel standard deviation error exceeds the permissible error. Mean values of important nuclear signals are also displayed on distributed monitors as a part of reactor safety parameters display system. The third function is on-line computation of reactor physics parameters of the core which are important from operational and safety point-of-view. The signals from radiation protection system and nuclear instrumentation channels in the reactor were interfaced with the computer for this purpose. The development work was done under an IAEA research contract as a part of coordinated research programme. (author) 12 figs

ANALISIS POLA MANAJEMEN BAHAN BAKAR DESAIN TERAS REAKTOR RISET TIPE MTR

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Lily Suparlina

2015-03-01

Full Text Available Parameter neutronik dibutuhkan dalam mendesain teras reaktor riset. Reaktor riset jenis MTR (Material Testing Reactor sangat diminati karena dapat digunakan baik untuk riset dan juga produksi radio isotop. Reaktor riset yang ada saat ini sudah tua sehingga dibutuhkan desain reaktor yang mempunyai teras kompak. Desain teras reaktor riset yang sudah ada saat ini belum cukup memadai untuk memenuhi persyaratan di dalam UCD yang telah ditetapkan yaitu fluks neutron termal di teras 1x1015 n/cm2s, oleh karena itu perlu dibuat desain teras reaktor baru sebagai alternatif yang kompak dan dapat menghasilkan fluks neutron tinggi. Telah dilakukan perhitungan dan analisis terhadap manajemen bahan bakar desain teras kompak dengan konfigurasi teras 5x5, berbahan bakar U9Mo-Al dan tinggi teras aktif 70 cm. Tujuan dari riset ini untuk memperoleh fluks neutron di teras memenuhi kebutuhan seperti yang telah ditetapkan di UCD dengan panjang siklus operasi minimum 20 hari pada daya 50 MW. Perhitungan dilakukan dengan menggunakan paket program komputer WIMSD-5B untuk menggenerasi tampang lintang makroskopik bahan bakar dan Batan-FUEL untuk memperoleh nilai parameter neutronik serta Batan-3DIFF untuk perhitungan nilai reaktivitas batang kendali. Perhitungan parameter neutronik teras reaktor riset ini dilakukan untuk bahan bakar U-9Mo-Al dengan tingkat muat bervariasi dan 2 macam pola pergantian bahan bakar yaitu teras segar dan teras setimbang. Hasil analisis menunjukkan bahwa pada teras segar, tingkat muat 235U sebesar 360 gram, 390 gram dan 450 gram memenuhi kriteria keselamatan dan kriteria penerimaan di UCD dengan nilai fluks neutron termal di teras lebih dari 1x1015 n/cm2s dan panjang siklus >20 hari, sedangkan pada teras setimbang panjang siklus dapat terpenuhi hanya untuk tingkat muat 450 gram. Kata kunci: desain teras reaktor, bahan bakar UMo, pola bahan bakar, WIMS, BATAN-FUEL   Research reactor core design needs neutronics parameter calculation use computer

Membandingkan Tingkat Kemiripan Rekaman Voice Changer Menggunakan Analisis Pitch, Formant dan Spectogram

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Ahmad Subki

2018-02-01

Full Text Available Audio forensik merupakan salah satu ilmu yang mnyandingkan antara ilmu pengetahuan dan metode ilmiah dalam proses analisis rekaman suara untuk membantu dan mendukung pengungkapan suatu tindak kejahatan yang diperlukan dalam proses persidangan. Undang-undang ITE No.19 Tahun 2016 menyebutkan bahwa rekaman suara merupakan salah satu alat bukti digital yang sah dan dapat digunakan sebagai penguat dakwaan. Rekaman suara yang merupakan barang bukti digital sangatlah mudah dan rentan dimanipulasi, baik secara sengaja maupun tidak disengaja. Pada penelitian ini dilakukan analisis terkait tingkat kemiripan antara rekaman suara voice changer dengan rekaman suara asli menggunakan analisis pitch, formant dan spectogram, rekaman suara yang dianalisis ada dua jenis rekaman suara yaitu suara laki-laki dan suara perempuan. Rekaman suara voice changer  dan rekaman suara asli, diekstrak menggunakan tools praat kemudian informasi yang diperoleh dianalisis dengan analisis statistik pitch, formant dan spectrogrammenggunakan tools gnumeric. Penelitian ini menghasilkan bahwa analisis rekaman suara voice changer dengan rekaman suara asli dapat menggunakan analisis statistik pitch, formant dan spectrogram, rekaman suara voice changer A memiliki tingkat kemiripan yang paling tinggi dengan rekaman suara asli pada posisi low pitch, sedangkan voice changer yang lain lebih sulit untuk diidentifikasi.

ANALISIS PENERAPAN 8 STANDAR NASIONAL PENDIDIKAN PADA SMP NEGERI 2 DOLOPO KABUPATEN MADIUN

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Luki Eko Cahyono

2015-10-01

Penelitian ini menggunakan desain penelitian Deskriptif Kualitatif. Jenis penelitian adalah studi kasus. Data yang digunakan adalah data Primer. Teknik pengumpulan data yang digunakan adalah wawancara dan dokumentasi. Teknik keabsahan data adalah Triangulasi Sumber dan teknik analisis data yang digunakan adalah pendekatan Strengths, Weakness, Opportunities, dan Threats (Analisis SWOT. Kesimpulan penelitian ini adalah (1 Hasil analisis Strenght (Kekuatan adalah sekolah sudah merencanakan, melaksanakan dan mengevaluasi sebagian besar indikator dalam pemenuhan Standar Nasional Pendidikan sehingga meningkatkan mutu pendidikan sekolah. (2 Hasil analisis Weakness (kelemahan adalah keterbatasan anggaran dana dan sumber daya manusia baik peserta didik, pendidik, maupun tenaga kependidikan dalam pemenuhan seluruh unsur Standar Nasional Pendidikan. (3 Hasil analisis Opportunities (peluang adalah Pemberian workshop dan pelatihan kepada pendidik dan tenaga kependidikan meningkatkan kualitas pendidikan sekolah, dan perencanaan, pelaksanaan pembiayaan serta evaluasi penganggaran yang baik memberikan dampak positif terhadap semua unsur operasional sekolah maupun sarana prasarana sekolah. (4 Hasil analisis Threats (Tantangan adalah perencanaan, sosialisasi, pelaksanaan dan evaluasi serta tindak lanjut yang tidak dijalankan dengan manajemen yang baik dalam upaya pemenuhan Standar Nasional Pendidikan akan menghambat peningkatan kualitas pendidikan sekolah. (5 Hasil penerapan Standar Nasional Pendidikan pada SMP Negeri 2 Dolopo menggunakan analisis SWOT menunjukkan bahwa Kekuatan lebih besar daripada Kelemahan dan Peluang lebih besar dari Ancaman, yang berarti Standar Nasional Pendidikan telah terpenuhi dan menghasilkan Akreditasi Sekolah nilai A.

The Centralized Reliability Data Organization (CREDO); an advanced nuclear reactor reliability, availability, and maintainability data bank and data analysis center

International Nuclear Information System (INIS)

Knee, H.E.

1991-01-01

The Centralized Reliability Data Organization (CREDO) is a data bank and data analysis center, which since 1985 has been jointly sponsored by the US Department of Energy's (US DOE's) Office of Technology Support Programs and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC). It focuses on reliability, availability and maintainability (RAM) data for components (e.g. valves, pumps, etc.) operating in advanced nuclear reactor facilities. As originally intended, the purpose of the CREDO system was to provide a centralized source of accurate, up-to-date data and information for use in RAM analyses necessary for meeting DOE's data needs in the areas of advanced reactor safety assessments, design and licensing. In particular, creation of the CREDO system was considered an essential element needed to fulfill the DOE Breeder Reactor Safety Program's commitment of 'identifying and exploiting areas in which probabilistic methods can be developed and used in making reactor safety Research and Development choices and optimizing designs of safety systems'. CREDO and its operation are explained. (author)

The approximate thermal-model-testing method for non-stationary temperature fields in central zones of fast reactor assemblies

International Nuclear Information System (INIS)

Mikhin, V.I.; Matukhin, N.M.

2000-01-01

The approach to generalization of the non-stationary heat exchange data for the central zones of the nuclear reactor fuel assemblies and the approximate thermal-model-testing criteria are proposed. The fuel assemblies of fast and water-cooled reactors with different fuel compositions have been investigated. The reason of the non-stationary heat exchange is the fuel-energy-release time dependence. (author)

Flow of ideal fluid through a central region of a nuclear reactor wire-spaced fuel subassembly

International Nuclear Information System (INIS)

Schmid, J.

1991-04-01

The results are given of calculations of the flow of an ideal fluid through the central region of a nuclear reactor wire-spaced fuel subassembly. The computer code used is briefly described. (author). 10 figs., 4 refs

Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1

International Nuclear Information System (INIS)

Israr, M.; Shami, Qamar-ud-din; Pervez, S.

1997-11-01

In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)

Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

Energy Technology Data Exchange (ETDEWEB)

Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

1967-09-15

(e), con reactor de agua en ebullicion y contencion por condensacion de vapor, y la central de Vandellos, de 480 MW(e), con reactor grafito-gas y diseno integrado del tipo EDF-4. Los dos primeros estan situados en el interior del pais, el tercero en la costa mediterranea. Se discuten los criterios convencionales y los relacionados con la seguridad, que se han utilizado en la seleccion. Se pone de relieve la influencia de la orografia espanola en el transporte del equipo pesado y su repercusion en la seleccion de emplazamientos para centrales nucleares. Se hace referencia a la experiencia obtenida en el transporte del equipo de la central de Zorita. Se analizan las dificultades practicas encontradas al aplicar unas determinadas normas de seguridad a emplazamientos de centrales de tipo y caracteristicas de diseno diferentes. Ya que el tipo de reactor y su sistema de contencion influyen en el valor practico de la aplicacion de unas determinadas normas que, ademas, han de adaptarse a las caracteristicas peculiares de cada nacion, se indica la conveniencia de utilizar de forma adecuada y flexible las normas de seguridad para el analisis de los emplazamientos de centrales nucleares. Se describen las caracteristicas geologicas y meteorologicas de los tres emplazamientos y se resumen los trabajos e investigaciones realizados en estos campos. En especial, se destacan los estudios de hidrologia realizados en el caso de Zorita y Santa Maria de Garofia, y se describen las estaciones meteorologicas montadas en ambos emplazamientos, los experimentos de difusion con globos equilibrados realizados en el caso de Santa Maria de Garofia y los resultados de estas investigaciones. (author)

ANALISIS HUBUNGAN KEMANDIRIAN KEUANGAN DAERAH DAN KETERGANTUNGAN DAERAH TERHADAP PENGANGGURAN DAN KEMISKINAN

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Rosyafah Febiandani

2017-06-01

Full Text Available Adanya desentralisasi fiskal diharapkan dapat menciptakan kemandirian daerah dan dapat mengurangi ketergantungan pemerintah daerah terhadap pemerintah pusat. Kemandirian keuangan daerah dicerminkan dengan perbandingan besarnya PAD terhadap total pendapatan daerah. Sejak 10 tahun dilaksanakannya otonomi daerah sesuai UU No 32 Tahun 2004, kemandirian keuangan daerah di Provinsi Jawa Tengah masih berada di level yang kurang baik dibandingkan dengan provinsi lainnya di Pulau Jawa. Jumlah pengangguran dan jumlah penduduk miskin di Provinsi Jawa Tengah juga masih terhitung tinggi. Penelitian ini bertujuan untuk mengetahui hubungan dari tingkat kemandirian keuangan daerah dan tingkat ketergantungan daerah terhadap tingkat pengangguran dan tingkat kemiskinan di kabupaten/kota Provinsi Jawa Tengah Tahun 2013. Data yang digunakan dalam penelitian ini adalah data sekunder. Metode analisis yang digunakan adalah Analisis Korelasi Kanonikal menggunakan bantuan program SPSS. Hasil penelitian menunjukkan kemandirian keuangan daerah mempunyi hubungan yang signifikan, kuat, dan tidak searah dengan pengangguran dan kemiskinan. Sedangkan hubungan antara ketergantungan daerah terhadap kemiskinan dan pengangguran mempunyai hubungan yang signifikan, tidak kuat, dan tidak searah. Peningkatan kemandirian keuangan daerah guna mengurangi tingkat ketergantungan terhadap pemerintah pusat dapat dilakukan dengan cara menggali dan mengelola sumber daya atau potensi daerah yang dimilikinya secara efektif dan efisien sebagai sumber utama pendapatan keuangan daerahnya. Fiscal decentralization is expected to create independency regional financial and to reduce the dependence of local governments to the central government. Independency regional financial can be result by the ratio of PAD to total local revenue. Since 10 years the implementation of regional autonomy based on UU No. 32 of 2004, independency regional financial in Central Java is still unwell compared to the other

Analisis Sektor/Sub Sektor Unggulan di Kabupaten Bungo

Directory of Open Access Journals (Sweden)

Gafur Gafur

2016-03-01

Full Text Available Abstract. This study aimed to analyze the leading sectors in Bungo. The method used is Location Quotient (LQ, Dynamic Location Quotient (DLQ, specialization index, Growth Ratio Model (MRP. Based on analysis of LQ and DLQ, there are only two basis sectors at present and in the future, namely the construction sector and trade, hotels and restaurants. Based on the analysis of Specialization Index, in Bungo Regency has a concentration of the economy in the agricultural sector and the manufacturing sector. Based on MRP analysis also showed that prominent sector growth at the level of Bungo and Jambi Province, namely electricity, gas and water supply; the building sector; and trade, hotels and restaurants. Keywords : Location Quotient (LQ, Dinamic Location Quotient (DLQ, Specialization Index, Growth Ratio Model   Abstrak. Penelitian ini bertujuan untuk menganalisis sektor unggulan di Kabupaten Bungo. Metode yang digunakan adalah analisis Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan (MRP. Berdasarkan analisis LQ dan DLQ,  hanya ada 2 sektor yang menjadi sektor basis pada saat ini dan pada masa yang akan datang yaitu sektor bangunan dan sektor perdagangan, hotel dan restoran. Berdasarkan analisis Indeks Spesialisasi, di Kabupaten Bungo telah terjadi konsentrasi ekonomi pada sektor pertanian dan sektor industri pengolahan. Berdasarkan analisis MRP juga dapat diketahui bahwa sektor yang menonjol pertumbuhannya pada tingkat Kabupaten Bungo dan Provinsi Jambi yaitu sektor listrik, gas dan air bersih; sektor bangunan; serta sektor perdagangan, hotel dan restoran. Kata Kunci : Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan

Analisis dan Desain BI-Dashboard Monitoring Realisasi Daftar Isian Pelaksanaan Anggaran (DIPA pada Kantor Pelayanan Perbendaharaan Negara (KPPN

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Ernestina Rahmanasari

2013-09-01

Full Text Available Transaksi keuangan badan pemerintahan tingkat daerah dipertanggungjawabkan kepada Kementrian Keuangan melalui Kantor Pelayanan Perbendaharaan Negara (KPPNsetiap bulan dalam bentuk Laporan Keuangan Pemerintah Pusat (LKPP. Laporan Keuangan, didukung dengan teknologi Business Intelligence(BI dashboarddapat dimanfaatkan sebagai data-driven decision support system yang mendorong performa kinerja. Analisis dan desainterhadap pembuatan BI dashboard menunjukkanbagaimana Laporan Keuangan dapat digunakan untuk monitoring realisasi penyerapan dana DIPA dan kinerja instansi secara tepat waktu dan interaktif.Analisis terdiri dari analisis Indikator Kinerja Utama (IKU dan analisis Laporan Keuangan. IKUpada analisis dan desain ini mencakup ketercapaian estimasi dengan penerimaan, ketercapaian pagu dengan belanja, ketepatan waktu pengiriman rekonsiliasi oleh instansi, validasi, akurasi, dan ketepatan data. Desain terdiri dari katalog dashboard, alur analisis, sumber data, desain User-Interface, dan desain objek dashboard. Sedangkan dashboard yang dirancang menggunakan aplikasi Vera sebagai Enterprise System, mengakses basis data MySQL, dan menampilkan data dengan teknologi data-driven business-intelligence Qlikview. Desain aplikasi yang telah dibuat akan menampilkan 4 (empat Tab yaitu: Dashboard utama, Analisis, Monitoring, dan Laporan

Semiotika Teks: Sebuah Pendekatan Analisis Teks

Directory of Open Access Journals (Sweden)

Yasraf Amir Piliang

2004-12-01

tanda-tanda yang membentuk apa yang disebut sebagai ‘teks’. Analisis teks, menurut Roland Barthes, akan menghasilkan makna denotatif, yakni makna tanda yang bersifat eksplisit, dan makna konotatif, yaitu makna tanda lapis kedua yang bersifat implisit.

Microfinanza: analisi d’impatto di un programma in India

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Tommaso Rondinella

2005-03-01

Full Text Available L’analisi d’impatto dei programmi di microfinanza è uno strumento utile sia per migliorare i servizi offerti sia per garantire ai donatori che il denaro concesso sia utilizzato per programmi efficaci nell’alleviare la povertà. Il presente lavoro è costituito da due parti: la prima è dedicata all’analisi d’impatto, la seconda all’analisi empirica sul campo. L’indagine è stata condotta attraverso l’utilizzo di uno strumento in grado di dare una indicazione chiara dei cambiamenti avvenuti nelle condizioni di vita dei beneficiari e con il pregio di essere applicabile a costi molto ridotti. I risultati ottenuti mostrano in che misura l’accesso al credito cambi le condizioni di vita dei più poveri inducendo consistenti aumenti del reddito familiare, dei risparmi, della diversificazione delle attività produttive e del consumo di cibo. Inoltre si osserva, all’interno dei nuclei familiari, un miglioramento della condizione femminile chiaramente dipendente dalla partecipazione al programma di microcredito

The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

2001-07-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN

OpenAIRE

ARIANTY, ASTRI

2012-01-01

ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN COMPANY FINANCIAL PERFORMANCE ANALYSIS PT. INSURANCE JIWASRAYA (LIMITED) SOUTH BRANCH SULAWESI Astri Arianty Prof. Dr. H. Muhammad Ali, SE., M.S Drs. Armayah Sida, M.Si Analisis terhadap kinerja keuangan perusahaan sangat penting dilakukan untuk mengetahui sejauh mana tingkat pencapaian yang telah diperoleh perusahaan sebagaimana tujuan perusahaan dalam menjalankan proses produk...

Perumusan Strategi Bersaing pada Perusahaan Ban dengan Metode Analisis Portofolio Produk (Studi Kasus: PT Multistrada Arah Sarana, Tbk

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Nathanael August Zefanya

2017-01-01

Full Text Available Industri ban di Indonesia mengalami perkembangan pesat dalam kurun waktu 10 tahun terakhir. Namun, terjadinya krisis ekonomi global menjadi penyebab menurunnya pendapatan, salah satunya adalah PT MASA dengan produk utamanya yaitu ban mobil Achilles dan ban motor Corsa yang digunakan sebagai objek penelitian ini. Telah diilakukan analisis PESTEL dan Porter’s Five Forces, identifikasi faktor lingkungan internal dan eksternal dengan analisis SWOT serta merumuskan alternatif strategi bersaing untuk direkomendasikan kepada PT MASA. Perumusan strategi alternatif didapat dari hasil analisis Matriks BCG dan Matriks IE sebagai analisis portofolio untuk mendapatkan tema strategi alternatif dalam pembuatan Matriks SWOT. Strategi alternatif kemudian diperingkatkan dengan QSPM dan dilanjutkan pembuatan rencana aksi bagi PT MASA dalam waktu 5 tahun ke depan. Setelah dilakukan analisis industri, diketahui bahwa ancaman terbesar datang dari pesaing produsen ban. Dari hasil analisis portofolio, PT MASA berada di kuadran I karena memiliki koordinat IFE serta EFE 3,32 dan 3,26. Dari hasil analisis Matriks IE, PT MASA direkomendasikan untuk melakukan strategi grow and build. Hasil Matriks BCG menunjukkan bahwa Achilles berada di dogs, sementara Corsa berada di question marks. Terdapat 13 strategi alternatif hasil dari formulasi strategi dengan menggunakan matriks TOWS. Dari hasil analisis QSPM, terdapat 7 alternatif strategi terbaik dan rencana aksi..

BWR type reactor

International Nuclear Information System (INIS)

Watanabe, Shoichi

1983-01-01

Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

ANALISIS ATRIBUT-ATRIBUT YANG MEMPENGARUHI TINGKAT KEPUASAN PELANGGAN TELEPON RUMAH (FIXED WIRELINE MENGGUNAKAN METODE ANALISIS DISKRIMINAN (STUDI KASUS DI PT. TELKOM KANDATEL SEMARANG

Directory of Open Access Journals (Sweden)

Diana Puspita Sari

2012-02-01

Full Text Available PT Telkom memiliki misi untuk memberikan layanan One Stop Infocom dengan kualitas prima dan harga kompetitif. Kenyataannya, PT. Telkom Kandatel Semarang mengalami penurunan pendapatan. Semakin berkembangnya layanan jasa fixed wireless yang lebih mudah dan murah, menyebabkan penurunan pemakaian jasa fixed wireline. Dengan konsumen melakukan pembelian pertama pada suatu produk tertentu dengan harga terjangkau, kualitas terjamin, maka konsumen akan kembali membeli produk tersebut, dan dampaknya dari fenomena ini adalah kepuasan pelanggan (customer satisfaction terhadap produk tertentu karena telah memberikan kepuasan dan terjaminnya kualitas, walaupun banyak pesaing lain.  Oleh sebab itu, penelitian ini membahas dan melakukan analisis kepuasan pelanggan fixed wireline PT. Telkom Kandatel Semarang, menggunakan variabel kepuasan pelanggan untuk dikelompokkan menjadi tiga tingkatan yaitu pelanggan yang sangat puas, puas, dan tidak puas dengan menggunakan analisis klaster, kemudian dilakukan analisis variabel 4P Customer Relationship Management (CRM menggunakan analisis diskriminan, sehingga diketahui atribut yang mempengaruhi tingkat kepuasan pelanggan agar PT. Telkom Kandatel Semarang dapat terus mempertahankan dan meningkatkan kepuasan pelanggan dengan berusaha memenuhi kebutuhan dan keinginan pelanggan dengan maksud kepuasan pelanggan tidak menurun agar dapat meningkatkan intensitas pemakaian fixed wireline. Kata kunci : analisis klaster, analisis diskriminan, kepuasan pelanggan, fixed wireline      PT Telkom has a mission to provide a One Stop Infocom services with excellent quality and competitive price. In fact, PT. Telkom Semarang Kandatel income decreased. The growing fixed wireless service is easier and cheaper, causes a decrease in the use of fixed wireline services.With the first consumer purchase a given product at an affordable price, guaranteed quality, then consumers will buy the product again, and the impact of this phenomenon is

Household appliance data collection and market survey in central and eastern european countries; Raccolta dati e analisi del mercato sugli apparecchi elettrodomestici nei paesi dell'Europa centrale e orientale

Energy Technology Data Exchange (ETDEWEB)

Presutto, M. [ENEA, Funzione Centrali Studi, Centro Ricerche Ispra, Vercelli (Italy); Ricci, A. [Istituto di Studi per l' Integrazione dei Sistemi, Rome (Italy); Meli, L. [ANIE, Federazione delle Imprese Elettrotecniche ed Elettroniche, International Affaires Direction, Milan (Italy)

2001-07-01

Since 1995 the European Commission, through the SAVE programme, and the Economic Commission for Europe of the United Nations, through the Energy Efficiency 2000 Project, jointly sponsored the so called SACHA projects in Central and Eastern European Countries regarding major household appliances. Consistently, the main objective of the projects was to analyse and interpret the situation of refrigerators, freezers and washing machines in seven CEEC, so as to increase the knowledge and understanding of the issues at stake in the area of energy efficiency and environmental friendliness, and therefore to identify possible scenarios of improvement. This paper describes the work accomplished and the results achieved in this context, focusing more on the data collection and market survey moments and illustrates, with an abundant series of exhibits, the quantitative picture resulting form the analyses carried out. Possibility exists for replication in Latin America, where ENEA and Italian experience could be fruitfully applied. Reliable and complete information is in fact one of the prerequisites to overcome potential barriers and facilitate a successful enforcement of any energy efficiency policy. Effective implementation and regional harmonisation are necessary, even if projects can facilitate the fulfilment of these goals as it provides a consolidated methodology and an integrated scheme for basic data collection and analysis. [Italian] A partire dal 1995 la Commissione Europea e la Commissione Economica per l'Europa delle Nazioni Unite hanno congiuntamente promosso lo studio dei piu' importanti apparecchi domestici nei paesi dell'Europa centrale ed orientale. Principale obiettivo di questi progetti, piu' noti come progetti con SACHA, dall'acronimo del titolo, era analizzare e soprattutto interpretare la situazione dei frigoriferi, congelatori e lavatrici in sette PECO, per migliorare da un lato la conoscenza e la comprensione delle problematiche

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

Computerized reactor monitor and control for research reactors

International Nuclear Information System (INIS)

Buerger, L.; Vegh, E.

1981-09-01

The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

Pembuatan Dan Analisis Exciter Generator Rf Untuk Siklotron Proton Decy-13

OpenAIRE

Prajitno, Prajitno

2011-01-01

PEMBUATAN DAN ANALISIS EXCITER GENERATOR RF UNTUK SIKLOTRON PROTON DECY-13.Telah dilakukan analisis dan pembuatan exciter generator RF untuk siklotron proton 13MeV. Generator RFakan digunakan sebagai sumber tegangan pemercepat bolak-Balik siklotron DECY-13 rancangan PTAPBBATAN.Berdasarkan dokumen rancangan dasar yang telah dibuat siklotron Decy-13 akan menggunakanmedan magnet 1,275 Tesla, sehingga frekuensi generator RF bila menggunakan harmonik keempat adalah77,667 MHz. Salah satu teknik pem...

Gas dynamics in the central cavity of HYLIFE-II reactor

International Nuclear Information System (INIS)

Chen, X.M.; Schrock, V.E.; Peterson, P.F.; Colella, P.

1992-01-01

In a HYLIFE-II ICF reactor, the microfusion of the D-T capsule in the center of the chamber produces X-rays that can ablate a thin layer off the liquid blanket which protects the first structural wall Thisablated material will implode toward the center line of the central cavity due to the initial vacuum and cylindrical geometry, and then rebound back to the liquid blanket vent through it and exert a pressure ''impulse'' onto the structural wall. The initial ablation occurs in a very short period with very small characteristic length and the implosion and rebounding processes feature very high pressures and temperatures. The proper design of the chamber relies on the reasonably accurate analysis of the gas dynamics in the central cavity and the gas-liquid interaction. In this paper, a second order Godunov numerical method is used to solve the compressible flow equations in the central cavity. The rarefaction and shock phenomena are very well captured by the numerical calculation. The equation of state for Flibe vapor is used in the calculation along with the parameters for the HYLIFE-II design. Since the radiation transport has not yet been included in the current calculations, the vapor possesses higher energy and therefore temperature. The total mass vaporized will also be underestimated in the later time of the calculation. The incorporation of a radiation calculation into this code is our next goal

Experimental facilities for PEC reactor design central channel test loop: CPC-1 - thermal shocks loop: CEDI

International Nuclear Information System (INIS)

Calvaresi, C.; Moreschi, L.F.

1983-01-01

PEC (Prova Elementi di Combustibile: Fuel Elements Test) is an experimental fast sodium-cooled reactor with a power of 120 MWt. This reactor aims at studying the behaviour of fuel elements under thermal and neutron conditions comparable with those existing in fast power nuclear facilities. Given the particular structure of the core, the complex operations to be performed in the transfer cell and the strict operating conditions of the central channel, two experimental facilities, CPC-1 and CEDI, have been designed as a support to the construction of the reactor. CPC-1 is a 1:1 scale model of the channel, transfer-cell and loop unit of the channel, whereas CEDI is a sodium-cooled loop which enables to carry out tests of isothermal endurance and thermal shocks on the group of seven forced elements, by simulating the thermo-hydraulic and mechanical conditions existing in the reactor. In this paper some experimental test are briefy discussed and some facilities are listed, both for the CPC-1 and for the CEDI. (Auth.)

Analisis Aliran Daya Berbasis Injeksi Arus dalam Bentuk Vektor

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Ahmad Wira Satriawan

2017-11-01

Full Text Available Tulisan ini memaparkan hasil penelitian yang telah dilakukan untuk membandingkan metode analisis aliran daya berbasis injeksi arus dalam bentuk vektor dengan format polar dan rektangular. Penelitian ini dilakukan untuk memperoleh metode analisa aliran daya dengan perhitungan yang lebih cepat dan akurat, serta iterasi yang lebih sedikit. Metode iterasi Newton Raphson diadopsi dalam penelitian ini dan bahasa pemrograman Python serta library komputasinya digunakan. Analisis terhadap karakteristik konvergensi dari kedua format dilakukan pada IEEE 14-bus Test System. Dari penelitian ini diperoleh hasil bahwa format rektangular lebih unggul dibandingkan format polar untuk kasus yang diteliti.

Adoption of in-vessel retention concept for VVER-440/V213 reactors in Central European Countries

Energy Technology Data Exchange (ETDEWEB)

Matejovic, Peter, E-mail: peter.matejovic@ivstt.sk [Inzinierska Vypoctova Spolocnost (IVS), Jana Holleho 5, 91701 Trnava (Slovakia); Barnak, Miroslav; Bachraty, Milan; Vranka, Lubomir [Inzinierska Vypoctova Spolocnost (IVS), Jana Holleho 5, 91701 Trnava (Slovakia); Berky, Robert [Integrita a Bezpecnost Ocelovych Konstrukcii, Rybnicna 40, 831 07 Bratislava (Slovakia)

2017-04-01

Highlights: • Design of in-vessel retention concept for VVER-440/V213 reactors. • Thermal loads acting on the inner reactor surface. • Structural response of reactor pressure vessel. • External reactor vessel cooling. - Abstract: An in-vessel retention (IVR) concept was proposed for standard VVER-440/V213 reactors equipped with confinement made of reinforced concrete and bubbler condenser pressure suppression system. This IVR concept is based on simple modifications of existing plant technology and thus it was attractive for plant operators in Central European Countries. Contrary to the solution that was adopted before at Loviisa NPP in Finland (two units of VVER-440/V213 reactor with steel confinement equipped with ice condenser), the coolant access to the reactor pressure vessel from flooded cavity is enabled via closable hole installed in the centre of thermal shield of the reactor lower head instead of lowering this massive structure in the case of severe accident. As a consequence, the crucial point of this IVR concept is narrow gap between torispherical lower head and thermal and biological shield. Here the highest thermal flux is expected in the case of severe accident. Thus, realistic estimation of thermal load and corresponding deformations of reactor wall and their impact on gap width for coolant flow are of primarily importance. In this contribution the attention is paid especially to the analytical support with emphasis to the following points: 1) {sup ∗}Estimation of thermal loads acting on the inner reactor surface; 2) {sup ∗}Estimation of structural response of reactor pressure vessel (RPV) with emphasis on the deformation of outer reactor surface and its impact on the annular gap between RPV wall and thermal/biological shield; 3) {sup ∗}Analysis of external reactor vessel cooling. For this purpose the ASTEC code was used for performing analysis of core degradation scenarios, the ANSYS code for structural analysis of reactor vessel

ANALISIS CLUSTER K-MEANS DALAM PENGELOMPOKAN KEMAMPUAN MAHASISWA

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B. Poerwanto

2016-12-01

Full Text Available Abstract. Cluster Analysis, K-Means Algorithm, Student Classification. This study aims to classify students based on learning outcomes for subject the basic of statistics (DDS, which is measured based on attendance, task, midterm (UTS, and final exams (UAS to further used to evaluate learning for subjects that require analysis of quantitative . This study uses k-means cluster analysis to classify the students into three groups based on learning outcomes. After grouped, there are 3 people in the low category, 27 in the medium category and over 70% in the high category.Abstrak. Analisis Cluster K-Means dalam Pengelompokan Kemampuan Mahasiswa. Pene-litian ini bertujuan untuk mengelompokkan mahasiswa berdasarkan hasil belajar mata kuliah dasar-dasar statistika (DDS yang diukur berdasarkan variabel nilai kehadiran, tugas, ujian tengah semester (UTS, dan ujian akhir semester (UAS untuk selanjutnya digunakan untuk mengevaluasi pembelajaran untuk mata kuliah yang membutuhkan kemampuan analisis kuantititatif yang baik. Penelitian ini menggunakan analisis cluster k-means dalam mengelompokkan mahasiswa ke dalam tiga kelompok berdasarkan hasil belajarnya. Seteleh dikelompokkan, terdapat 3 orang yang masuk pada kategori rendah, 27 orang pada kategori sedang dan lebih dari 70% pada kategori tinggi.Kata Kunci: Cluster Analysis, K-Means Algoritma, Klasifikasi Mahasiswa, Universitas Cokroaminoto Palopo

Klasifikasi Kecamatan Berdasarkan Nilai Akhir SMA/MA di Kabupaten Aceh Selatan Menggunakan Analisis Diskriminan

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Fitriana A.R.

2015-11-01

Full Text Available Analisis diskriminan merupakan bagian dari analisis peubah ganda. Analisis diskriminan digunakan untuk memodelkan variabel tak bebas yang bersifat kualitatif dengan variabel bebas yang bersifat kuantitatif. Pada penelitian ini, analisis diskriminan lebih dari dua kelompok diterapkan pada data nilai akhir SMA/MA di Kabupaten Aceh Selatan yang bertujuan untuk mendapatkan model untuk pengklasifikasian kecamatan. Pengklasifikasian ini bertujuan untuk melihat perbedaan kualitas siswa SMA/MA yang berada di masing-masing kecamatan Kabupaten Aceh Selatan berdasarkan data nilai akhir. Variabel tak bebas yang digunakan berupa klasifikasi kecamatan berdasarkan rata-rata jumlah nilai akhir SMA/MA yang berada di masing-masing kecamatan yang dibentuk dengan K-Means Cluster. Sedangkan variabel bebas yang digunakan adalah data rata-rata nilai akhir SMA/MA untuk setiap mata pelajaran yang diujiankan pada masing-masing jurusan setiap kecamatan. Model yang didapatkan adalah dua model diskriminan untuk jurusan IPA dan IPS.

Reactor core of nuclear reactor

International Nuclear Information System (INIS)

Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

1994-01-01

In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

ANALISIS KESENJANGAN PEMBANGUNAN EKONOMI ANTAR KABUPATEN/KOTA DI PROVINSI JAWA TENGAH

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Panji Irawan Yogyadipratama

2017-06-01

Full Text Available Tujuan dari penelitian ini adalah (1 mengetahui bagaimana perkembangan tingkat ketimpangan pembangunan ekonomi Provinsi Jawa Tengah menurut Indeks Williamson; (2 mengetahui sejauh mana pengaruh angkatan kerja terhadap tingkat pembangunan ekonomi Provinsi Jawa Tengah; dan (3 mengetahui bagaimana pengaruh alokasi dana bantuan pembangunan kabupaten/kota terhadap pembangunan ekonomi Provinsi Jawa Tengah. Penelitian ini merupakan penelitian kuantitatif dengan digunakan data panel, data time series (tahun 2002-2011 dan cross section (35 kabupaten/kota di Provinsi Jawa Tengah. Jenis data yang digunakan dalam penelitian ini adalah data sekunder yang diperoleh dari Badan Pusat Statistik (BPS. Metode analisis yang digunakan adalah metode analisis regresi linier berganda data panel dengan metode FEM digunakan alat bantu software Eviews 7. Hasil penelitian adalah menunjukan(1 ketimpangan pembangunan ekonomi antar daerah di Provinsi Jawa Tengah yang dihitung dengan menggunakan indeks Williamson selama periode 2008-2011 menunjukkan ketimpangan semakin melebar; (2 alokasi dana bantuan pembangunan dari pemerintah pusat yang tidak merata dan daerah yang mendapat bantuan terlalu besar dapat meningkatkan tingkat ketimpangan antar daerah. Hal ini akibat pembangunan yang terkonsentrasi dengan daerah-daerah yang sudah maju dibandingkan daerah yang masih tertinggal, karena daerah yang maju memiliki fasilitas lebih baik dari daerah yang belum maju; dan (3 nilai R2 sebesar 0,9949 artinya variasi variabel ketimpangan pembangunan ekonomi di Provinsi Jawa Tengah dapat dijelaskan oleh variabel-variabel angkatan kerja dan alokasi dana pembangunan daerah sebesar 95,5% sedangkan sisanya sebesar 0,05% dijelaskan faktor-faktor lainnya di luar model. The purpose of this study were (1 to know how the development level of inequality of economic development in Central Java Province according to Williamson Index; (2 determine the extent of the influence of the labor force to the

PENGUKURAN KINERJA PERUSAHAAN PT. HADJI KALLA DENGAN MENGGUNAKAN ANALISIS ECONOMIC VALUE ADDED

OpenAIRE

2013-01-01

Tujuan dari penelitian ini adalah mengetahui kinerja Economic Value Added (EVA) yang dicapai oleh perusahaan PT. Hadji Kalla, sedangkan metode analisis yang digunakan dalam penelitian ini adalah analisis perkembangan Economic Value Added (EVA), Net Operating Profit After Tax (NOPAT) dan The purpose of this study was to determine the performance of the Economic Value Added (EVA), which is achieved by the company PT. Hadji Kalla...

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

International Nuclear Information System (INIS)

Novakovic, M.

1961-12-01

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 2 with beryllium cladding, cooled by CO 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 2 . This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment

ANALISIS HARGA POKOK PRODUKSI DAN PENERAPAN TARGET COSTING PADA UD WAJUKU MAKASSAR

OpenAIRE

-, CHAIDIR HAFID

2017-01-01

ABSTRAK Analisis Harga Pokok Produksi dan Penerapan Target Costing pada UD Wajuku Makassar The Analysis of The Cost of Goods Manufactured and Implementation of Target Costing in UD Wajuku Makassar Chaidir Hafid Asri Usman Syahrir Penelitian ini bertujuan untuk mengetahui perhitungan harga pokok produksi baju kaos polos sebelum dan setelah penerapan metode target costing pada UD Wajuku Makassar. Metode pengumpulan data yang digunakan adalah dokumentasi. Metode analisis dat...

Analisis Komoditi Unggulan Subsektor Tanaman Pangan di Sumatera Utara Tahun 2010 – 2014

OpenAIRE

Sinaga, Terry Praganda

2016-01-01

Tujuan penelitian ini adalah untuk mengetahui perkembangan produksi komoditi tanaman pangan selama periode tersebut sehingga dapat menganalisis komoditi subsektor tanaman pangan yang menjadi unggulan di Sumatera Utara. Komoditi unggulan tersebut juga dijabarkan untuk setiap kabupatem/kota yang ada di Sumatera Utara. Metode yang digunakan yaitu secara Convenience Sampling, dan metode analisis data dengan menggunakan analisis Location Quotient. Hasil penelitian menyimpulkan ba...

Nuclear reactor instrumentation at research reactor renewal

International Nuclear Information System (INIS)

Baers, B.; Pellionisz, P.

1981-10-01

The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

Determination of the flows profile in the role of power in the central thimble of TRIGA Mark III Reactor; Determinacion del perfil de flujos en funcion de la potencia en el dedal central del Reactor Triga Mark III

Energy Technology Data Exchange (ETDEWEB)

Garcia F, A.

2010-07-01

The overall objective of the thesis project is to determine the flow profiles sub cadmic and epi cadmic in the central thimble to different powers and operation times of TRIGA Mark III Reactor, using activation foils as detectors. In the reactor operation, it is necessary to know the neutron flow profile for to realize other tasks as: the radioisotopes production, research in reactors physics and fuel burning. The distribution of the neutron flow, accurately reflects what is happening in the reactor core, plus the flows value in this distribution is directly related to the power generated. For this reason it is performed the sub cadmic flow measurement with energies between 0 and 0.4 eV (energy of the cadmium cut E{sub cd} approx 0.4 eV) and epi cadmic flow with energies greater than 0.4 eV, in the central thimble powers to the powers of 10, 100 W, 1, 10 100 Kw and 1 MW. The method used is known as flakes activation, which is to be arranged by placing flakes ( 3 mm of diameter and 0.0508 mm of thickness) of a given material (either Au, In, Cu, Mn, etc.) into an aluminum tube outside diameter equal to 6.35 mm, alternating flakes with lids covered and discovered of cadmium (3.4 mm of diameter and 0.508 mm of thickness) and separated by lucite pieces of 3 mm of diameter and 25.4 mm in length. After irradiating the flakes for some time, is measured the gamma activity of each of them, using a hyper pure germanium detector of high resolution. Already known gamma activity, proceed to calculate the epi cadmic and sub cadmic flows using a computer program in Fortran language, called Caflu. (Author)

Advanced reactor development

International Nuclear Information System (INIS)

Till, C.E.

1989-01-01

Consideration is given to what the aims of advanced reactor development have to be, if a new generation of nuclear power is really to play an important role in man's energy generation activities in a fragile environment. The background given briefly covers present atmospheric evidence, the current situation in nuclear power, how reactors work and what can go wrong with them, and the present magnitudes of world energy generation. The central part of the paper describes what is currently being done in advanced reactor development and what can be expected from various systems and various elements of it. A vigorous case is made that three elements must be present in any advanced reactor development: (1) breeding; (2) passive safety; and (3) shorter-live nuclear waste. All three are possible. In the right advanced reactor systems the ways of achieving them are known. But R and D is necessary. That is the central argument made in the paper. Not advanced reactor prototype construction at this point, but R and D itself. (author)

ANALISIS SENSITIVITAS TURBULENSI ALIRAN PADA KANAL BAHAN BAKAR PWR BERBASIS CFD

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Endiah Puji Hastuti

2015-04-01

Full Text Available Turbulensi aliran pendingin pada proses perpindahan panas berfungsi untuk meningkatkan nilai koefisien perpindahan panas, tidak terkecuali aliran dalam kanal bahan bakar. Program CFD (CFD=computational fluid dynamics, FLUENT adalah program komputasi berbasis elemen hingga (finite element yang mampu memprediksi dan menganalisis fenomena dinamika aliran fluida secara teliti. Program perhitungan CFD dipilih dalam penelitian ini karena selain akurat juga dapat memberikan visualisasi dengan baik. Penelitian ini bertujuan untuk memahami karakteristika perpindahan panas, massa dan momentum dari dinding rod bahan bakar ke pendingin secara visual, pada medan temperatur, medan tekanan, dan medan energi kinetika pendingin, sebagai fungsi dinamika aliran di dalam kanal, pada kondisi tunak dan transien. Analisis dinamika aliran pada kanal bahan bakar PWR berbasis CFD dilakukan dengan menggunakan sampel data reaktor PWR dengan daya 1000 MWe dengan susunan bahan bakar 17x17. Untuk menguji sensitivitas persamaan aliran yang sesuai dengan model aliran turbulen pada kanal bahan bakar dilakukan pemodelan dengan menggunakan persamaan k-omega (Ƙ-ω, k-epsilon (Ƙ-ε, dan Reynold stress model (RSM. Pada analisis sensitivitas aliran turbulen di dalam kanal digunakan model mesh hexahedral dengan memilih tiga geometri sel yang masing masing berukuran 0,5 mm; 0,2 mm dan 0,15 mm. Hasil analisis menunjukkan bahwa pada analisis kondisi tunak (steady state, terdapat hasil yang mirip pada model turbulen Ƙ-ε standard dan Ƙ-ω standard. Pengujian terhadap kriteria Dittus Boelter untuk bilangan Nusselt menunjukkan bahwa model Reynold stress model (RSM direkomendasikan. Analisis sensitivitas terhadap geometri mesh antara sel yang berukuran 0,5 mm, 0,2 mm dan 0,15 mm, menunjukkan bahwa geometri sel sebesar 0,5 mm telah mencukupi. Aliran turbulen berkembang penuh telah tercapai pada model LES dan DES, meskipun hanya dalam waktu singkat (3 s, model LES memerlukan waktu komputasi

APLIKASI METODE-METODE AGGLOMERATIVE DALAM ANALISIS KLASTER PADA DATA TINGKAT POLUSI UDARA

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Dewi Rachmatin

2014-09-01

Full Text Available ABSTRAK   Analisis Klaster merupakan analisis pengelompokkan data yang mengelompokkan data berdasarkan informasi yang ditemukan pada data. Tujuan dari analisis klaster adalah agar objek-objek di dalam satu kelompok memiliki kesamaan satu sama lain sedangkan dengan objek-objek yang berbeda kelompok memiliki perbedaan. Analisis klaster dibagi menjadi dua metode yaitu metode hirarki dan metode non-hirarki. Metode hirarki dibagi menjadi dua, yaitu metode agglomerative (pemusatan dan metode divisive (penyebaran. Metode-metode yang termasuk dalam metode agglomerative adalah Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward’s Method, Centroid Method dan Median Method. Pada artikel ini dibahas metode-metode agglomerative tersebut yang diterapkan pada data tingkat polusi udara. Masing-masing metode tersebut memberikan jumlah klaster yang berbeda.   Kata Kunci : Analisis Klaster, Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward’s Method, Centroid Method dan Median Method.     ABSTRACT Cluster analysis is an analysis of the data classification based on information found in the data.The objective of cluster analysis is that the objects in the group have in common with each other, while the different objects have different groups. Cluster analysis is divided into two methods : the method of non-hierarchical and hierarchical methods.Hierarchical method is divided into two methods, namely agglomerative methods (concentration and divisive methods (deployment. The methods included in the agglomerative method is Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward 's Method, Method and Median Centroid Method. In this article discussed the agglomerative methods were applied to the data rate of air pollution. Each of these methods provides a different number of clusters.   Keywords: Cluster Analysis , Single Linkage Method, Complete Linkage Method, Average Linkage Method, Ward

Risk analysis; Analisis de riesgos

Energy Technology Data Exchange (ETDEWEB)

Baron, J H; Nunez McLeod, J; Rivera, S S [Universidad Nacional de Cuyo, Mendoza (Argentina). Instituto de Capacitacion Especial y Desarrollo de Ingenieria Asistida por Computadora (CEDIAC)

1997-07-01

This book contains a selection of research works performed in the CEDIAC Institute (Cuyo National University) in the area of Risk Analysis, with specific orientations to the subjects of uncertainty and sensitivity studies, software reliability, severe accident modeling, etc. This volume presents important material for all those researches who want to have an insight in the risk analysis field, as a tool to solution several problems frequently found in the engineering and applied sciences field, as well as for the academic teachers who want to keep up to date, including the new developments and improvements continuously arising in this field. [Spanish] Este libro contiene una seleccion de trabajos de investigacion realizados dentro del Instituto de Capacitacion Especial y Desarrollo de la Ingenieria Asistida por Computadora en el area del analisis de riesgos, con una orientacion hacia el estudio de incertidumbres y sensibilidad, confiabilidad de software, modelacion de accidentes severos, etc. Este volumen recoge un material de indudable importancia e interes para todos aquellos investigadores y profesionales que desean incursionar en este campo del analisis de riesgos como herramienta para la solucion de problemas frecuentemente encontrados en la ingenieria y las ciencias aplicadas, asi como para los academicos que desean mantenerse al dia, conociendo los nuevos desarrollos y tecnicas que constantemente aparecen en su area.

ANALISIS PENGARUH KINERJA LINGKUNGAN TERHADAP KINERJA INDUSTRI KECIL

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Sukirman -

2012-03-01

Full Text Available Tujuan penelitian adalah mengidentifikasi, menganalisis praktik pengelolaan lingkungan pada sentra industri kecil dibandingkan best practices dalam upaya meningkatkan kinerja lingkungan di Kabupaten Pati. Kajian difokuskan pada pengelolaan lingkungan secara efektif dengan melibatkan variabel inisiatif lingkungan, keterlibatan karyawan, dan integrasi dengan supplier. Populasinya adalah seluruh perusahaan Industri Kecil di Kabupaten Pati. Sampel berjumlah 97 perusahaan. Teknik sampling menggunakan kluster sampling, dengan sampel pada sentra industri kecil di Kabupaten Pati.  Analisis menggunakan analisis deskriptif dan analisis komparatif. Hasil penelitian menunjukkan praktik pengelolaan lingkungan pada sentra industri kecil di Kabupaten Pati belum dilaksanakan secara optimal. Sementara itu, variabel integrasi supplier berpengaruh langsung terhadap kinerja perusahaan.The purpose of this study is to identify and to analyze an environmental management practice which is compared to the best practices in order to improve environmental performance in the industrial centers in Pati District. This study focuses on managing the environment effectively by involving environmental initiative variables, employee involvement, and integration of suppliers. Population in this study was all small industrial enterprises in Pati regency which has 97 companies as data samples. Data were collected by using cluster sampling techniques, and samples were taken from small industrial centers in the District of Pati. Data were analyzed by using descriptive and comparative methods. Results of this study showed that environmental management practices in small industrial centers had not been implemented optimally. Meanwhile, supplier integration variables influenced directly toward corporate performance.

Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

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I Gusti Ayu Made Srinadi

2014-06-01

Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

Directory of Open Access Journals (Sweden)

I Gusti Ayu Made Srinadi

2015-04-01

Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

ANALISIS KELAYAKAN FINANSIAL PROYEK NARROWNECK PRESS AND BLOW UNTUK PROSES PRODUKSIBOTOL MINUMAN BERENERGI DI PT. ABC

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Toni MT Munthe

2015-08-01

Full Text Available PT. ABC merupakan salah satu pabrik yang memproduksi botol kemasan kaca. Penelitian ini bertujuan untuk mengetahui layak atau tidaknya rencana investasi pada proyek Narrow Neck Press and Blow secara finansial di PT. ABC pada periode bulan April 2014 hingga bulan Juni 2014. Analisis kelayakan finansial proyek Narrow Neck Press and Blow, menggunakan metode analisis Net Present Value, Internal Rate of Return, Payback Period dan Sensitivity Analysis. Perbedaan antara nilai sekarang dari semua kas masuk dengan nilai sekarang dari semua kas keluar dari suatu proyek atau suatu investasi diperoleh dengan metode NPV, sedangkan untuk mencari tingkat bunga yang menyamakan nilai sekarang dari aliran kas bersih dan investasi diperoleh dengan metode IRR. Metode analisis yang dapat digunakan untuk mengetahui berapa lamakah waktu yang diperlukan untuk menutup dana yang dikeluarkan untuk suatu proyek dapat diperoleh dengan metode Payback Period. Setelah itu, dilakukan pengujian menggunakan sensitivitas analisis untuk mengetahui tingkat sensitivitas untuk tiap-tiap parameter terhadap persentase kenaikan dan penurunan. Dari hasil analisis data diperoleh nilai NPV sebesar Rp. 1.179.728.649.900,06, nilai IRR sebesar 56,36% dan periode pengembalian terletak pada 2 tahun 2 bulan 9 hari. Dengan menggunakan analisis sensitivitas dapat diketahui bahwa proyek ini sangat sensitif terhadap penurunan volume produksi. Berdasarkan hasil perhitungan, titik impas akan dicapai apabila volume produksi 213.403.267 unit per tahun atau 88,92% dari volume produksi awal. Nilai ini menunjukkan bahwa apabila volume produksi pada suatu periode mengalami penurunan lebih dari 11,08% dari volume produksi awal, maka investasi tersebut akan merugikan.

Analisis Industri Ritel Di Indonesia

OpenAIRE

Soliha, Euis

2008-01-01

This article presents an overview the analisys of retail industry in Indonesia.Retail industry in Indonesia grow rapidly. Industrial presence of modern retailbasically exploits public shopping pattern especially middle-weight and to which donot want to mill around in traditional market. Analysis Five Forces is used toanalysis retail industry. Analysis five force is bargaining power of buyers,bargaining power of suppliers, threat of new entrants, threat of new substituteproducts, and rivalry a...

Analisis Value Chain Di Industri Otomotif

OpenAIRE

Hendri, Hendri

2017-01-01

Penelitian ini untuk menganalisis industri otomotif. Tujuan dari penelitian ini adalah untuk menganalisis dan mengetahui aktivitas dan kondisi internal proses industri manufaktur dengan menggunakan value chain guna masukan dimasa akan datang bagi industri otomotif secara khusus. Value Chain merupakan rantai nilai yang dapat mengetahui kekuatan Perusahaan, keuntungan dan kesuksesan dari rantai aktivitas dalam Perusahaan atau industri manufaktur.Metode analisis menggunakan Statistika Deskript...

The Analisis Sentimen Sosial Media Twitter Dengan Algoritma Machine Learning Menggunakan Software R

Directory of Open Access Journals (Sweden)

Jaka Aulia Pratama

2017-10-01

Full Text Available Media sosial adalah wadah untuk mengungkapkan opini terhadap suatu topik tertentu. Ketersediaan informasi dan opini dari para pengguna media sosial merupakan kumpulan dokumen data berupa teks yang amat sangat besar dan berguna untuk kepentingan penelitian maupun membuat suatu keputusan bagi pihak – pihak tertentu. Text Mining bisa didefinisikan sebagai proses penggalian informasi di mana pengguna berinteraksi dengan kumpulan dokumen dari waktu ke waktu dengan menggunakan suatu alat analisis. Analisis sentimen atau Opinion Mining adalah salah satu studi di bidang komputasi yang berhubungan dengan kasus publik mengenai opini, penilaian, sikap, dan emosi. Penelitian ini akan menggunakan metode Machine Learning pada analisis sentimen pengguna layanan jejaring sosial Twitter terhadap Donald Trump dan Barack Obama dalam 20000 tweets. Nilai akurasi metode Machine Learning yang diperoleh cukup tinggi yaitu 87.52% untuk Data Training dan 87.4% untuk Data Testing.

Uncertainty and sensitivity analysis methodology in a level-I PSA (Probabilistic Safety Assessment); Analisis de incertidumbres y sensibilidad aen un APS (Analisis Probabilistico de Seguridad) nivel-I

Energy Technology Data Exchange (ETDEWEB)

Nunez McLeod, J E; Rivera, S S [Universidad Nacional de Cuyo, Mendoza (Argentina). Instituto de Capacitacion Especial y Desarrollo de Ingenieria Asistida por Computadora (CEDIAC)

1997-07-01

This work presents a methodology for sensitivity and uncertainty analysis, applicable to a probabilistic safety assessment level I. The work contents are: correct association of distributions to parameters, importance and qualification of expert opinions, generations of samples according to sample sizes, and study of the relationships among system variables and system response. A series of statistical-mathematical techniques are recommended along the development of the analysis methodology, as well different graphical visualization for the control of the study. (author) [Spanish] En este trabajo se presenta una metodologia de analisis de sensibilidad e incertidumbres, aplicable a un analisis probabilistico de seguridad (APS) de nivel I. En el cual se plantea: la adecuada asociacion de distribuciones a variables, la importancia y penalizacion de la opinion de expertos, la generacion de muestras y su tamano, y el estudio de las relaciones entre las variables del sistema y la respuesta de este. Ademas durante el desarrollo de la metodologia de analisis se recomiendan una serie de tecnicas estadistico-matematicas y tipos de visualizacion grafica para el control del estudio. (autor)

Review of operational experience with the gas-cooled Magnox reactors of the United Kingdom Central Electricity Generating Board

International Nuclear Information System (INIS)

Cave, L.; Clarke, A.W.

1984-01-01

The paper provides a review, which is mainly of a statistical nature, of 260 reactor years of operating experience which the (United Kingdom) Central Electricity Generating Board (CEGB) has obtained with its gas-cooled, graphite moderated Magnox reactors. The main emphasis in the review is on safety rather than on availability. Data are provided on the overall incidence and frequencies of faults and it is shown that the plant items which are predominantly responsible for recorded faults are the gas circulators and the turbo-alternators. Analysis of the reactor trip experience shows that the incidence of events which necessitate an automatic shutdown of the reactor has been about one per reactor year and that of other events leading to a reactor trip has not been much higher (1.4 per reactor year). As would be expected from the length of the operating experience, some relatively rare events have occurred (expected frequency 10 -2 per reactor year, or less) but on each occasion the reactor shutdown system and decay heat removal systems functioned satisfactorily. No overheating of, or damage to, the fuel occurred as a result of these rare events or of other, more frequent, faults. Analysis of the trend of failure rates has shown an improvement with time in nearly all safety-related items and external inspection of the primary coolant circuits has shown no significant deterioration with time. However, some derating of the reactors has been necessary to reduce the effects of oxidation of mild steel in CO 2 , in order to obtain optimum service lives. In spite of major differences between the systems, a comparison of the failure rates of analogous systems and plant items in PWRs and the Magnox reactors show a considerable similarity. Overall, the review of CEGB's operational experience with its Magnos reactors has shown that the frequencies of faults in systems and plant items has been satisfyingly low. (author)

Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor *

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Parma Edward J.

2016-01-01

Full Text Available Characterization of the neutron environment in the central cavity of the Sandia National Laboratories' Annular Core Research Reactor (ACRR is important in order to provide experimenters with the most accurate spectral information and maintain a high degree of fidelity in performing reactor experiments. Characterization includes both modeling and experimental efforts. Building accurate neutronic models of the ACRR and the central cavity “bucket” environments that can be used by experimenters is important in planning and designing experiments, as well as assessing the experimental results and quantifying uncertainties. Neutron fluence characterizations of two bucket environments, LB44 and PLG, are presented. These two environments are used frequently and represent two extremes in the neutron spectrum. The LB44 bucket is designed to remove the thermal component of the neutron spectrum and significantly attenuate the gamma-ray fluence. The PLG bucket is designed to enhance the thermal component of the neutron spectrum and attenuate the gamma-ray fluence. The neutron characterization for each bucket was performed by irradiating 20 different activation foil types, some of which were cadmium covered, resulting in 37 different reactions at the peak axial flux location in each bucket. The dosimetry results were used in the LSL-M2 spectrum adjustment code with a 640-energy group MCNP-generated trial spectrum, self-shielding correction factors, the SNLRML or IRDFF dosimetry cross-section library, trial spectrum uncertainty, and trial covariance matrix, to generate a least-squares adjusted neutron spectrum, spectrum uncertainty, and covariance matrix. Both environment character-izations are well documented and the environments are available for use by experimenters.

AZTLAN platform: Mexican platform for analysis and design of nuclear reactors; AZTLAN platform: plataforma mexicana para el analisis y diseno de reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Francois L, J. L.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

2014-10-15

The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

Final results of the cadmium and spectral ratios obtained inside of the fuel rod positioned in the central position of the IPEN/MB-01 nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Bitelli, Ulysses d' Utra; Mura, Luiz Ernesto C.; Santos, Diogo Feliciano dos, E-mail: ubitelli@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Lambiasi, Beatriz G.N. [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil)

2015-07-01

The spectral ratios are very important to determine some nuclear reactors parameters such as reaction rates, fuel lifetime, etc and some safety operational conditions. This study aims to determine the spectral ratios in 2 (two) spatial positions located inside the core of the Nuclear Reactor IPEN/MB-01. These places are at the central position of the nuclear reactor core in an asymptotic neutron flux region. The experiment consists in inserting different activation foil detectors inside an experimental fuel rod. The experimental rod is assembled at the central position of the reactor core. Activation neutron foil detectors of different elements such as {sup 197}Au, {sup 238}U, {sup 45}Sc, {sup 58}Ni, {sup 24}Mg, {sup 47}Ti and {sup 115m}In were used to cover a large range of neutron spectrum. Saturation activity per target nucleus was obtained by gamma spectrometry using a HPGe system. The experimental cadmium ratios compared with values computed by MCNP-4C code show good agreement. (author)

ANALISIS PENGENDALIAN DAYA REAKTOR PCMSR DENGAN LAJU ALIR PENDINGIN

Directory of Open Access Journals (Sweden)

Iqbal Syafin Noha

2015-03-01

Full Text Available Passive Compact Molten Salt Reactor (PCMSR merupakan pengembangan dari Molten Salt Reactor (MSR yang memiliki karakter berbeda dengan lima reaktor generasi IV lainnya, yaitu menggunakan bahan bakar leburan garam. Pada reaktor MSR, garam lebur tidak digunakan sebagai pendingin tetapi digunakan sebagai medium pembawa bahan bakar. Dengan fase bahan bakar yang berupa garam lebur LiF-BeF2-ThF4-UF4, maka dapat dilakukan pengendalian daya dengan mengatur laju aliran bahan bakar dan pendingin. Tujuan penelitian ini adalah untuk mengetahui pengaruh perubahan laju alir pendingin terhadap daya reaktor PCMSR. Analisis dilakukan dengan empat jenis masukan untuk perubahan laju alir pendingin, yaitu masukan step, ramp, eksponensial, dan sinusoidal. Untuk masukan step, laju alir pendingin dibuat berubah secara mendadak. Selanjutnya untuk masukan ramp dan eksponensal, perubahan laju alir masing-masing dibuat perlahan secara linear dan mengikuti fungsi eksponensial. Kemudian untuk masukan sinusoidal, laju alir berubah naik turun secara periodik dengan memvariasikan frekuensi dari perubahan laju alir tersebut. Hasil penelitian menunjukkan bahwa penurunan laju alir pendingin sebesar 50% dari laju pendingin sebelumnya, menyebabkan daya pada reaktor PCMSR turun sebesar 63% dari daya sebelumnya. Jika terjadi fluktuasi laju aliran pendingin, maka semakin cepat perubahan tersebut, maka respon daya yang diberikan semakin kecil. Pada frekuensi yang sangat cepat, daya reaktor menjadi konstan dan cenderung tidak memiliki respon terhadap laju aliran. Hal ini merupakan salah satu aspek keselamatan reaktor, karena reaktor tidak merespon perubahan yang terlalu cepat. Kemampuan reaktor mengatur daya menyesuaikan laju aliran pendingin merupakan aspek keselamatan lainnya. Kata kunci : PCMSR, pengendalian daya, laju alir pendingin, uji respon   Passive Compact Molten Salt Reactor (PCMSR is the development of Molten Salt Reactor (MSR which has different character from other five

Analisis Kebijakan dan Efektivitas Organisasi

Directory of Open Access Journals (Sweden)

Amir Syarifudin Kiwang

2015-05-01

Full Text Available Penerapan Peraturan Gubernur Nusa Tenggara Timur Nomor 8 Tahun 2011 tentang Organisasi dan Tata Kerja Unit Pelaksana Teknis Pendidikan dan Pelatihan Koperasi dan Usaha Mikro Kecil dan Menengah pada Dinas Koperasi dan Usaha Mikro Kecil dan Menengah Provinsi Nusa Tenggara Timur adalah dalam rangka untuk meningkatkan efektivitas kerja organisasi pada UPT Diklat Koperasi dan UMKM. Penelitian ini berusaha untuk melihat dampak kebijakan organisasi terhadap efektivitas organisasi dengan menggunakan enam elemen variabel dari kebijakan dan praktik manajemen. Keenam elemen tersebut adalah penetapan tujuan strategis, pencarian dan pemanfaatan sumber daya, lingkungan prestasi, proses komunikasi, kepemimpinan dan pengambilan keputusan, serta adaptasi dan inovasi organisasi. Penelitian kualitatif ini menggunakan pendekatan studi kasus. Teknik analisis data yang digunakan adalah analisis data model Miles dan Huberman, yang terdiri atas reduksi data, display/penyajian data, dan kesimpulan/verifikasi. Hasil penelitian menunjukkan bahwa efektivitas organisasi pada UPT Diklat koperasi dan UMKM belum berjalan secara baik, hal ini dapat dilihat dari beberapa hal antara lain, belum adanya tenaga spesialisasi pengelola diklat dan tenaga khusus (sarjana di bidang perkoperasian dan kondisi lingkungan kerja (lingkungan prestasi pada UPT Diklat koperasi dan UMKM yang belum efektif. Penempatan pegawai juga belum tepat, mutasi ke UPT Diklat Koperasi dan UMKM tidak memperhatikan latar belakang pendidikan dan spesialisasi/keahlian pegawai sehingga membutuhkan waktu dalam proses penyesuaian serta menurunkan jumlah pelaksanaan diklat dikarenakan keterbatasan alokasi dana.

ANALISIS PERIKANAN HUHATE DI PERAIRAN LARANTUKA, FLORES

Directory of Open Access Journals (Sweden)

Mohamad Adha Akbar

2016-11-01

Full Text Available Informasi mengenai beberapa aspek perikanan huhate sangat diperlukan sebagai bahan untuk perencanaan pengelolaan perikanan yang berkelanjutan. Penelitian ini dilakukan di Larantuka, Flores Timur pada tahun 2014 dengan tujuan untuk menganalisis perikanan huhate sebagai salah satu tulang punggung perikanan TCT. Kegiatan penelitian diprioritaskan pada analisis unit alat tangkap, daerah penangkapan, komposisi hasil tangkapan dan estimasi Total Faktor Produktivitas (TFP perikanan huhate. Basis data pengukuran adalah himpunan  data pendaratan dan observasi lapang. Hasil penelitian menunjukan bahwa karakteristik armada terdiri dari kapal yang terbuat dari fibreglass dengan kisaran bobot kapal 6 - 30 GT. Daerah penangkapan di sekitar perairan Laut Sawu dan Laut Flores. Hasil tangkapan utama didominansi oleh cakalang (Katsuwonus pelamis sebanyak 82%, juwana tuna (Thunnus spp. 17% dan tongkol (Auxis spp. 1% serta hasil tangkapan ikutan lemadang (Coryphaena hippurus dan marlin (Makaira spp. < 1%. Hasil analisis tangkapan per unit upaya (CPUE memberikan nilai rata-rata sebesar 1,1 ton/trip (0,4-1,7 ton/trip dengan nilai tertinggi terjadi pada Februari, sedangkan terendah terjadi pada Januari. Hasil penelitian menunjukkan terdapat hubungan yang signifikan antara tren bulanan CPUE dan nilai TFP.

ANALISIS PENGELOLAAN LINGKUNGAN PERMUKIMAN DI KABUPATEN SOPPENG

Directory of Open Access Journals (Sweden)

Bakhrani Rauf

2016-08-01

Full Text Available Penelitian ini  bertujuan untuk mendeskripsikan pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 penyediaan dan penanganan lahan terbuka hijau (open space; (2 penyediaan dan penanganan drainase; (3  penanganan sampah; (4 penyediaan dan penanganan pembuangan veses (septic tank. Jenis penelitian ini adalah penelitian kuantitatif dengan pendekatan survei.  Sampel wailayah penelitian ini adalah satu RW di ibu kota kabupaten dan satu RW di desa yang dipilih dengan metode purpossive sampling,  yaitu RW yang sudah maju di ibu kota kabupaten dan RW yang tertinggal di desa. Responden sebanyak 50 kepala keluarga yakni masing-masing 25 kepala keuarga di setiap RW, dipilih dengan  systematic random sampling.  Teknik pengumpulan data yang dilakukan adalah melakukan observasi langsung dan dilengkapi dengan wawancara terhadap responden. Analisis yang digunakan adalah analisis deskriptif. Hasil penelitian menunjukkan bahwa pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 ketersediaan dan penanganan lahan terbuka hijau (open space ditemukan belum memadai; (2 ketersediaan drainase (air kotor dan air hujan ditemukan belum memadai; (3 Penanganan sampahbelum memadai; dan (4 penanganan veses dan penyediaan septic tankbelum memadai.

Analisis Perbandingan Material Slab Beton Pada Perkerasan Apron Dengan Menggunakan Program Bantu Elemen Hingga

Directory of Open Access Journals (Sweden)

Hendrawan Setyo Warsito

2016-04-01

Full Text Available Kekuatan slab beton sangat dipengaruhi oleh jenis material yang dipakai. Jenis material yang dimaksud adalah material beton dengan menggunakan PC (Portland Cement dan penggunaan geopolimer dalam komposisi campuran slab beton. Beton geopolimer merupakan beton yang ramah lingkungan. Permasalahan lain yang timbul adalah letak roda pesawat tidak selalu berada pada titik yang sama disuatu permukaan slab beton apron. Pada tugas akhir ini dimaksudkan untuk menganalisis suatu slab beton yang dibebani roda pesawat dengan campuran variasi material beton dan variasi letak roda pesawat pada slab beton dengan program bantu metode elemen hingga. Dengan data pergerakan pesawat, spesifikasi apron bandara Juanda kondisi eksisting. Dilakukan perhitungan tebal slab beton menggunakan software FAARFIELD dan diperoleh tebal slab beton sebesar 442,5 mm. Dari analisis program bantu elemen hingga dapat diperoleh tegangan pada slab beton yang ditimbulkan oleh pembebanan roda pesawat. Hasil validasi dari analisis tegangan menggunakan program bantu elemen hingga dengan analisis Westergaard yaitu memiliki nilai tegangan yang hampir sama pada ketebalan slab beton 450mm. Nilai tegangan tiap-tiap material beton menunjukan nilai tebal slab beton yang diijinkan untuk tipe pesawat tertentu. Dari analisis menggunakan program bantu elemen hingga tebal slab beton yang diijinkan untuk material slab beton PC yaitu sebesar 425mm. Sedangkan untuk material beton geopolimer yaitu sebesar  415 mm.

Analisis Model Penelusuran Backward Chaining dalam Mendeteksi Tingkat Kecanduan Game pada Anak

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Anastasya Latubessy

2017-10-01

Full Text Available Game addiction rate can be detected by applying expert system. This study developed a model of game addiction analysis using backward chaining. This model uses six types of game addiction behavior, among others, salience, euphoria, conflict, tolerance, withdrawal, relapse and reinstatement. Someone is said to be addicted to the game if it meets at least three types of game addiction behavior. Testing the validity of the model is done by testing the closeness of the agreement between the model analysis and expert analysis, resulting in a value of 0.78 which means having a strong agreement. Tingkat kecanduan game dapat dideteksi dengan mengaplikasikan sistem pakar. Penelitian ini mengembangkan model analisis tingkat kecanduan game menggunakan backward chaining. Model ini menggunakan enam jenis perilaku kecanduan game antara lain, salience, euphoria, conflict, tolerance, withdrawal, relapse dan reinstatement. Seseorang dikatakan kecanduan game jika memenuhi paling sedikit tiga jenis perilaku kecanduan game. Pengujian validitas model dilakukan dengan menguji keeratan kesepakatan antara analisis model dan analisis pakar, menghasilkan nilai 0,78 yang berarti memiliki keeratan kesepakatan kuat.

Estetika Tari Minang dalam Kesenian Randai Analisis Tekstual-Kontekstual

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Sri Rustiyanti

2013-03-01

Full Text Available ABSTRACT   This paper reveals textual and contextual Randai, among other things, an analysis of Gerak Ga­ lombang Randai, an analysis of the character of Anak Randai, and at the end of the study series, to reveal the values contained in Randai as a cultural reality, which in principle is an inseparable part of the existence of Minangkabau community as the cultural support. The variety of motion used in Gerak Galombang Randai is not only a decoration of the motion beauty (tangible, but it also can be translated, as well as a symbol or emblem that has educational meanings (intangible, and can be an example of the daily life of the indigenous Minangkabau society.   Keywords: Minang Dance aesthetic, Randai, textual­contextual analysis     ABSTRAK   Tulisan ini mengungkap teksual dan kontekstual Randai, di antaranya, analisis terhadap gerak galombang Randai, analisis karakter tokoh anak Randai, dan sebagai akhir dari rang- kaian penelitian ini, mengungkapkan nilai-nilai yang terdapat pada Randai sebagai realitas budaya, yang pada prinsipnya merupakan bagian yang tak dapat dipisahkan dari eksistensi masyarakat Minangkabau sebagai penyangga kebudayaan. Ragam gerak yang digunakan dalam gerak galombang Randai itu kiranya tidak hanya sekedar hiasan keindahan gerak be- laka (tangibel, namun ia dapat diterjemahkan, sekaligus merupakan simbol atau lambang yang bermakna  mendidik (intangibel, dan dapat   menjadi teladan dalam kehidupan se- hari-hari dalam masyarakat adat di Minangkabau.   Kata Kunci: estetika Tari Minang, Randai, analisis tekstual-kontekstual

Transient Analysis of Generation IV quick reactors; Analisis de Transitorios en Reactores Rapidos de Generacion IV

Energy Technology Data Exchange (ETDEWEB)

Vazquez, M.; Martin-Fuertes, F.

2013-07-01

As a complement to the attached code 3D neutron-CIEMAT thermohydraulic added a module to simulate transient. Temporary kinetics is resolved by factoring flow in a spatial part and another storm. MCNP provides the reactivity and updated spatial function and COBRA-IV calculates the temperature distribution. Temporary dependence of amplitude is calculated using time delayed neutron Kinetic equations. As an example of application, examines a transient loss of flow in MYRRHA, a lead-cooled experimental reactor.

Light water reactor safety

CERN Document Server

Pershagen, B

2013-01-01

This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

ANALISIS PERBAIKAN SISTEM PENTANAHAN TELEKOMUNIKASI

Directory of Open Access Journals (Sweden)

Umar Umar

2015-04-01

Hasil dari penelitian ini adalah perbaikan sistem pentanahan site Kampung Baru dengan menggunakan konfigurasi single point connection window (SPCW, untuk mengamankan sistem telekomunikasi dari kebocoran arus dan petir serta imbasnya.  Perbaikan sistem pentanahan di site Kampung Baru menggunakan banyak elektroda yang membentuk persegi dikarenakan topografi tempat di sana yang memungkinkan dan efektif adalah menggunakan sistem tersebut. Berdasarkan hasil analisis dan perhitungan perbaikan sistem di site Kampung Baru, didapatkan nilai perhitungan sistem pentanahan adalah 1.34 Ohm serta pengukurannya 1.21-1.25 Ohm.

Improved nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

Nuclear reactors

International Nuclear Information System (INIS)

Yoshioka, Michiko.

1985-01-01

Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

Neutron analysis of the fuel of high temperature nuclear reactors; Analisis neutronico del combustible de reactores nucleares de alta temperatura

Energy Technology Data Exchange (ETDEWEB)

Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

2014-10-15

In this work a neutron analysis of the fuel of some high temperature nuclear reactors is presented, studying its main features, besides some alternatives of compound fuel by uranium and plutonium, and of coolant: sodium and helium. For this study was necessary the use of a code able to carry out a reliable calculation of the main parameters of the fuel. The use of the Monte Carlo method was convenient to simulate the neutrons transport in the reactor core, which is the base of the Serpent code, with which the calculations will be made for the analysis. (Author)

ANALISIS DAYA SAING KEDELAI INDONESIA

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Sarwono Sarwono

2014-09-01

Full Text Available RCA (Revealed Comparative Advantage index of soybean in Indonesia from 1983 up to 2013 is less than one, mostly. It means that the competitiveness of soybean in Indonesia is low. The purpose of this study is to analyze the factors influence the soybean competitiveness. OLS (Ordinary Least Square was used as the analysis method. Hypotheses test based on that analysis model is not bias, so that, classic divergence test is needed. It is for getting the Best Linier Unbiased Estimator (BLUE appraisal. T statistic and F statistic were also applied. The result of this research shows that production and export have positive and significant influence. In addition, exchange rate and government policy do not influence the Indonesia soybean competitiveness.Indeks RCA (Revealed Comparative Advantage kedelai Indonesia dari tahun 1983-2013 kecenderungan bernilai kurang dari satu yang berarti daya saing kedelai Indonesia rendah.Penelitian ini bertujuan untuk menganalisis faktor-faktor yang mempengaruhi daya saing kedelai Indonesia.Metode analisis yang digunakan adalah Ordinary Least Square (OLS.Pengujian hipotesis berdasarkan model analisis tersebut tidak bias maka perlu dilakukan uji penyimpangan klasik yang tujuannya agar diperoleh penaksiran yang bersifat Best Linier Unbiased Estimator (BLUE.Pengujian statistik menggunakan uji t statistikdan uji f statistik.Hasil penelitian ini menunjukkan bahwa produksi dan ekspor berpengaruh secara positif dan signifikan terhadap daya saing kedelai Indonesia. Nilai tukar rupiah dan kebijakan pemerintah tidak berpengaruh terhadap daya saing kedelai Indonesia.

Determination of the flows profile in the role of power in the central thimble of TRIGA Mark III Reactor

International Nuclear Information System (INIS)

Garcia F, A.

2010-01-01

The overall objective of the thesis project is to determine the flow profiles sub cadmic and epi cadmic in the central thimble to different powers and operation times of TRIGA Mark III Reactor, using activation foils as detectors. In the reactor operation, it is necessary to know the neutron flow profile for to realize other tasks as: the radioisotopes production, research in reactors physics and fuel burning. The distribution of the neutron flow, accurately reflects what is happening in the reactor core, plus the flows value in this distribution is directly related to the power generated. For this reason it is performed the sub cadmic flow measurement with energies between 0 and 0.4 eV (energy of the cadmium cut E cd ∼ 0.4 eV) and epi cadmic flow with energies greater than 0.4 eV, in the central thimble powers to the powers of 10, 100 W, 1, 10 100 Kw and 1 MW. The method used is known as flakes activation, which is to be arranged by placing flakes ( 3 mm of diameter and 0.0508 mm of thickness) of a given material (either Au, In, Cu, Mn, etc.) into an aluminum tube outside diameter equal to 6.35 mm, alternating flakes with lids covered and discovered of cadmium (3.4 mm of diameter and 0.508 mm of thickness) and separated by lucite pieces of 3 mm of diameter and 25.4 mm in length. After irradiating the flakes for some time, is measured the gamma activity of each of them, using a hyper pure germanium detector of high resolution. Already known gamma activity, proceed to calculate the epi cadmic and sub cadmic flows using a computer program in Fortran language, called Caflu. (Author)

Analisis Pengaruh Display Interior Terhadap Perilaku Pembelian Impulsif Konsumen Indomaret Pontianak

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Ana Fitriana

2016-07-01

Full Text Available Pembelian impulsif adalah kecenderungan membeli produk atau jasa dengan tidak terencana, selanjutnya ketika pembelian sering tidak terencana, maka umumnya konsumen membeli produk atau jasa yang tidak terdaftar dalam daftar belanja. Sejalan dengan tujuan pemasar, pembelian tidak terencana ini berdampak sangat positif bagi pihak perusahaan. Salah satu perilaku konsumen yang sangat penting adalah perilaku belanja impulsif. Penelitian ini bertujuan untuk mengetahui pengaruh display interior pada Indomaret Pontianak terhadap impulsive buying konsumennya. Metode penelitian yang digunakan adalah penelitian kuantitatif. Populasi penelitian ini adalah konsumen Indomaret Pontianak, sebanyak 100 responden dipilih secara accidental sampling sebagai sampel penelitian. Metode pengumpulan data yang digunakan adalah metode pengumpulan data primer dengan teknik pengumpulan data kuesioner. Teknik analisis data yang digunakan adalah uji validitas dan reliabilitas, analisis koefisien determinasi, analisis regresi berganda dan uji hipotesis.Hasil perhitungan data menggunakan SPSS for windows ver 16 menunjukan secara simultan pengaruh display interior terhadap impulsive buying diketahui berpengaruh sebesar 61,31%. Sedangkan 38,69% dipengaruhi oleh faktor lain yang tidak diteliti didalam penelitian ini. Secara parsial tiga variabel bebas yaitu pengadaan barang, pengelompokan barang, dan penyusunan barang dan pencahayaan mempunyai pengaruh signifikan terhadap Impulsive buying.   Kata kunci — Pengadaan barang, Pengelompokan barang, Penyusunan barang dan pencahayaan, Perilaku Pembelian Impulsif

Risk analysis in the chemical industry; Analisis de riesgos en la industria quimica

Energy Technology Data Exchange (ETDEWEB)

Rea Soto, Rogelio; Sandoval Valenzuela, Salvador [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)

2000-07-01

The Instituto de Investigaciones Electricas has a group of risk analysis (GAR), specialized in the most advanced methodologies to apply them in diverse industries of the productive sector, such as the nuclear, the oil and the chemical industries. In this work the integrated methodology that the GAR uses to make risk analysis in the chemical and oil industries is described. These analyses have as an objective to make a meticulous evaluation of the system design, the operation practices, the maintenance and inspection policies and the emergency plans. [Spanish] El Instituto de Investigaciones Electricas cuenta con un grupo de analisis de riesgo (GAR), especializado en las metodologias mas avanzadas para aplicarlas en diversas industrias del sector productivo, como lo son la nuclear, la petrolera y la quimica. En este trabajo se describe la metodologia integrada que el GAR utiliza para realizar analisis de riesgos en las industrias quimica y petrolera. Estos analisis tienen como objetivo realizar una minuciosa evaluacion del diseno del sistema, las practicas de operacion, las politicas de mantenimiento e inspeccion y los planes de emergencia.

Analisis Reduksi Intensitas Cahaya Pada Smartphones’ Screen Protector Dan Dampaknya Pada Mata

Directory of Open Access Journals (Sweden)

Bhekti Kumorowati

2017-04-01

Full Text Available Analisis reduksi intensitas cahaya yang melewati screen protector dan identifikasi kemampuan screen protector sebagai pelindung mata dilakukan dengan mengukur reduksi intensitas cahaya menggunakan luxmeter, kemudian menetapkan fokus bahasan yang mencakup kemampuan cahaya menembus screen protector dan analisis fisis screen protector sebagai pelindung mata. Peran sebagai pelindung mata dikaji melalui pendekatan peristiwa polarisasi yaitu proses terserapnya sebagian arah getar cahaya. Dihasilkan sebagian arah getar cahaya layar smartphone sebelum masuk ke mata akan terserap oleh screen protector sehingga dapat memperlambat terjadinya degenerasi makula. Rekomendasi pemilihan screen protector bergantung pada besarnya koefisien atenuasi (koefisien penyerapan yang dimiliki masing-masing screen protector. Koefisien atenuasi terbesar dimiliki oleh screen protector jenis anti spy.

Physical start up of the Dalat nuclear research reactor with the core configuration having a central neutron trap; Khoi dong vat ly lo phan ung hat nhan Da Lat voi cau hinh vung hoat co bay notron

Energy Technology Data Exchange (ETDEWEB)

Hien, Pham Duy; Huy, Ngo Quang; Long, Vu Hai; Mai, Tran Khanh [Nuclear Research Inst., Da Lat (Viet Nam)

1994-10-01

After the reactor has reached physical criticality with the core configuration exempt from central neutron trap on 1 November 1983, the core configuration with a central neutron trap has been arranged in the reactor and the reactor has reached physical criticality with this core configuration at 17h48 on 18 December 1983. The integral worths of different control rods are determined with accuracy. 2 refs., 24 figs., 18 tabs.

Analisis Termal High Pressure Feedwater Heater di PLTU PT. XYZ

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Maria Ulfa Damayanti

2017-01-01

Full Text Available Abstrak- PT. XYZ mengoperasikan tiga unit Pembangkit Listrik Tenaga Uap (PLTU unit 3, 7 dan 8 berkapasitas 2.030 MegaWatt. Pada PLTU Paiton unit 7 dan 8 terdapat delapan buah feedwater heater yaitu empat buah Low Pressure Water Heater (LPWH, tiga buah High Pressure Water Heater (HPWH, dan sebuah dearator. Pada PLTU Paiton unit 7 dan 8 terdapat kerusakan pada HPWH 6 yang menyebabkan penurunan efisiensi dari siklus secara keseluruhan. Penurunan efisiensi dapat terjadi karena temperatur feedwater sebelum masuk ke boiler terlalu rendah, sehingga kalor yang dibutuhkan oleh boiler untuk memanaskan feedwater meningkat. Oleh karena itu konsumsi batubara akan meningkat dan menyebabkan terjadi kenaikan biaya operasional harian dalam sistem pembangkit. Dari data Divisi Produksi PT. XYZ Unit 7 dan 8 diperoleh spesifikasi HPWH 6, 7, dan 8 dan propertis fluida dalam HPWH 6, 7, dan 8. Data tersebut digunakan sebagai dasar analisis termal yang meliputi performa masing-masing HPH. Tahap selanjutnya dalam analisis termal adalah memvariasikan beban 25%, 50%, 75%, 100%, dan 105%. Tahap terakhir analisis adalah menghitung performa dengan variasi sumbatan (plug 5%, 10%, 15%, dan 20% sesuai dengan variasi beban. Hasil yang didapatkan dari penelitian tugas akhir ini adalah nilai effectiveness tertinggi tercapai pada pembebanan 100% serta menghasilkan pressure drop tertinggi pada pembebanan 105%, nilai effectiveness terbesar serta nilai pressure drop terkecil terjadi pada zona Condensing, serta sumbatan (plugging pada HPH akan menyebabkan penurunan nilai effectiveness dan kenaikan pressure drop sisi tube.

Analisis Kinerja Local Area Network Menggunakan Router.

OpenAIRE

Hutahaean, Yosua

2012-01-01

Perangkat internetworking menawarkan komunikasi di antara segmen Local Area Network (LAN). Ada empat tipe utama perangkat internetworking ini: repeater, bridge, router, dan gateway. Perangkat ini dibedakan atas dasar system lapisan Open System Interconnection (OSI) yang digunakan, berfungsi sebagai media komunikasi dari LAN ke LAN. Pada Tugas Akhir ini penulis tertarik untuk membahas analisis kinerja Local Area Network (LAN) menggunakan Router yang menggunakan sistem antrian M/M/1 dimana j...

Rethinking the economics of centralized spent fuel storage

International Nuclear Information System (INIS)

Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

1991-04-01

The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility with a pre-defined MRS operating scenario. This paper reverses this approach to economic analysis of the MRS by seeking the optimal MRS operating scenario (in terms of the parameters listed above) implied by the economic incentives arising from the relative costs of at-reactor storage and centralized storage. This approach treats an MRS as a possible storage location that will be used according to its economic value in system operation. 5 refs., 5 figs

Nuclear Energy in Central Europe 98, Proceedings

International Nuclear Information System (INIS)

Ravnik, M.; Jencic, I.; Zagar, T.

1998-01-01

Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 63 articles from Slovenia, sorounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Nuclear Methods, Reactor Physics, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation and Nuclear Waste disposal

Multivariate analysis in the frequency mastery applied to the Laguna Verde Central; Analisis multivariable en el dominio de la frecuencia aplicado a la Central Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Castillo D, R.; Ortiz V, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, carretera Nautla-Cardel Km. 42.5, Alto Lucero, Veracruz (Mexico)]. e-mail: rcd@nuclear.inin.mx

2006-07-01

The noise analysis is an auxiliary tool in the detection of abnormal operation conditions of equipment, instruments or systems that affect to the dynamic behavior of the reactor. The spectral density of normalized power has usually been used (NPSD, by its initials in English), to watch over the behavior of some components of the reactor, for example, the jet pumps, the recirculation pumps, valves of flow control in the recirculation knots, etc. The behavior change is determined by individual analysis of the NPSD of the signals of the components in study. An alternative analysis that can allow to obtain major information on the component under surveillance is the multivariate autoregressive analysis (MAR, by its initials in English), which allows to know the relationship that exists among diverse signals of the reactor systems, in the time domain. In the space of the frequency, the relative contribution of power (RPC for their initials in English) it quantifies the influence of the variables of the systems on a variable of interest. The RPC allows, therefore that for a peak shown in the NPSD of a variable, it can be determine the influence from other variables to that frequency of interest. This facilitates, in principle, the pursuit of the important physical parameters during an event, and to study their interrelation. In this work, by way of example of the application of the RPC, two events happened in the Laguna Verde Central are analyzed: the rods blockade alarms by high scale in the monitors of average power, in which it was presents a power peak of 12% of width peak to peak, and the power oscillations event. The main obtained result of the analysis of the control rods blockade alarm event was that it was detected that the power peak observed in the signals of the average power monitors was caused by the movement of the valve of flow control of recirculation of the knot B. In the other oscillation event the results its show the mechanism of the oscillation of

Research reactor spent fuel management in Argentina

International Nuclear Information System (INIS)

Audero, M.A.; Bevilacqua, A.M.; Mehlich, A.M.; Novara, O.

2002-01-01

The research reactor spent fuel (RRSF) management strategy will be presented as well as the interim storage experience. Currently, low-enriched uranium RRSF is in wet interim storage either at reactor site or away from reactor site in a centralized storage facility. High-enriched uranium RRSF from the centralized storage facility has been sent to the USA in the framework of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The strategy for the management of the RRSF could implement the encapsulation for interim dry storage. As an alternative to encapsulation for dry storage some conditioning processes are being studied which include decladding, isotopic dilution, oxidation and immobilization. The immobilized material will be suitable for final disposal. (author)

Analisis Penerimaan PAD Pada Dinas Perikanan dan Peternakan Kabupaten Tebo

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Eko Purnarianto

2016-06-01

Full Text Available Abstract. This study aims to analyze potential, efficiency, effectivity and contribution of PAD admission at Department of Fishery and Animal Husbandry in Tebo Regencyincluding the strategy establishment to increase its revenue.The analysis used is a potential formula, efficiency ratio, effectivity ratio, contributions ratio and SWOT analysis.The results shows that the potential revenue of retribution slaughterhouse (RPH, the potential sales of livestock, and potential sales fishery product are beyond the current target. The efficiency level of retribution slaughterhouse (RPH and sales of fishery product is poor, but the sales of livestock is very efficient. Effectivity level of livestock and fishery product sales are low, whileretribution slaughterhouses(RPH is not effective regarded to its potential  but in the contrary for its target. Contribution of PAD admission of Fishery and Animal Husbandry Department is very low regarded Tebo Regency PAD. The result of SWOT analysis of retribution slaughter house (RPH admission using WO (Weakness-Opportunity strategy, livestock sales using SO (Strength-Oppurtunity strategy, and fishery product sales using ST (strength-threat strategy. Keywords: Retribution SlaughterHouse (RPH, Sales of Fishery, Livestock Sales, SWOT Analysis   Abstrak. Penelitian ini bertujuan untuk menganalisis potensi, efisiensi, efektivitas dan kontribusi penerimaan PAD pada Dinas Perikanan dan Peternakan Kabupaten Teboserta menetapkan strategi untuk peningkatan penerimaan PAD. Analisis yang digunakan adalah rumus potensi, rasio efisiensi, rasio efektivitas, rasio kontribusi dan analisis SWOT.Hasil penelitian menunjukkan bahwa potensi penerimaan retribusi rumah potong hewan (RPH, potensi penjualan hasil peternakan, potensi  penjualan hasil perikanan lebih besar dari target yang telah ditetapkan. Tingkat efisiensi retribusi RPH dan penjualan hasil perikanan tidak efisien, penjualan hasil peternakan sangat efisien. Tingkat

Analisis Spasial Kejadian Filariasi di Kabupaten Demak Jawa Tengah

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Nurjazuli Nurjazuli

2018-04-01

Full Text Available Latar Belakang: Filariasis merupakan salah satu penyakit tular vektor yang kurang mendapatkan perhatian, termasuk kelompok Neglected Tropical Diseases (NTDs. Kabupaten Demak merupakan salah satu wilayah di Propinsi Jawa Tengah  yang merupakan daerah endemis filarisis (mf rate>1%. Kejadian filarisis di daerah ini diduga berkaitan dengan kondisi lingkungan fisik dan biologis (nyamuk yang mempunyai peran penting dalam penyebaran penyakit filarisis. Penelitian ini bertujuan untuk menemukan adanya penderita baru,  mengidentifikasi kondisi lingkungan fisik dan biologi yang berkaitan dengan sebaran filarisis di Kabupaten Demak. Matede: Penelitian ini merupakan penelitian observasional dengan rancangan cross-sectional. Sebanyak 30 kasus filariasis dijadikan indek kasus yang selanjutnya dipilih secara purposif sebanyak 140 yang tinggal di sekitar 30 kasus tersebut untuk dilakukan pengamblan darah jari. Observasi lingkungan dilakukan untuk mengidentifikasi kondisi lingkungan (breeding places dan resting places dari yang diduga sebagai nyamuk vektor filariasis. Penangkapan nyamuk dilakukan di sekitar rumah penderita filariasis. Pengukuran koordinat kasus filariais dilakukan dengan pesawat Geographic Positioning System (GPS. Pemeriksaan darah jadi jari dilakukan di Laboratorium Kesehatan Daerah (LABKESDA Propinsi Jawa Tengah. Sedang bedah nyamuk dilakukan di Balai Penelitian Vektor Penyakit Banjarnegara. Analisis data dlakukan secara deskriptif, analisis spasial dilakukan dengan software ArcGis 9.3. Hasil: Penelitian ini tidak menemukan penderita baru filarisis (mf rate=0%. Sebanyak 129 ekor nyamuk telah dilakukan pembedahan dengan hasil semuanya negatip cacing filaria. Hasil identifikasi nyamuk menemukan spesies nyamuk Culex quinquefasciatus merupakan nyamuk yang dominan (72,86% di lokasi penelitian.Terdapat breeding places (40% berupa genangan air terbuka (SPAL dan resting places (83,3% berupa semak-semak di sekitar rumah penderita. Analisis spasial

Post-Construction Testing of the Elk River, Hallam and Piqua Power Reactor Plants; Essais apres construction des centrales nucleaires d'Elk River, de Hallam et de Piqua; Predehkspluatatsionnoe ispytanie Ehlk-riverskoj, Khehlpemskoj i Pikuaskoj ehnergeticheskikh reaktornykh ustanovok; Ensayos posteriores a la construccion de las centrales nucleoelectricas de Elk River, Hallam y Piqua

Energy Technology Data Exchange (ETDEWEB)

Pursel, C. A. [United States Atomic Energy Commission, Argonne, IL (United States)

1963-10-15

defectos hallados: Reactor de Elk River. Se descubrieron grietas en parte del revestimiento superficial del recipiente del reactor; ello obligo a efectuar una serie de investigaciones y analisis, asi como ciertas reparaciones y modificaciones del recipiente. La insuficiente capacidad de separacion de vapor obligo a sustituir y modificar algunas piezas metalicas en el interior del recipiente del reactor. Central nucleoelectrica de Hallam. Debido al arrastre de helio, hubo que modificar los circuitos secundarios de sodio. La falla de un tubo del intercambiador de calor intermedio (sodio-sodio) obligo a llevar a cabo una serie de analisis para descubrir su causa y extraer y reparar el intercambiador. Central nucleoelectrica de Piqua. Durante la limpieza de las tuberias con agentes quimicos, se dallaron varias valvulas que fue preciso reparar o sustituir. Las fugas en el circuito del refrigerante organico y del vapor secundario provocaron demoras repetidas. Una vez concluidas las reparaciones e introducidas las modificaciones necesarias, se comprobo que las caracteristicas de rendimiento reales de cada uno de los tres reactores se ajustaban estrictamente a las previstas en el proyecto. (author) [Russian] Fakticheskij opyt, nakoplennyj vo vremya predehkspluatatsionnykh ispytanij trekh yadernykh ehnergeticheskikh ustanovok, postroennykh po demonstratsionnoj programme ehnergeticheskikh reaktorov Komissii po atomnoj ehnergii Soedinennykh Shtatov, pozvolyaet sdelat' nekotorye obobshcheniya v otnoshenii ehtoj fazy stroitel'stva i ehkspluatatsii ustanovok. Tri ustanovki, a imenno Ehlk-riverskij reaktor (ERR), Khehllemskaya yadernaya ehnergeticheskaya ustanovka (HNPF) i Pikuaskaya yadernaya ehnergeticheskaya ustanovka (PNPF), predstavlyayut tri razlichnykh tipa reaktorov: reaktor s kipyashej vodoj s estestvennoj tsirkulyatsiej, natrievo-grafitovyj reaktor i reaktor s organicheskim teplonositelem i zamedlitelem sootvetstvenno. Period predehkspluatatsionnykh ispytanij okhvatyvaet vremya

On fusion and fission breeder reactors

International Nuclear Information System (INIS)

Brandt, B.; Schuurman, W.; Klippel, H.Th.

1981-02-01

Fast breeder reactors and fusion reactors are suitable candidates for centralized, long-term energy production, their fuel reserves being practically unlimited. The technology of a durable and economical fusion reactor is still to be developed. Such a development parallel with the fast breeder is valuable by reasons of safety, proliferation, new fuel reserves, and by the very broad potential of the development of the fusion reactor. In order to facilitate a discussion of these aspects, the fusion reactor and the fast breeder reactor were compared in the IIASA-report. Aspects of both reactor systems are compared

The safety of light water reactors

International Nuclear Information System (INIS)

Pershagen, B.

1986-04-01

The book describes the principles and practices of reactor safety as applied to the design, regulation and operation of both pressurized water reactors and boiling water reactors. The central part of the book is devoted to methods and results of safety analysis. Some significant events are described, notably the Three Mile Island accident. The book concludes with a chapter on the PIUS principle of inherent reactor safety as applied to the SECURE type of reactor developed in Sweden. (G.B.)

Reactor power distribution monitor

International Nuclear Information System (INIS)

Sekimizu, Koichi

1980-01-01

Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

An examination of reliability critical items in liquid metal reactors: An analysis by the Centralized Reliability Data Organization (CREDO)

International Nuclear Information System (INIS)

Humphrys, B.L.; Haire, M.J.; Koger, K.H.; Manneschmidt, J.F.; Setoguchi, K.; Nakai, R.; Okubo, Y.

1987-01-01

The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Department of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 21,000 components and approximately 1300 event records. A conservative estimation is that the total component operating hours is approaching 3.5 billion hours. Because data gathering for CREDO concentrates on event (failure) information, the work reported here focuses on the reliability information contained in CREDO and the development of reliability critical items lists. That is, components are ranked in prioritized lists from worst to best performers from a reliability standpoint. For the data contained in the CREDO data base, FFTF and JOYO show reliability growth; EBR-II reveals a slight unreliability growth for those components tracked by CREDO. However, tabulations of events which cause reactor shutdowns decrease with time at each site

Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

International Nuclear Information System (INIS)

Reuscher, J.A.; Pickard, P.S.

1976-01-01

The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

Fast reactor parameter optimization taking into account changes in fuel charge type during reactor operation time

International Nuclear Information System (INIS)

Afrin, B.A.; Rechnov, A.V.; Usynin, G.B.

1987-01-01

The formulation and solution of optimization problem for parameters determining the layout of the central part of sodium cooled power reactor taking into account possible changes in fuel charge type during reactor operation time are performed. The losses under change of fuel composition type for two reactor modifications providing for minimum doubling time for oxide and carbide fuels respectively, are estimated

Interaction of CREDO [Centralized Reliability Data Organization] with the EBR-II [Experimental Breeder Reactor II] PRA [probabilistic risk assessment] development

International Nuclear Information System (INIS)

Smith, M.S.; Ragland, W.A.

1989-01-01

The National Academy of Sciences review of US Department of Energy (DOE) class 1 reactors recommended that the Experimental Breeder Reactor II (EBR-II), operated by Argonne National Laboratory (ANL), develop a level 1 probabilistic risk assessment (PRA) and make provisions for level 2 and level 3 PRAs based on the results of the level 1 PRA. The PRA analysis group at ANL will utilize the Centralized Reliability Data Organization (CREDO) at Oak Ridge National Laboratory to support the PRA data needs. CREDO contains many years of empirical liquid-metal reactor component data from EBR-II. CREDO is a mutual data- and cost-sharing system sponsored by DOE and the Power Reactor and Nuclear Fuels Development Corporation of Japan. CREDO is a component based data system; data are collected on components that are liquid-metal specific, associated with a liquid-metal environment, contained in systems that interface with liquid-metal environments, or are safety related for use in reliability/availability/maintainability (RAM) analyses of advanced reactors. The links between the EBR-II PRA development effort and the CREDO data collection at EBR-II extend beyond the sharing of data. The PRA provides a measure of the relative contribution to risk of the various components. This information can be used to prioritize future CREDO data collection activities at EBR-II and other sites

Perbandingan Penilaian Saham Dengan Metode Analisis Fundamental Dan Analisis Tehknical, Penggorengan Saham, Serta Keputusan Penilaian Saham Jika Hasil Berlawanan Arah Untuk Kedua Metode Analisis Pada Saham Bakrie Group Untuk Periode 2005- 2009

OpenAIRE

Harwaningrum, Miranti

2016-01-01

Beberapa tahun belakangan ini, dunia investasi mengalami peningkatan. Hal ini dapat terlihat dari data rata-rata perdagangan saham yang dimiliki oleh Bapepam. Salah satu jenis instrumen investasi yang sering diminati oleh investor adalah saham. Apabila dibandingkan dengan obligasi, saham memiliki expected return yang lebih tinggi. Namun, saham memiliki resiko yang lebih tinggi bila dibandingkan dengan obligasi. Untuk melakukan penilaian saham ada dua analisis yang dapat dilakukan, yaitu funda...

ANALISIS MODEL PREDIKSI AWAL MUSIM HUJAN DI SULAWESI SELATAN

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Alimatul Rahim

2016-03-01

Full Text Available Model prediksi awal musim hujan merupakan salah satu kunci yang dapat digunakan untuk mengurangi resiko kegagalan panen padi yang disebabkan oleh faktor iklim di provinsi Sulawesi Selatan. Model prediksi awal musim hujan dibangun  dengan menggunakan data curah hujan observasi Sulawesi Selatan dan anomali suhu muka laut di kawasan Pasifik dan perairan Sulawesi. Pada studi ini dilakukan analisis pemilihan stasiun hujan observasi, penentuan awal musim hujan, analisis komponen utama dan pengelompokan, analisis korelasi awal musim hujan terhadap anomali suhu muka laut, pembangunan model untuk prediksi awal musimhujan dan verifikasi model.Hasil analisis awal musim hujan menunjukkan setiap stasiun hujan mempunyai perbedaan awal musim hujan dengan rata-rata jatuh pada Julian Date (JD ke-348 (14 Desember. Berdasarkan hasil analisis PCA dan cluster, diperoleh bahwa di Sulawesi Selatan terbagi menjadi 3 cluster wilayah. Cluster 1 mempunyai pola hujan lokal, sedangkan cluster 2 dan 3 mempunyai pola hujan monsun. Pada peta korelasi antara awal musim hujan di Sulawesi Selatan dan anomali suhu muka laut menunjukkan bahwa terdapat korelasi nyata(r≥0.5 antara kawasan Pasifik dan Laut Sulawesi pada cluster 1 dan 2 pada bulan Juni Juli Agustus September(JJAS. Sedangkan pada cluster 3, korelasi nyata hanya pada bulan Juni di perairan Sulawesi. Model prediksi AMH terbaik, pada cluster 2 terdapat di domain prediktor kawasan pasifik dengan nilai r=0.82, sedangkan pada cluster 1 dan 3, terdapat di domain perairan Sulawesi dengan nilai r=0.78 dan r-0.48. Verifikasi model terpilih pada cluster 3 mempunyai RMSE = 3, sedangkan cluster 1 dan 2, nilai RMSE berturut-turut sebesar 16 dan 29.   Model prediction of rainy season onset is one of the keys to reduce the risk of paddy haverst failure because of climate factor in South Sulawesi province. The model prediction for rainy season onset was build using rainfall data in South Sulawesi and SST anomaly in Pacific Ocean and

Comparative analysis of power conversion cycles optimized for fast reactors of generation IV; Analisis comparativo de ciclos de conversion de potencia optimizados para reactores rapidos de generacion IV

Energy Technology Data Exchange (ETDEWEB)

Perez Pichel, G. D.

2011-07-01

For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

La financial education nella regione Puglia: analisi e prospettive di intervento

OpenAIRE

A. Garzoni; V. Nastasi

2010-01-01

Analisi del contesto e delle principali tematiche di financial education affrontate a livello internazionale e nazionale, valutazione delle opportunità e degli aspetti critici, il progetto pilota nella regione Puglia e le nuove idee di progetto da realizzare

Text Mining Untuk Analisis Sentimen Review Film Menggunakan Algoritma K-Means

Directory of Open Access Journals (Sweden)

Setyo Budi

2017-02-01

Full Text Available Kemudahan manusia didalam menggunakan website mengakibatkan bertambahnya dokumen teks yang berupa pendapat dan informasi. Dalam waktu yang lama dokumen teks akan bertambah besar. Text mining merupakan salah satu teknik yang digunakan untuk menggali kumpulan dokumen text sehingga dapat diambil intisarinya. Ada beberapa algoritma yang di gunakan untuk penggalian dokumen untuk analisis sentimen, salah satunya adalah K-Means. Didalam penelitian ini algoritma yang digunakan adalah K-Means. Hasil penelitian menunjukkan bahwa akurasi K-Means dengan dataset digunakan 300 positif dan 300 negatif  akurasinya 57.83%,  700 dokumen positif dan 700  negatif akurasinya 56.71%%, 1000 dokumen positif dan 1000  negatif akurasinya 50.40%%. Dari hasil pengujian disimpulkan bahwa semakin besar dataset yang digunakan semakin rendah akurasi K-Means.   Kata Kunci : Text Mining, Analisis Sentimen, K-Means, Review Film 

Analisis Nilai Perusahaan pada Implementasi Program Kepemilikan Saham pada Karyawan/Manajemen

Directory of Open Access Journals (Sweden)

Dwitya Aribawa

2016-12-01

  Penelitian ini bertujuan menganalisis economic value added (EVA sebelum dan sesudah implementasi program kepemilikan saham pada karyawan/ manajemen dengan objek penelitian ini adalah perusahaan publik yang menggunakan kebijakan ESOP/MSOP sebagai sarana benefit/incentive berupa pembagian sebagian saham untuk karyawan/ manajemen. Variabel yang digunakan sebagai indikator nilai perusahaan adalah EVA. Nilai EVA dianggap sebagai indikator yang kompleks dan mempertimbangkan faktor resiko (beta dari perusahaan. Perusahaan yang dianalisis adalah perusahaan yang listing di Bursa Efek Indonesia. Terdapat 17 perusahaan yang layak untuk dilakukan analisis berdasarkan kriteria yang ditentukan peneliti. Pengumpulan dan data dianalisis secara pooling, hal ini melihat dari tidak dibedakannya perusahaan berdasarkan industri (multi industri. Paired sample test digunakan untuk menguji hipotesis pada penelitian dan sebelumnya dilakukan uji normalitas data. Hasil analisis bahwa hasil perbandingan rata-rata EVA sebelum dan sesudah implementasi program kepemilikan saham pada karyawan/manajemen terdapat perbedaan yag signifikan.

Undergraduate reactor control experiment

International Nuclear Information System (INIS)

Edwards, R.M.; Power, M.A.; Bryan, M.

1992-01-01

A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

FACTORS INFLUENCING HUMAN RELIABILITY OF HIGH TEMPERATURE GAS COOLED REACTOR OPERATION

Directory of Open Access Journals (Sweden)

Sigit Santoso

2016-10-01

ABSTRAK Peran dan tindakan operator pada reaktor berpendingin gas akan berbeda dengan peran operator pada operasi tipe reaktor lain. Analisis unjuk kerja operator dan faktor yang berpengaruh dapat dilakukan secara komprehensif melalui analisis keandalan manusia(HRA. Melalui HRA dampak dari kesalahan manusia pada sistem maupun cara untuk mengurangi dampak dan frekuensi kesalahan dapat diketahui. Makalah membahas faktor yang berpengaruh pada tindakan operator, yaitu pada kejadian kecelakaan pendingin reaktor gas bersuhu tinggi-HTGR. Analisis untuk kualifikasi faktor pembentuk kinerja(PSF dilakukan berdasarkan kurva keandalan fungsi waktu, dan metode keandalan manusia yang dikembangkan berdasar pada aspek kognitif yaitu Cognitive Reliability and Error Analysis Method (CREAM. Hasil analisis berdasar kurva keandalan fungsi waktu menunjukkan komponen waktu berkontribusi positif pada peningkatan keandalan operator (PSF<1 pada kondisi semua fitur keselamatan berfungsi sesuai rancangan. Sedangkan pada metoda analisis dengan pendekatan kognitif CREAM diketahui selain faktor ketersediaan waktu, faktor pelatihan dan rancangan HMI juga berkontribusi meningkatkan keandalan operator. Faktor pembentuk kinerja keseluruhan diketahui sebesar 0,25 dengan faktor kontribusi positif dominan atau berpengaruh pada penurunan kesalahan manusia adalah ketersediaan waktu (PSF=0,01, dan faktor kontribusi negatif dominan adalah prosedur dan siklus kerja (PSF=5. Nilai PSF tersebut sebagai faktor pengali dalam perhitungan probabilitas kesalahan manusia. Analisis faktor pembentuk kinerja perlu dikembangkan pada skenario kejadian lain untuk selanjutnya digunakan untuk perhitungan dan analisis keandalan manusia yang komprehensif dan perancangan sistem interaksi manusia mesin di ruang kendali. Kata kunci: PSF, HTGR, operator, ruang kendali, keandalan manusia

PENGGUNAAN METODE STRUCTURAL EQUATION MODELLING UNTUK ANALISIS FAKTOR YANG MEMPENGARUHI MOTIVASI BELAJAR MAHASISWA FIP UMJ

Directory of Open Access Journals (Sweden)

Ririn Widiyasari

2018-02-01

Full Text Available Tujuan yang ingin dicapai dalam penelitian ini adalah mengetahui faktor apa saja  yang mempengaruhi motivasi belajar mahasiswa, apakah terdapat pengaruh yang signifikan antara cara belajar, fasilitas belajar dan lingkungan belajar terhadap motivasi belajar mahasiswa, serta faktor mana yang paling berpengaruh terhadap motivasi belajar mahasiswa. Jumlah sampel dalam penelitian ini adalah 192 mahasiswa (FIP UMJ angkatan tahun 2013-2015 yang aktif mengikuti perkuliahan. Metode penelitian yang dilakukan adalah metode kuantitatif survey. Metode pengambilan data menggunakan  kuesioner dengan skala likert. Metode analisis data yang digunakan adalah analisis deskriptif, dan analisis  Structural Equation Modeling (SEM berbantuan program LISREL 8.3. Uji hipotesis yang digunakan dalam penelitian ini adalah uji Chi-square dan uji t. Hasil penelitian menunjukkan bahwa variabel cara belajar memiliki kontribusi yang paling besar, selanjutnya variabel kedua yang berkontribusi meningkatkan motivasi belajar adalah lingkungan belajar dan terakhir fasilitas belajar memberikan pengaruh yang paling kecil terhadap motivasi belajar. Jadi, variabel laten cara belajar dan lingkungan belajar berpengaruh positif terhadap motivasi belajar dan fasilitas belajar berpengaruh negatif terhadap motivasi belajar.

Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

International Nuclear Information System (INIS)

Wittenbrock, N.G.

1982-01-01

Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte I

Energy Technology Data Exchange (ETDEWEB)

Caro, R; Ahnert, C; Naudin, A E; Martinez Fanegas, R; Minguez, E; Rovira, A

1976-07-01

In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

Neutronics and thermohydraulics of the reactor C.E.N.E. Part II; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte II

Energy Technology Data Exchange (ETDEWEB)

Caro, R

1976-07-01

In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

Determination of the energy spectrum of the neutrons in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor Triga Mark III

Energy Technology Data Exchange (ETDEWEB)

Parra M, M. A.

2014-07-01

This thesis presents the neutron spectrum measurements inside the core of the TRIGA Mark III reactor at 1 MW power in steady-state, with the bridge placed in the center of the swimming pool, using several metallic threshold foils. The activation detectors are inserted in the Central Thimble of the reactor core, all the foils are irradiated in the same position and irradiation conditions (one by one). The threshold detectors are made of different materials such as: Au{sup 197}, Ni{sup 58}, In{sup 115}, Mg{sup 24}, Al{sup 27}, Fe{sup 58}, Co{sup 59} and Cu{sup 63}, they were selected to cover the full range the energies (10{sup -10} to 20 MeV) of the neutron spectrum in the reactor core. After the irradiation, the activation detectors were measured by means of spectrometry gamma, using a high resolution counting system with a hyper pure Germanium crystal, in order to obtain the saturation activity per target nuclide. The saturation activity is one of the main input data together with the initial spectrum, for the computational code SANDBP (hungarian version of the code SAND-II), which through an iterative adjustment, gives the calculated spectrum. The different saturation activities are necessary for the unfolding method, used by the computational code SANDBP. This research work is very important, since the knowledge of the energetic and spatial distribution of the neutron flux in the irradiation facilities, allows to characterize properly the irradiation facilities, just like, to estimate with a good precision various physics parameters of the reactor such as: neutron fluxes (thermal, intermediate and fast), neutronic dose, neutron activation analysis (NAA), spectral indices (cadmium ratio), buckling, fuel burnup, safety parameters (reactivity, temperature distribution, peak factors). In addition, the knowledge of the already mentioned parameters can give a best use of reactor, optimizing the irradiations requested by the users for their production process or

Analisis de la microbiota en suelos cultivados del Altiplano central

OpenAIRE

Sivila, R.; Hervé, Dominique

2001-01-01

Se estudio la poblacion microbina en una rotacion de cultivos con descanso, comun en el Altiplano Central boliviano. Se determino la presencia y densidad de cuatro grupos taxonomicos de microorganismos: bacterias; hongos, actinomicetos y esporas de las micorrizas arbusculares en el suelo rizosferico de cuatro cultivos de la rotacion (papa, quinua, cebada y avena); en las principales especies silvestres perennes (#Stipa ichu, Festuca dolichophylla, Baccharis incarum$) que colonizan las parcela...

ANALISIS IMPOR BERAS DI INDONESIA

Directory of Open Access Journals (Sweden)

Ratih Kumala Sari

2014-10-01

Full Text Available Abstrak ___________________________________________________________________ Salah satu kebijakan pemerintah untuk memenuhi kebutuhan beras yaitu dengan menggenjot produksi beras dalam negeri. Namun dengan semakin meningkatnya jumlah penduduk akan meningkatkan permintaan terhadap beras dan upaya peningkatan produktivitas dalam negeri tidak dapat memenuhi kebutuhan beras dalam negeri. Sehingga untuk menutupi kekurangan tersebut pemerintah mengambil keputusan untuk melakukan impor beras dari negara lain. Akan tetapi pada kenyataannya impor beras dilakukan ketika data statistik menunjukkan bahwa Indonesia sedang mengalami surplus beras. Penelitian ini bertujuan untuk mengetahui faktor-faktor apa saja yang mempengaruhi impor beras di Indonesia. Metode analisis yang digunakan adalah analisis regresi linier berganda dengan model Error Correction Model (ECM. Berdasarkan hasil penelitian disimpulkan bahwa secara parsial maupun secara bersama-sama produksi beras, konsumsi beras, harga beras dalam negeri dan nilai tukar rupiah terhadap dollar AS berpengaruh dan signifikan terhadap impor beras di Indonesia. Abstract ___________________________________________________________________ One of the government’s policy to fulfill the need of rice is to boost the domestic production. However, by increasing the population, the demand of rice will also increase and the effort of increasing the domestic productivity cannot supply domestic rice need. So, to cover the shortage the government make decision to import rice from other countries. Yet, in fact importing rice is occurred when the statistical data showed that the supply of rice in Indonesia is surplus. The purpose of this research is necessary to study the factors which influence the import of rice in Indonesia. The analysis method used is multiple linear regression analysis model with Error Correction Model (ECM. Based on the research proven that partially or jointly the production, the consumption, the

ANALISIS LITERASI EKONOMI

Directory of Open Access Journals (Sweden)

Peter Garlans Sina

2012-10-01

Full Text Available Abstract: Analysis of Economic Literacy. The aim of this research is as an effort to increase economic literacy for individuals and households who want to achieve prosperity. Therefore, the obligation of improving the economic literacy needs to be done in a well-planned manner and come from the strong intention to learn in order to improve the economic literacy. It could have an effect on the assets accumulation, a better debt management, as a protection, as well as to increase savings and managing spending intelligently.   Keyword: economic literacy, asset, debt, protection, saving, spending   Abstrak: Analisis Literasi Ekonomi. Tulisan ini bertujuan sebagai upaya meningkatkan literasi ekonomi bagi individu maupun rumah tangga yang menginginkan mencapai kesejahteraan. Oleh karena itu, kewajiban meningkatkan literasi ekonomi perlu dilakukan secara terencana dan diawali dari niat untuk belajar meningkatkan literasi ekonomi karena dapat berefek pada akumulasi aset, pengelolaan utang yang tepat, proteksi, meningkatkan tabungan dan cerdas mengelola pengeluaran.   Kata kunci: literasi ekonomi, aset, utang, proteksi, menabung, pengeluaran

The fast breeder reactor

International Nuclear Information System (INIS)

Davis, D.A.; Baker, M.A.W.; Hall, R.S.

1990-01-01

Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

International Nuclear Information System (INIS)

Wati, Nurokhim

2008-01-01

Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

A computer control system for a research reactor

International Nuclear Information System (INIS)

Crawford, K.C.; Sandquist, G.M.

1987-01-01

Most reactor applications until now, have not required computer control of core output. Commercial reactors are generally operated at a constant power output to provide baseline power. However, if commercial reactor cores are to become load following over a wide range, then centralized digital computer control is required to make the entire facility respond as a single unit to continual changes in power demand. Navy and research reactors are much smaller and simpler and are operated at constant power levels as required, without concern for the number of operators required to operate the facility. For navy reactors, centralized digital computer control may provide space savings and reduced personnel requirements. Computer control offers research reactors versatility to efficiently change a system to develop new ideas. The operation of any reactor facility would be enhanced by a controller that does not panic and is continually monitoring all facility parameters. Eventually very sophisticated computer control systems may be developed which will sense operational problems, diagnose the problem, and depending on the severity of the problem, immediately activate safety systems or consult with operators before taking action

Analisis Safety System dan Manajemen Risiko pada Steam Boiler PLTU di Unit 5 Pembangkitan Paiton, PT. YTL

Directory of Open Access Journals (Sweden)

Luluk Kristianingsih

2013-09-01

Full Text Available Pembangkit listrik tenaga uap (PLTU merupakan pembangkit listrik yang banyak digunakan di Indonesia. Salah satu bagian dari sistem PLTU yang memiliki risiko bahaya tinggi adalah boiler, oleh karena itu diperlukan adanya analisis bahaya dan safety system sebagai langkah pencegahan bahaya pada boiler. Analisis bahaya dalam penelitian ini dilakukan menggunakan metode HAZOP. Node yang dipakai adalah economizer, steam drum, superheater, dan reheater yang merupakan komponen utama penyusun boiler. Guide word dan deviasi ditentukan berdasarkan control chart yang dibentuk oleh data proses masing-masing komponen selama bulan Maret 2013. Estimasi likelihood dilakukan berdasarkan data maintenance dari work order PT YTL selama 5 tahun, sedangkan estimasi consequences dilakukan berdasarkan kriteria risiko yang ditimbulkan serta berdasarkan control chart. Hasil perkalian likelihood dan consequences dengan risk matrix menghasilkan kriteria risiko dari komponen. Berdasarkan hasil analisis, diperoleh hasil bahwa komponen yang memiliki risiko bahaya paling besar adalah level transmitter steam drum dengan deviasi berupa less level, yaitu dengan kriteria likelihood adalah A dan consequences 4, sehingga risiko bernilai extreme. Selain itu, risiko extreme juga terdapat pada pressure transmitter outlet superheater, dengan likelihood B dan consequences 4. Untuk menurunkan risiko, maka dilakukan perawatan dan kalibrasi secara rutin, serta penambahan redundant transmitter. Bahaya paling besar pada seluruh node adalah adanya kebakaran. Oleh karena itu, dilakukan analisis emergency response plan untuk kebakaran yang mencakup peta evakuasi, tugas dan tanggungjawab tiap personel, langkah pencegahan, serta langkah penanganan.

MCTP, a code for the thermo-mechanical analysis of a fuel rod of BWR type reactors (Neutron part); MCTP, un codigo para el analisis termo-mecanico de una barra combustible de reactores tipo BWR (Parte Neutronica)

Energy Technology Data Exchange (ETDEWEB)

Hernandez L, H; Ortiz V, J [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2003-07-01

In the National Institute of Nuclear Research of Mexico a code for the thermo-mechanical analysis of the fuel rods of the BWR type reactors of the Nucleo electric Central of Laguna Verde is developed. The code solves the diffusion equation in cylindrical coordinates with several energy groups. The code, likewise, calculates the temperature distribution and power distribution in those fuel rods. The code is denominated Multi groups With Temperatures and Power (MCTP). In the code, the energy with which the fission neutrons are emitted it is divided in six groups. They are also considered the produced perturbations by the changes in the temperatures of the materials that constitute the fuel rods, the content of fission products, the uranium consumption and in its case the gadolinium, as well as the plutonium production. In this work there are present preliminary results obtained with the code, using data of operation of the Nucleo electric Central of Laguna Verde. (Author)

The advanced MAPLE reactor concept

International Nuclear Information System (INIS)

Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

1989-01-01

High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D 2 O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10 19 n·s -1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable

Physical Characteristics of the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Ngo Quang Huy

1994-10-01

The operation of the TRIGA MARK II reactor of nominal power 250 KW has been stopped as all the fuel elements have been dismounted and taken away in 1968. The reconstruction of the reactor was accomplished with Russian technological assistance after 1975. The nominal power of the reconstructed reactor is of 500 KW. The recent Dalat reactor is unique of its kind in the world: Russian-designed core combined with left-over infrastructure of the American-made TRIGA II. The reactor was loaded in November 1983. It has reached physical criticality on 1/11/1983 (without central neutron trap) and on 18/12/1983 (with central neutron trap). The power start up occurred in February 1984 and from 20/3/1984 the reactor began to be operated at the nominal power 500 KW. The selected reports included in the proceedings reflect the start up procedures and numerous results obtained in the Dalat Nuclear Research Institute and the Centre of Nuclear Techniques on the determination of different physical characteristics of the reactor. These characteristics are of the first importance for the safe operation of the Dalat reactor

ANALISIS PENGARUH KONSUMSI ROKOK DENGAN KEMISKINAN DI PROVINSI JAWA TENGAH

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Agnes Marisca Dian Sari

2017-06-01

Full Text Available Tujuan penelitian ini adalah untuk mengetahui pengaruh kemiskinan dengan konsumsi rokok di Jawa Tengah tahun 2013 dan mengetahui pengaruh pajak rokok dengan konsumsi rokok di Jawa Tengah tahun 2013. Jenis data yang digunakan adalah data sekunder. Metode analisis yang digunakan ialah regresi Ordinary Least Square (OLS dengan data cross section tahun 2013 di Provinsi Jawa Tengah dengan 35 Kabupaten/Kota. Hasil penelitian ini adalah ketika Garis kemiskinan naik maka akan menaikan konsumsi rokok. Variabel Garis kemiskinan signifikan dan positif terhadap konsumsi rokok di Jawa Tengah tahun 2013.Variabel pajak rokok bernilai positif namun tidak signifikan. Variabel Kemiskinan dan pajak rokok mampu menjelaskan tingkat konsumsi rokok sebesar 0.1263% dan sisanya dijelaskan oleh variabel lain. F-statistik sebesar 2,31. F-tabel sebesar 1,37, dan t-tabel sebesar 2,034.Hasil penelitian dapat disimpulkan adanya pengaruh antara konsumsi rokok dengan kemiskinan di Jawa Tengah tahun 2013. Ketika konsumsi rokok di Jawa Tengah naik maka meningkatkan kemiskinan di Jawa Tengah pada Tahun 2013 dan pengaruh antara konsumsi rokok dan pajak rokok di Jawa Tengah pada tahun 2013 tidak signifikan tapi bernilai positif. Artinya kebijakan pajak di Jawa Tengah belum mampu untuk mengurangi konsumsi rokok di Jawa Tengah pada tahun 2013. Meskipun sudah ada pajak rokok namun konsumsi rokok tetap terus meningkat. The aims of this research were to find out the effects of poverty on cigarette consumption in Central Java in 2013 and to recognize the effects of tax cigarette on cigarette consumption in Central Java in 2013. The type of the data used was secondary data. The analysis method used was the regression of Ordinary Least Square (OLS with the cross section data of 2013 in 35 Districts of Central Java Province.The research results show that when the Poverty Line increases, it increases cigarette consumption. The variable on Poverty Line has effect on cigarette consumption in

Method of constructing lower dry well access tunnel for nuclear reactor container

International Nuclear Information System (INIS)

Kume, Tadashi; Furukawa, Hedeyasu.

1993-01-01

The method of the present invention facilitates construction of a lower dry well access tunnel for a nuclear reactor container. The lower dry well access tunnel is constructed across the reactor container and the reactor main body foundation. In this case, the lower dry well access tunnel is divided into three sections, i.e., axial end portions and a central portion. At first, each of the end portions is attached to the walls of the reactor container and the reactor main body foundation respectively. Subsequently, the central portion is attached to each of the end portions. An adjusting margin is previously provided to the central portion upon manufacturing each of the sections for adjusting deviation from a nominal size upon construction. In such a construction method, it is possible to eliminate interference accident during construction between the end portions of the lower dry well access tunnel and the reactor container and the reactor main body foundation, to facilitate the construction. Further, this facilitates the fabricating operation for dimensional alignment between the lower dry well access tunnel, and the reactor container and the reactor main body foundation. (I.S.)

Un approccio innovativo per l’analisi quantitativa delle superfici di frattura a fatica nelle ghise sferoidali mediante elaborazione di immagini

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O. Di Bartolomeo

2008-07-01

Full Text Available Le osservazioni al microscopio elettronico a scansione (SEM delle superfici di frattura ottenute a seguito di rotture per fatica consentono di evidenziare alcuni meccanismi di avanzamento che dipendono dal materiale e dalla modalità di applicazione delle sollecitazioni. L’introduzione di moderne tecniche di analisi di immagine assistite al calcolatore permette di elaborare un numero di informazioni elevato che consente di porre in relazione le caratteristiche morfologiche locali con il comportamento meccanico macroscopico del materiale.In questo lavoro è stata implementata una tecnica innovativa di analisi di immagine basata sull’analisi della tessitura, valutando l’influenza delle condizioni di applicazione della sollecitazione (ΔK applicato sulla evoluzione del clivaggio rilevato sulle superfici di frattura a fatica di una ghisa sferoidale ferrito-perlitica.

Analisis Rugi Daya Pada Penyulang Bangli Dengan Beroperasinya PLTS Kayubihi

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I GN Dion Adiputra

2015-06-01

Full Text Available Analisis rugi daya pada Penyulang Bangli dilakukan untuk mengetahui perbanding an rugi daya pada jaringan distribusi setelah penempatan pembangkit tersebar jenis PLTS berkapasitas 1 MWp. Lokasi penempatan PLTS ditentukan berdasarkan analisis sensitivitas bus. Nilai sensitivitas bus(?didapat dengan cara membandingkan nilai rugi daya pada sistem dengan total beban yang terhubung pada bus. Penelitian ini menggunakan simulasi aliran daya dengan metode aliran daya Newton-Raphson. Hasil penelitian menunjukkan bus TK 0041 memiliki sensitivitas terbesar dengan nilai ?= 0,178. Dari hasil simulasi aliran daya, penempatan PLTS 1MWp pada lokasi alternatif 1 menghasilkan rugi daya minimum pada Penyulang Bangli yaitu 103,1 kW atau 3,3% dari total suplai daya 3071 kW. Pemasangan PLTS dapat menurunkan rugi daya pada Penyulang Bangli sebesar 57 kW dari total rugi daya pada kondisi tanpa PLTS yaitu 160,1 kW. Bila dibandingkan dengan kondisi eksisting, penem patan PLTS pada lokasi alternatif 1 memiliki selisih rugi daya 7,3 kW lebih kecil dari total rugi daya yang dihasilkan kondisi eksisting sebesar 110,4kW.

ANALISIS TINGKAT KAPABILITAS SISTEM INFORMASI RUMAH SAKIT BERDASARKAN COBIT 5 (MEA01 PADA RSUD TUGUREJO SEMARANG

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Ariel Bagus Nugroho

2015-11-01

Full Text Available RSUD Tugurejo Semarang merupakan Rumah Sakit kelas B milik pemerintah Provinsi Jawa Tengah yang menyediakan pelayanan jasa untuk masyarakat. Dalam manajemen pengolahan data, RSUD Tugurejo Semarang telah menggunakan sistem informasi rumah sakit. Untuk mengetahui apakah sistem informasi telah berjalan seperti yang diharapkan, maka perlu dilakukan analisis tatakelola teknologi informasi. Pada penelitian ini analisis tatakelola teknologi informasi berfokus pada proses pengawasan, evaluasi dan penilaian kinerja, dan kesesuaian kinerja teknologi informasi, yaitu domain MEA01 pada framework COBIT 5.Tujuan penelitian ini untuk mengetahui tingkat kapabilitas dan strategi perbaikan untuk proses pengawasan, evaluasi dan penilaian kinerja dan kesesuaian TI. Metode pengumpulan  data penelitian ini dengan menggunakan studi dokumen, kuesioner dan wawancara kemudian dianalisis tingkat kapabilitas dan kesenjangan. Tingkat kapabilitas yang didapat dari hasil penelitian yaitu berada level 2 (managed. Untuk menaikkan tingkat kapabilitas pada level 3 maka maka perlu dilakukan secara bertahap strategi perbaikan pada PA 2.1, PA2.2, PA 3.1, dan 3.2. Kata kunci: Analisis Tata Kelola TI, COBIT 5, MEA01, Tingkat Kapabilitas, Rumah Sakit.

KONDISI CURAH HUJAN PADA KEJADIAN BANJIR JAKARTA DAN ANALISIS KONDISI UDARA ATAS WILAYAH JAKARTA BULAN JANUARI – FEBRUARI 2013

OpenAIRE

Syaifullah, M. Djazim

2018-01-01

IntisariKondisi curah hujan di wilayah Jakarta pada kejadian banjir besar tanggal 17 Januari 2013 telah dianalisis yang dihubungkan dengan kondisi atmosfer pada selang waktu tersebut. Data curah hujan menggunakan data TRMM sedangkan analisis kondisi atmosfer menggunakan data rawinsonde. Hasil analisis menunjukkan bahwa puncak kejadian banjir Jakarta musim hujan tahun 2013 terjadi pada tanggal 17 Januari 2013 disebabkan oleh faktor lokal yang sangat kuat ditambah dengan faktor global yang mend...

Preliminary design of a tandem mirror reactor

International Nuclear Information System (INIS)

Strohmayer, J.N.

1984-04-01

The purpose of this thesis is to examine the TARA mirror experiment as a possible tandem mirror reactor configuration. This is a preliminary study to size the coil structure based on using the smallest end cell axial length that physics and engineering allow, zeroing the central cell parallel currents and having interchange stability. The input powers are estimated for the final reactor design so a Q value may be estimated. The Q value is defined as the fusion power divided by the total injected power absorbed by the plasma. A computer study was performed on the effect of the transition size, the transition vertical spacing and transition current. These parameters affect the central cell parallel currents, the recircularization of the flux tube and the ratio of central cell beta to anchor beta needed for marginal stability. Two designs were identified. The first uses 100 keV and 13 keV neutral beams to pump the ions that trap in the thermal barrier. The Q value of this reactor is 11.3. The second reactor uses a pump beam at 40 keV. This energy is chosen because there is a resonance for the charge exchange cross section between D 0 and He 2+ at this energy, thus the alpha ash will be pumped along with the deuterium and tritium. The Q value of this reactor is 11.6

Analisis Sikap Konsumen terhadap Produk Fashion Lokal dan Impor

OpenAIRE

Setiawan, Evelyn

2014-01-01

Abstrak: Analisis Sikap Konsumen Terhadap Produk Fashion Lokal dan Impor. Penelitian ini bertujuan untuk menganalisis sikap konsumen terhadap produk fashion lokal dan impor yang akan berpengaruh terhadap keputusan konsumsi. Sampel yang akan digunakan dalam penelitian ini adalah 1.000 mahasiswa dari 10 perguruan tinggi swasta terbesar di Surabaya. Pengambilan data dilakukan dengan metode kuesioner. Hasil pengujian statistik menunjukkan bahwa sebagian besar mahasiswa di Surabaya merasa bangga d...

Uso de Analisis de Covarianza (ANCOVA en investigacion cientifica.

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Badii, M.H.

2008-01-01

Full Text Available The basics of the ANalisis of COVAriance (ANCOVA are given. The objectives and the application of ANCOVA are laid out. Techniques for the estimation of contrasts and for the control and reduction of the degree of error are discussed. The application of a simple ANCOVA using real data is highlighted. The application of this technique in fixing the auxiliary variable in experimentation is emphasized.

THERMOS, district central heating nuclear reactors

International Nuclear Information System (INIS)

Patarin, L.

1981-02-01

In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

PEMODELAN TERAS UNTUK ANALISIS PERHITUNGAN KONSTANTA MULTIPLIKASI REAKTOR HTR-PROTEUS

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Zuhair Zuhair

2015-04-01

Full Text Available PTRKN sebagai salah satu unit kerja di BATAN dengan tugas pokok dan fungsi yang berkaitan erat dengan teknologi reaktor dan keselamatan nuklir, menaruh perhatian khusus pada konsep reaktor pebble bed. Dalam makalah ini pemodelan reaktor pebble bed HTR-PROTEUS dilakukan dengan program transport Monte Carlo MCNP5. Partikel bahan bakar berlapis TRISO dimodelkan secara detail dan eksak dimana distribusi acak partikel ini dalam bola bahan bakar didekati menggunakan array teratur kisi SC dengan fraksi packing 5,76% tanpa zona eksklusif. Model teras pebble bed didekati dengan memanfaatkan kisi teratur dari bola yang disusun sebagai kisi BCC berdasarkan sel berulang yang digenerasi dari sejumlah sel satuan. Hasil perhitungan MCNP5 memperlihatkan kesesuaian yang sangat baik dengan eksperimen, walaupun teras HTR-PROTEUS diprediksi lebih reaktif daripada pengukuran, khususnya di teras 4.2 dan 4.3. Pustaka ENDF/B-VI menunjukkan konsistensi dengan estimasi keff paling akurat dibandingkan pustaka ENDF/B-V, terutama ENDF/B-VI (66c. Deviasi estimasi keff yang dihitung dengan eksperimen dikaitkan sebagai konsekuensi dari komposisi reflektor grafit yang dispesifikasikan. Komparasi yang dibuat memperlihatkan bahwa MCNP5 menghasilkan keff teras HTR-PROTEUS lebih presisi daripada hasil dari MCNP4B dan MCNPBALL. Hasil ini menyimpulkan bahwa, sukses metodologi pemodelan ini menjustifikasi aplikasi MCNP5 untuk analisis reaktor pebble bed lainnya. Kata kunci: pemodelan teras HTR-PROTEUS, konstanta multiplikasi, MCNP5   PTRKN as a working unit in BATAN whose main duties and functions are related to reactor technology and nuclear safety, consern attention to pebble bed reactor concept. In this paper modeling of HTR-PROTEUS pebble bed reactor was done using Monte Carlo transport code MCNP5. The TRISO coated fuel particle is modeled in detailed and exact manner where random distributions of these particles in fuel pebble is approximated by using regular array of SC lattice

ANALISIS RELEVANSI LULUSAN PERGURUAN TINGGI DENGAN DUNIA KERJA

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Ali Muhson

2012-04-01

Full Text Available Abstract: A Relevance Analysis of University Graduates with World of Work. Education should be oriented to the competencies required by the workforce as a percentage of unemployment among the educated increase continuously. This study aims to examine the relevance of YSU Economic Education graduates. The study only focuses on the type of work and subjects taught. The subject of this study is the alumni of Economic Education Study Program. Sampling technique used is snowball sampling. Data collection technique using questionnaires and documentation while the technique of data analysis using descriptive analysis. The result suggests that the majority of the graduates find their first job as private a teacher, a private employee and a tutor, while current job of the most graduates are private teacher, private employee, and civil servant (teacher. The data shows that more than 50 percent of the graduates work in the education area. This implies that the relevance level based on the type of work is categorized as sufficient. Majority of the graduates teaches social science, economic, and entrepreneurship, hence it can be concluded that the relevance level based on the subjects taught is highly relevant.   Keyword: relevance of graduates, type of work, unemployment, employment     Abstrak: Analisis Relevansi Lulusan Perguruan Tinggi dengan Dunia Kerja. Pendidikan harus berorientasi pada kompetensi yang dibutuhkan oleh dunia kerja karena persentase penganggur di kalangan terdidik terus meningkat. Penelitian ini bertujuan untuk mengkaji tingkat relevansi (kesesuaian lulusan Pendidikan Ekonomi UNY. Kajian hanya diarahkan pada jenis pekerjaan dan mata pelajaran yang diampu. Penelitian ini mengambil subjek alumni Prodi Pendidikan Ekonomi dari berbagai angkatan. Teknik sampling yang digunakan adalah snowball sampling. Teknik pengumpulan data menggunakan angket dan dokumentasi sedangkan teknik analisis data menggunakan analisis deskriptif. Penelitian ini

A conceptual design of the International Thermonuclear Experimental Reactor for the Central Solenoid

International Nuclear Information System (INIS)

Heim, J.R.; Parker, J.M.

1990-01-01

Conceptual design of the International Thermonuclear Experimental Reactor (ITER) superconducting magnet system is nearing completion by the ITER Design Team, and one of the Central Solenoid (CS) designs is presented. The CS part of this magnet system will be a vertical stack of eight modules, approximately 16 m high, each having a approximate dimensions of: 4.1-m o.d., 2.8-m i.d., 1.9-m h. The peak field at the bore is approximately 13.5 T. Cable-in-conduit conductor with Nb 3 Sn composite wire will be used to wind the coils. The overall coil fabrication will use the insulate-wind-react-impregnate method. Coil modules will be fabricated using double-pancake coils with all splice joints located in the low-field region on the outside of the coils. All coils will be structurally graded with high-strength steel reinforcement which is co-wound with the conductor. We describe details of the CS coil design and analysis

ANALISIS KONTRIBUSI PAJAK HOTEL TERHADAP PENDAPATAN ASLI DAERAH KABUPATEN NUNUKAN

OpenAIRE

-, MULIATI

2014-01-01

2014 Analisis Kontribusi Pajak Hotel terhadap Pendapatan Asli Daerah Kabupaten Nunukan Analysis of The Contributions Tax on Hotel Againts Regional Renenue Nunukan District Muliati Haerial M. Christian Mangiwa Penelitian ini bertujuan untuk mengetahui seberapa besar kontribusi pajak hotel terhadap pendapatan asli daerah, mengetahui sistem pengawasan, dan potensi yang ada untuk meningkatkan pajak hotel, mengetahui sistem dan prosedur...

Numerical calculation procedure for criticality parameters of the two-zone reflected reactor with flat central zone

International Nuclear Information System (INIS)

Bosevski, T.; Strugar, P.

1966-10-01

In determining the criticality parameters of a two-zone reactor with flat central zone one encounters a numerical problem requiring the solution of a system of two non-linear equations. To solve them the Newton method, which proved convenient, was used n this work. By comparing our results with those reported one obtains about 5% smaller values of both the radius of the flat zone and of the radial buckling of the outer zone. This discrepancy probably results from some approximations used in solving the same system of equations used in solving the same system of equations where the procedure form was applied, whereas the calculation time is by one order of magnitude smaller

Centralized Reliability Data Organization (CREDO) assessment of critical component unavailability in liquid metal reactors

International Nuclear Information System (INIS)

Koger, K.H.; Haire, M.J.; Humphrys, B.L.; Manneschmidt, J.F.; Setoguchi, K.; Nakai, R.

1988-01-01

The Centralized Reliability Data Organization (CREDO) is the largest repository of liquid metal reactor (LMR) component reliability data in the world. It is jointly sponsored by the US Dept. of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The CREDO data base contains information on a population of more than 20,000 components and approximately 1500 event records. A conservative estimation is that the total component operating hours is approaching 2.2 billion hours. The work reported here focuses on the availability information contained in CREDO and the development of availability critical items lists. That is, individual components are ranked in prioritized lists from worst to best performers from an availability standpoint. Availability as used here is an inherent characteristics of the component and is not necessarily related to plant operability. A major observation is that a few components have a much higher unavailability factor than the average. The top fifteen components contribute 93%, 77%, and 87% of the total system unavailability for EBR-II, FFTF, and JOYO respectively. Critical components common to all three sites are mechanical pumps and electromagnetic pumps. Application of resources to these components with the highest unavailability will have the greatest effect on overall availability. All three sites demonstrate that low maintainability (i.e., long repair times), rather than unreliability (i.e., high failure rates), are the main contributors, by about a two-to-one margin, to liquid metal system unavailability

Rethinking the economics of centralized spent fuel storage

International Nuclear Information System (INIS)

Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

1991-01-01

The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility (in terms of avoided utility costs) with a pre-defined MRS operating scenario (e.g., spent fuel acceptance schedule, storage capacity, and typical storage cycle). While these analyses provided some insight into the economic justification for an MRS facility, even the most favorable scenarios resulted in net costs of hundreds of millions of dollars when evaluated on a discounted cash flow basis

Computerized reactor power regulation with logarithmic controller

International Nuclear Information System (INIS)

Gossanyi, A.; Vegh, E.

1982-11-01

A computerized reactor control system has been operating at a 5 MW WWR-SM research reactor in the Central Research Institute for Physics, Budapest, for some years. This paper describes the power controller used in the SPC operating mode of the system, which operates in a 5-decade wide power range with +-0.5% accuracy. The structure of the controller easily limits the minimal reactor period and produces a reactor transient with constant period if the power demand changes. (author)

Determination of the neutrons energy spectrum in the central thimble of the reactor core TRIGA Mark III; Determinacion del espectro de energia de los neutrones en el dedal central del nucleo del reactor TRIGA Mark III

Energy Technology Data Exchange (ETDEWEB)

Parra M, M. A.; Luis L, M. A. [Universidad Autonoma Metropolitana, Unidad Azcapotzalco, Division de Ciencias Basicas, Av. San Pablo No. 180, Col. Reynosa Tamaulipas, 02200 Mexico D. F. (Mexico); Raya A, R.; Cruz G, H. S., E-mail: roberto.raya@inin.gob.mx [ININ, Departamento del Reactor, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2013-10-15

This work presents the measurement of the neutrons spectrum in energies in the central thimble of the reactor TRIGA Mark III to a power of 1 MW in stationary state, with the core in the center of the pool. To achieve this objective, several thin sheets were irradiated (one at the time) in the same position of the core. The activation probes were selected in such a way that covered the energy range (1 x 10{sup -10} to 20 MeV) of the neutrons spectrum in the reactor core, for this purpose thin sheets were used of {sup 197}Au, {sup 58}Ni, {sup 115}In, {sup 24}Mg, {sup 27}Al, {sup 58}Fe, {sup 59}Co and {sup 63}Cu. After the irradiation, the high energy gamma emissions of the activated thin sheets were measured by means of gamma spectrometry, in a counting system of high resolution, with a Hyper pure Germanium detector, obtaining this way the activity induced in the thin sheets whose magnitude is proportional to the intensity of the neutrons flow, this activity together to a theoretical initial spectrum are the main entrance data of the computational code SANDBP (Hungarian version of the code Sand-II) that uses the unfolding method for the calculation of the spectrum. (Author)

ANALISIS POTENSI DAN PROYEKSI PENERIMAAN RETRIBUSI PELAYANAN PASAR DI KABUPATEN SEMARANG

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Evi Fatmawati

2017-06-01

Full Text Available Retribusi pelayanan pasar merupakan jenis retribusi jasa umum yang cukup potensial, dikarenakan Kabupaten Semarang menarik retribusi dari 33 pasar tradisional setiap harinya. Tujuan penelitian ini, untuk menganalisis potensi penerimaan retribusi pasar di Kabupaten Semarang tahun 2011 – 2015, serta memproyeksi pendapatan retribusi pelayanan pasar tahun 2016 – 2020. Penelitian ini menggunakan analisis kontribusi, analisis pertumbuhan, analisis potensi, dan analisis ARIMA (2,1,2 (Auto Regressive Integrated Moving Average. Hasil penelitian menunjukan: (1 kontribusi retribusi pelayanan pasar terhadap retribusi daerah dan PAD dalam kategori kurang dan sangat kurang, (2 pertumbuhan retribusi pelayanan pasar berfluktuasi, (3 penerimaan retribusi pelayanan pasar belum berdasarkan potensi, (4 target retribusi pelayanan pasar berada dibawah potensi, (5 proyeksi pendapatan retribusi pasar meningkat dalam lima tahun kedepan. Adanya selisih antara potensi dengan realisasi dapat dijadikan peluang oleh Pemerintah Daerah dalam memaksimalkan penerimaan retribusi pelayanan pasar. Saran peneliti yaitu penetapan target sesuai dengan potensi, serta peningkatan kualitas pelayanan pasar, hal tersebut diharapkan dapat meningkatkan sumbangan retribusi pelayanan pasar terhadap PAD di Kabupaten Semarang. Retribution as a source of local income had a great opportunity to be improve and be develop so. Market retribution service was a kind of public service retribution that potential enough, due to Semarang Regency managed and attracted the retribution of 33 traditional markets every day. The objective of this research was to analyze the potential and contribution of market retribution at Semarang Regency in 2011-2015, also approximate local market retribution service in 2016-2010. This research used contribution analysis, the growth analysis, potential analysis, and analyzed ARIMA (2,1,2 (Auto Regressive Integrated Moving Average. The results of this research that : (1

Determination of the energy spectrum of the neutrons in the central thimble of the reactor core TRIGA Mark III

International Nuclear Information System (INIS)

Parra M, M. A.

2014-01-01

This thesis presents the neutron spectrum measurements inside the core of the TRIGA Mark III reactor at 1 MW power in steady-state, with the bridge placed in the center of the swimming pool, using several metallic threshold foils. The activation detectors are inserted in the Central Thimble of the reactor core, all the foils are irradiated in the same position and irradiation conditions (one by one). The threshold detectors are made of different materials such as: Au 197 , Ni 58 , In 115 , Mg 24 , Al 27 , Fe 58 , Co 59 and Cu 63 , they were selected to cover the full range the energies (10 -10 to 20 MeV) of the neutron spectrum in the reactor core. After the irradiation, the activation detectors were measured by means of spectrometry gamma, using a high resolution counting system with a hyper pure Germanium crystal, in order to obtain the saturation activity per target nuclide. The saturation activity is one of the main input data together with the initial spectrum, for the computational code SANDBP (hungarian version of the code SAND-II), which through an iterative adjustment, gives the calculated spectrum. The different saturation activities are necessary for the unfolding method, used by the computational code SANDBP. This research work is very important, since the knowledge of the energetic and spatial distribution of the neutron flux in the irradiation facilities, allows to characterize properly the irradiation facilities, just like, to estimate with a good precision various physics parameters of the reactor such as: neutron fluxes (thermal, intermediate and fast), neutronic dose, neutron activation analysis (NAA), spectral indices (cadmium ratio), buckling, fuel burnup, safety parameters (reactivity, temperature distribution, peak factors). In addition, the knowledge of the already mentioned parameters can give a best use of reactor, optimizing the irradiations requested by the users for their production process or research projects. (Author)

Tingkat Keamanan Konsumsi Residu Karbamat dalam Buah dan Sayur Menurut Analisis Pascakolom Kromatografi Cair Kinerja Tinggi

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Bambang Wispriyono

2013-02-01

Full Text Available Karbamat merupakan salah satu jenis pestisida yang banyak digunakan untuk membasmi hama buah dan sayur. Untuk menentukan bahwa residu karbamat dalam sayuran masih aman dikonsumsi manusia, telah dilakukan analisis beberapa residu karbamat seperti metomil, karbaril, karbofuran, dan propoksur. Sampel-sampel tomat, apel, selada air, kubis, dan sawi hijau dikumpulkan dari tiga supermarket dan satu pasar tradisional di Depok, Jawa Barat. Analisis dilakukan serempak untuk ke empat residu karbamat menggunakan kromatografi cair kinerja tinggi denganpereaksi o-ftalaldehida dan 2-merkaptoetanol dalam reaktor pascakolom dengan detektor fluoresensi. Dari sampel-sampel buah dan sayur yang dianalisis, hanya sawi hijau asal pasar tradisional yang positif mengandung propoksur dengan kadar 1,2 mg/25 gram berat basah (0,048 mg/g berat basah. Dengan Acceptable Daily Intake(ADI propoksur 0,005 mg/kg berat badan/hari, konsumsi sawi hijau harian seberat 20 g/hari masih cukup aman dari gangguan kesehatan akibat pajanan kronik propoksur dengan margin of safety 298,7 (> 100 sebagai batas aman. Carbamat is a group of pesticides which is commonly used to control fruits and vegetables pests. To determine that carbamat residues in fruits and vegetables are safe for human consumption, carbamate residues such as methomyl, carbaryl, carbofuran, and propoxur in vegetables and fruits have been analyzed. Samples of tomato, apple, water lettuces, cabbage, and mustard greens were collected from three supermarkets and one traditional market in Depok, West Java. The analysis was carried out simultaneously for all four carbamate residues by high performance liquid chromatography using o-phtaladehyde and 2 mercaptoethanol reagents in post-column reactor with a fluorescence detector. Of fruits and vegetable samples analyzed, only mustard greens from traditional market positively containe propoxur at 1.2 mg/ 25 gram wet weight (0,048 mg/gram wet weight. With Acceptable Daily Intake (ADI

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

International Nuclear Information System (INIS)

Stritar, A.; Jencic, I.

1996-01-01

Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information

Third Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Stritar, A; Jencic, I [Nuclear Society of Slovenia (Slovenia); eds.

1996-07-01

Third Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 71 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accident management, Thermal Hydraulics, NPP Operation, Radioactive Waste Management, Main Components Integrity, Environment and Other Aspects and Public Information.

MARS: Mirror Advanced Reactor Study

International Nuclear Information System (INIS)

Logan, B.G.

1984-01-01

A recently completed two-year study of a commercial tandem mirror reactor design [Mirror Advanced Reactor Study (MARS)] is briefly reviewed. The end plugs are designed for trapped particle stability, MHD ballooning, balanced geodesic curvature, and small radial electric fields in the central cell. New technologies such as lithium-lead blankets, 24T hybrid coils, gridless direct converters and plasma halo vacuum pumps are highlighted

Safety equipment in a reactor

International Nuclear Information System (INIS)

Shiratori, Hirozo; Ishiyama, Satoshi; Ugawa, Yukio.

1976-01-01

Object: To safely retain, even if fuel should be molten and flown through the bottom of a container in a reactor, the molten fuel to remove heat generation of the fuel to prevent occurrence of a critical trouble. Structure: A reactor container housing a core and coolant has thereunder a separation dome in a central portion thereof and a partitioning plate coaxially and circularly disposed in the periphery of the separation dome, with a tray formed of magnesium oxide being disposed. Further, a cooling path system is provided so as to surround the tray. The cooling path system and the reactor container are surrounded and protected by a reactor wall provided with heat insulating refractory bricks, a coolant pouring system extends through the reactor wall, and the coolant is supplied to the tray. (Furukawa, Y.)

A fast and flexible reactor physics model for simulating neutron spectra and depletion in fast reactors - 202

International Nuclear Information System (INIS)

Recktenwald, G.D.; Bronk, L.A.; Deinert, M.R.

2010-01-01

Determining the time dependent concentration of isotopes within a nuclear reactor core is central to the analysis of nuclear fuel cycles. We present a fast, flexible tool for determining the time dependent neutron spectrum within fast reactors. The code (VBUDS: visualization, burnup, depletion and spectra) uses a two region, multigroup collision probability model to simulate the energy dependent neutron flux and tracks the buildup and burnout of 24 actinides, as well as fission products. While originally developed for LWR simulations, the model is shown to produce fast reactor spectra that show high degree of fidelity to available fast reactor benchmarks. (authors)

ANALISIS FINANSIAL DAN KELEMBAGAAN RANTAI NILAI MEBEL MAHONI JEPARA

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Nunung Parlinah

2011-12-01

Full Text Available Industri mebel umumnya termasuk dalam industri kecil dan menengah. Selain berperan dalam penerimaan devisa, bisnis di bidang mebel ini juga menciptakan lapangan kerja bagi masyarakat terutama di Kabupaten Jepara. Adanya hubungan (pemberi kepercayaan - (penerima kepercayaan yang terjadi antar aktor atau pelaku di dalam rantai berpengaruh terhadap besarnya distribusi nilai tambah yang diperoleh oleh masingmasing pelaku di sepanjang rantai nilai Tujuan dari penelitian ini adalah mengidentifikasi kelembagaan (aturan yang terjadi antar pelaku di sepanjang rantai nilai mebel mahoni Jepara dan menentukan skenario kebijakan yang dapat mendukung bagi kelestarian industri mebel Jepara. Data yang digunakan meliputi data primer dan data sekunder. Analisis data meliputi identifikasi aktor dan kelembagaan (aturan yang terjadi antar pelaku serta analisis manfaat biaya yang terdiri dari NVP, BCR dan IRR. Hasil penelitian menunjukkan bahwa (1 para pengrajin ( memproduksi mebelnya lebih didasarkan pada pesanan pembeli ( . agent principal Asymetic information yang terjadi antara pedagang kayu dan petani juga telah mengakibatkan posisi petani sebagai (2 Nilai NPV, BCRdan IRR untuk tiap pelaku berbeda-beda tetapi nilai-nilai tersebut mengindikasikan bahwa pola kemitraan yang terjadi antar pelaku dalam rantai nilai mebel mahoni saat ini sudah efektif. Skenario kebijakan yang dapat diterapkan adalah kebijakan yang bersifat insentif bagi petani hutan rakyat, peningkatan kemampuan pengrajin di bidang pemasaran; dan membangun aksi kolektif diantara pengrajin. price taker;

Analisis Neraca Air Lahan untuk Tanaman Padi dan Jagung Di Kota Bengkulu

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Jaka A. I. Paski

2018-01-01

Citation: Paski, J.A.I., Faski, G.I.S.L., Handoyo, M.F. dan Pertiwi, D.A.S. (2017. Analisis Neraca Air Lahan untuk Tanaman Padi dan Jagung di Kota Bengkulu. Jurnal Ilmu Lingkungan, 15(2, 83-89, doi:10.14710/jil.15.2.83-89

Pengaruh Advance Organizer Berbasis Proyek Terhadap Kemampuan Analisis – Sintesis Siswa

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Tasiwan -

2014-01-01

Full Text Available Penelitian ini dilakukan untuk mengetahui pengaruh model pengatur kemajuan (advance organizer berbasis proyek terhadap kemampuan analisis – sintesis siswa pada konsep Energi. Sebelum pembelajaran, diberikan tugas proyek pada siswa untuk merealisasikan bel listrik sederhana, rangkaian arus seri - paralel, dan tuas. Produk proyek digunakan sebagai advance organizer dalam pembelajaran di kelas. Penguatan kognitif dilakukan melalui diskusi kelompok dan pembuatan peta konsep, ekspositori guru di kelas, dan kegiatan eksperimen laboratorium. Data diambil melalui pretest, post test, observasi partisipatif pembelajaran oleh dua orang observer, penilaian produk, peta konsep dan laporan kegiatan eksperimen. Teknik analisis data meliputi uji prasyarat data dan uji hipotesis Hasil penelitian menunjukkan bahwa siswa mengalami peningkatan kemampuan analisis – sintesis dalam aspek menguraikan, mengkategorikan, mengidentifikasi, merumuskan pernyataan, merekonstruksi, menentukan konsep, dan menganalisis konsep dengan rata – rata peningkatan delta skor sebesar 54,46 %, uji t sebesar 6,4, dan skala gain sebesar 0,3. This study was conducted to determine the effect of project-based advance organizer model on student’s analysis - synthesis ability of the energy concept. Students were given an assignment to realize the project on simple electric bell, the series – parallel circuit, and lever, before learning. The products of project were used as an advanced organizer in the learning activity. Cognitive strengthening was done through group discussions and concept mapping, expository learning in the classroom, and laboratory experiments activities. The data were taken through a pretest, post-test, participant observation study by two observers, product assessment, concept maps and report of experiment activities. Results showed that the students’ analysis - synthesis ability increased in the aspect of describing, categorizing, identifying, statement

ANALISIS BEBAN KERJA DENGAN MENGGUNAKAN METODE CVL DAN NASATLX DI PT. ABC

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Renty Anugerah Mahaji Puteri

2017-10-01

Full Text Available PT. ABC merupakan perusahaan Jepang yang bergerak di bidang usaha jasa konstruksi mekanikal, elektrikal, dan system komunikasi. Sebagai perusahaan jasa konstruksi, PT. ABC dituntut untuk mencapai tujuan / target perusahaan tiap tahunnya yaitu mendapatkan tender proyek, maka tak jarang karyawannya dituntut untuk lembur. Seringnya karyawan lembur, maka menimbulkan masalah kelelahan terhadap para karyawannya sehingga target tidak tercapai. Penelitian ini bertujuan untuk mengevaluasi beban kerja yang dialami oleh engineer leader pada Departemen DesaindanOperasional di PT. ABC. Beban kerja yang diukur adalah beban kerja fisik dan mental. Beban kerja fisik diukur berdasarkan cardiovascular load (CVL. Beban kerja mental diukur dengan menggunakan metode NASA-Task Load Index (NASA-TLX. Berdasarkan hasil analisis CVL, beban kerja fisik yang diterima engineer proyek memiliki presentase CVL sebesar 31,16%, denganhasilperbaikanmenjadi 23,38%. Sedangkan dari hasil analisis NASA-TLX, beban kerja mental yang diterima engineer proyek yaitu dengan skor NASA-TLX 74,2% denganhasilperbaikanmenjadi 51,6%, sedangkan skor NASA-TLX engineer head office 61,5% denganhasilperbaikanmenjadi 47,66%.

Analisis Struktur Kristal Lifepo4 Olivine Sebagai Bahan Katoda Batere Li-Ion

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Indra Gunawan

2013-10-01

Full Text Available Sintesis LiFePO4 dilakukan dengan pencampuran LiCl, FeCl2.4H2O dan H3PO4 ekuimolar ke dalam air. Homogenasi larutan dilakukan dengan pengaduk magnetic pada suhu 60o C. Prekursor LiFePO4 diperoleh setelah pemanasan 200o C dengan furnace selama 2 jam. Sintering prekursor LiFePO4 dilakukan pada suhu 700o C dengan furnace selama 4 jam dengan aliran N2 untuk membentuk fasa kristalit LiFePO4. Kemurnian fasa dan struktur kristal dianalisis dengan menggunakan XRD. Analisis struktur kristal dari pola difraksi sinar-X dilakukan dengan perangkat lunak FULLPROF. Pengamatan morfologinya dilakukan dengan menggunakan SEM dengan kombinasi energy dispersive spectroscopy (EDS dan pengukuran gugus fungsional dengan FT-IR. Hasil analisis struktur kristal menunjukkan bahwa senyawa LiFePO4 memiliki struktur Kristal orthorhombic, space group 62, simbol Pnma (Hermann-Mauguin dengan parameter kisi a= 6.0019999, b= 10.330000, c= 4.6999998. 

Analisis dan Rencana Pengembangan Jaringan Distribusi Air Bersih Unit Cabang Timur PDAM Kabupaten Klaten

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Ana Tri Lestari

2017-01-01

Full Text Available Unit Cabang Timur Perusahaan Daerah Air Minum (PDAM Kabupaten Klaten dibagi menjadi 3 unit pelayanan Ibu Kota Kecamatan (IKK dan mempunyai tingkat pelayanan yang masih rendah pada tahun 2015, yaitu Unit IKK Ceper 17,6%; Unit IKK Pedan 2,43%; dan Unit IKK Cawas 31,26% sehingga peningkatan persen pelayanan menjadi hal yang perlu dilakukan. Hal ini didukung dengan adanya penambahan debit produksi sebesar 50 liter/detik. Selain itu, jaringan distibusi belum dibentuk blok pelayanan sehingga sulit untuk mengontrol kehilangan air. Perencanaan ini dilakukan pembagian blok pelayanan menjadi 26 blok dan 5 tapping. Setelah itu dilakukan analisis kondisi eksiting. Hasil analisis kondisi eksisting menunjukkan kondisi hidrolika perpipaan kecuali kecepatan masih memenuhi kriteria, yaitu tekanan antara (15,43-59,99 m, kecepatan (0-0,91 m/detik, unit headloss (0-3,51 m/km. Kemudian dilakukan pengembangan jaringan yang dibagi menjadi 2 tahap, dimana tahap 1 meningkatkan persen pelayanan, sedangkan tahap 2 menambah daerah pelayanan baru. Blok pelayanan setelah pengembangan menjadi 29 blok dan 5 titik tapping. Kemudian analisis rencana pengembangan dilakukan dan menunjukkan bahwa kondisi hidrolika pipa untuk tekanan di jaringan distribusi IKK Cawas bernilai negatif. Hal ini dikarenakan unit headloss yang terjadi pada pipa dari reservoir menuju titik tapping pertama IKK Cawas sebesar 5,78 m/km dengan panjang pipa 14,35 km sehingga headloss  sebesar 82,94 m menyebabkan tekanan menjadi -2,89 m. Permasalahan ini dapat diatasi dengan parallel pipa diameter 200 mm sepanjang 9 km. Parallel pipa tersebut mengakibatkan tekanan  pada titik tapping pertama IKK Cawas menjadi 34,65 m dan titik tapping terjauh (blok 19 sebesar 16,34 m.  Hasil analisis hidrolika, seperti unit headloss berada pada rentang (0-5,78 m/km, namun kecepatan masih ada yang di bawah 0,3 m/detik. Rencana anggaran biaya (RAB yang dibutuhkan untuk melakukan pengembangan jaringan sebesar Rp 2.470.153,051.71.

Meeting on reactor safety research

International Nuclear Information System (INIS)

1982-09-01

The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.) [de

Analisis Karakteristik Hujan untuk Pendugaan Debit Aliran Rencana Sungai Anafri di Kota Jayapura

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Nurfaijin Nurfaijin

2016-10-01

Full Text Available ABSTRAK Penelitian ini bertujuan mengkaji karakteristik hujan wilayah DAS Anafri, menghitung debit aliran rencana, dan mengkaji kapasitas Sungai Anafri dalam merespon pengalihragaman hujan menjadi aliran permukaan. Kajian karakteristik hujan yakni ketebalan, intensitas, dan durasi hujan dilakukan dengan analisis statistik data hujan. Analisis distribusi data hujan diasumsikan sesuai dengan Metode Gumbel, sehingga untuk menentukan hujan periode ulang 2 tahun, 5 tahun, 10 tahun, dan 25 tahun menggunakan persamaan Gumbel. Hujan periode ulang digunakan untuk menghitung debit aliran rencana Metode Rasional. Analisis kapasitas sungai dilakukan dengan membandingkan debit aliran rencana dalam periode ulang T dengan kapasitas sungai. Penghitungan kapasitas sungai dilakukan pada penampang PI (bagian hulu, P2,dan P3 (bagian hilir. Debit aliran rencana yang digunakan dalam analisis kapasitas sungai adalah debit aliran Q25tahun (107,478 m³/detikdan 163,726 m³/detik. Hasil analisis menunjukan bahawa, terjadinya limpasan pada penampang sungai PI dan P2 pada saat menampung debit banjir yang diketahui penyebab utamanya adalah bank full capacity kecil, maka alternat! ( penanganan yang direkomendasikan adalah peninggian tanggul sungai. Analisis kapasitas sungai menggunakan debit banjir periode ulang 25 tahun menunjukan bahwa, terjadi limpasan pada lokasi penampang PI sampai P2 dengan panjang ruas 400 m yang terjadi pada tanggul sisi kanan dan tanggul sisi kiri dengan panjang ruas 40 meter. Limpasan terjadi setinggi 0,1 m hingga 1,6 m pada tanggul sisi kanan dan 0,1 m hingga 0,3 m pada tanggul sisi kiri, sehingga peninggian tanggul yang direkomendasikan adalah setinggi 1,6 mpada sisi kanan dan 0,3 m pada tanggul sisi kiri. ABSTRACT This study aims to examine the characteristics of rainfall watershed of Anafri calculate the flow rate plan, and assess the river capacity to respond diversion of rain to be surface runoff. In this study, the analysis of rainfall

Fuel loading method to exchangeable reactor core of BWR type reactor and its core

International Nuclear Information System (INIS)

Koguchi, Kazushige.

1995-01-01

In a fuel loading method for an exchangeable reactor core of a BWR type reactor, at least two kinds of fresh fuel assemblies having different reactivities between axial upper and lower portions are preliminarily prepared, and upon taking out fuel assemblies of advanced combustion and loading the fresh fuel assemblies dispersingly, they are disposed so as to attain a predetermined axial power distribution in the reactor. At least two kinds of fresh fuel assemblies have a content of burnable poisons different between the axial upper portion and lower portions. In addition, reactivity characteristics are made different at a region higher than the central boundary and a region lower than the central boundary which is set within a range of about 6/24 to 16/24 from the lower portion of the fuel effective length. There can be attained axial power distribution as desired such as easy optimization of the axial power distribution, high flexibility, and flexible flattening of the power distribution, and it requires no special change in view of the design and has a good economical property. (N.H.)

Design features of BREST reactors. Experimental work to advance the concept of BREST reactors. Results and plans

International Nuclear Information System (INIS)

Filin, A.I.; Orlov, V.V.; Leonov, V.N.; Sila-Novitskij, A.G.; Smirnov, V.S.; Tsikunov, V.S.

2001-01-01

Principle designs of 300 MW(th) and 1200 MW(th) lead-cooled fast reactors are presented. Reactors of various output are shown to be built using the same principles. In conjunction with increased output and to implement inherent safety concept in BREST-1200 reactor design a number of new solutions, which may be used in BREST-300 concept too, has been taken including: pool-type reactor design not requiring metal vessel, hence, not limiting reactor power; new handling system allowing to reduce central hall and building dimensions as a whole; emergency cooling system using Field pipes, immersed directly in lead, which may be used to cool down reactor under normal conditions; by-pass line incorporated in coolant loop allowing to refuse the actively actuating valve initiated in pumps shut down. (author)

Development of a methodology of analysis of instabilities in BWR reactors; Desarrollo de una metodologia de analisis de inestabilidades en reactores PWR

Energy Technology Data Exchange (ETDEWEB)

Garcia-Fenoll, M.; Abarca, A.; Barrachina, T.; Miro, R.; Verdu, G.

2012-07-01

This paper presents a methodology of analysis of the reactors instabilities of BWR type. This methodology covers of modal analysis of the point operation techniques of signal analysis and simulation of transients, through 3D Coupled RELAP5/PARCSv2.7 code.

Developments in gaseous core reactor technology

International Nuclear Information System (INIS)

Diaz, N.J.; Dugan, E.T.

1979-01-01

An effort to characterize the most promising concepts for large, central-station electrical generation was done under the auspices of the Nonproliferation Alternative Systems Assessment Program (NASAP). The two leading candidates were identified from this effort: The Mixed-Flow Gaseous Core Reactor (MFGCR) and the Heterogeneous Gas Core Reactor (HGCR). Key advantages over other nuclear concepts are weighed against the disadvantages of an unproven technology and the cost-time for deployment to make a sound decision on RandD support for these promising reactor alternatives. 38 refs

Communication system and spectral analysis for Ge-Li and GeHp detectors; Sistema de comunicaciones y analisis de espectros para detectores Ge-Li y GeHp

Energy Technology Data Exchange (ETDEWEB)

Fernandez, J; Castano, P; Bonino, A D; Righetti, M A

1991-12-31

An integral communication and spectral analysis system (SICADE) was developed and implemented to satisfy the need to optimize and automate the measurement system used in Atucha I nuclear power plant for the activity in the primary loop`s water extracted by the TV system. The importance of these measurements is based on the fact that from the spectrometric analysis of the samples extracted, the Iodines-GN and Iodines-Iodines relations, which allow to detect the presence of deficient fuel elements, are calculated. The system developed is based on two modules integrated in a unique set commanded by the operators through the screen dialogue. (Author). [Espanol] Dada la necesidad de optimizar y automatizar el sistema de medicion utilizado en la Central Nuclear Atucha I para la actividad en el agua del circuito primario extraida a traves del sistema TV se desarrollo e implemento un sistema integral de Comunicacion y Analisis de espectros (SICADE). La importancia de estas mediciones radica en el hecho que del analisis espectrometrico de las muestras extraidas se calculan las relaciones entre Iodos-GN e Iodos-Iodos que permiten detectar la presencia de elementos combustibles fallados. El sistema desarrollado esta basado en dos modulos integrados en un unico conjunto comandado por el operador a traves del dialogo por pantalla. (Autor).

Analisis “Brand Equity” Siaran Berita Stasiun Televisi Swasta Indonesia

OpenAIRE

Arif Sugiono; Prima Mulyasari Agustina

2004-01-01

Penelitian ini bertujuan untuk mengetahui keadaan berbagai merek siaran berita stasiun televisi swasta berdasarkan dimensi ekuitas mereknya, dengan memfokuskan pada empat dimensi ekuitas merek, yang meliputi loyalitas merek, kesadaran merek, persepsi kualitas, dan asosiasi merek. Metode yang digunakan metode deskriptif, dengan analisis data menggunakan tabulasi dan teknik skala. Hasil penelitian dari dimensi loyalitas merek tiga besar siaran berita secara berurutan adalah Buser, Patroli dan L...

ANALYSIS OF GAMMA HEATING AT TRIGA MARK REACTOR CORE BANDUNG USING PLATE TYPE FUEL

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Setiyanto Setiyanto

2016-10-01

Full Text Available ABSTRACT In accordance with the discontinuation of TRIGA fuel element production by its producer, the operation of all TRIGA type reactor of at all over the word will be disturbed, as well as TRIGA reactor in Bandung. In order to support the continuous operation of Bandung TRIGA reactor, a study on utilization of fuel plate mode, as used at RSG-GAS reactor, to replace the cylindrical model has been done. Various assessments have been done, including core design calculation and its safety aspects. Based on the neutronic calculation, utilization of fuel plate shows that Bandung TRIGA reactor can be operated by 20 fuel elements only. Compared with the original core, the new reactor core configuration is smaller and it results in some empty space that can be used for in-core irradiation facilities. Due to the existing of in-core irradiation facilities, the gamma heating value became a new factor that should be evaluated for safety analysis. For this reason, the gamma heating for TRIGA Bandung reactor using fuel plate was calculated by Gamset computer code. The calculations based on linear attenuation equations, line sources and gamma propagation on space. Calculations were also done for reflector positions (Lazy Susan irradiation facilities and central irradiation position (CIP, especially for any material samples. The calculation results show that gamma heating for CIP is significantly important (0,87 W/g, but very low value for Lazy Susan position (lest then 0,11 W/g. Based on this results, it can be concluded that the utilization of CIP as irradiation facilities need to consider of gamma heating as data for safety analysis report. Keywords: gamma heating, nuclear reactor, research reactor, reactor safety.   ABSTRAK Dengan dihentikannya produksi elemen bakar reaktor jenis Triga oleh produsen, maka semua reaktor TRIGA di dunia terganggu operasinya, termasuk juga reaktor TRIGA 2000 di Bandung. Untuk mendukung pengoperasian reaktor TRIGA Bandung

Fourth Regional Meeting: Nuclear Energy in Central Europe, Proceedings

Energy Technology Data Exchange (ETDEWEB)

Mavko, B; Cizelj, L [eds.; Nuclear Society of Slovenia (Slovenia)

1997-07-01

Fourth Regional Meeting for Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 89 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Research Reactors, Reactor Physics, Probabilistic Safety Assessment, Severe Accidents, Ageing and Integrity, Thermal Hydraulics, NPP Operation Experiance, Radioactive Waste Management, Environment and Other Aspects, Public and Nuclear Energy, SG Replacement and Plant Uprating.

Analisis Derau dalam Perancangan Rangkaian Terintegrasi Op-Amp

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Siti Sendari

2009-02-01

Full Text Available Perancangan IC Op-Amp, memerlukan spesifikasi-spesifikasi yang meliputi parameter proses dan parameter perancangan. Dalam menentukan parameter perancangan, derau merupakan suatu hal yang tidak bisa ditinggalkan, karena derau dapat menentukan keandalan perancangan. Untuk menganalisis derau pada IC Op-Amp langkah pertama yang harus diketahui adalah sumber-sumber derau, setelah itu dilakukan analisis derau baik secara teoritis maupun secara simulasi untuk mengetahui derau yang mungkin terjadi dalam perancangan IC, apakah sudah sesuai dengan spesifikasi yang ditentukan atau tidak. Untuk simulasi derau dapat dilakukan dengan program Spice.

Pembelajaran Biokimia melalui Analisis Kasus-kasus Olahraga untuk Meningkatkan Sport Scientific Literaci Mahasiswa

Directory of Open Access Journals (Sweden)

- Erman

2013-01-01

Full Text Available Abstract: Biochemistry Teaching through Sport-case Analyses to Improve Students' Sport Scientific Literacy. This quasi-experimental study focuses on examining the effect of biochemistry teaching on students' sport scientific literacy (SSL. The study involved 107 students of a teacher training institution, selected using a stratified random sampling. The results of t-test utilizing pre-test and post-test control group design show that biochemistry teaching affects students' SSL, as indicated by the scores of the experimental group which were four times higher than those of the control group. The SSL level of the experimental group increased from level 2 (nominal and level 3 (functional to level 3 (functional, level 4 (conceptual, and level 5 (multidimensional. Abstrak: Pembelajaran Biokimia melalui Analisis Kasus-kasus Olahraga untuk Meningkatkan Sport Scientific Literaci Mahasiswa. Penelitian ini bertujuan untuk mengetahui pengaruh pembelajaran biokimia melalui analisis kasus-kasus olahraga terhadap literasi sport scientific mahasiswa. Sebanyak 107 mahasiswa dari program studi ilmu keolahragaan sebuah LPTK di Surabaya dipilih sebagai sampel dengan menggunakan sampling random berstrata. Desain yang digunakan adalah desain pretest-posttest control group dari desain kuasi eksperimen. Data dianalisis dengan uji-t sampel independen. Hasil peneli­tian menunjukkan bahwa pembelajaran biokimia melalui analisis kasus-kasus olahraga merupakan suatu metode yang efektif untuk meningkatkan sport Scientific literacy (SSL mahasiswa. Rerata skor perolehan SSL yang diperoleh mahasiswa kelompok eksperimen sekitar 4 kali lebih tinggi daripada yang diperoleh mahasiswa kelompok kontrol. Tingkatan SSL mahasiswa naik dari level 2 (nominal dan level 3 (fungsional menjadi level 3 (fungsional, level 4 (konseptual, dan level 5 (multidimensional.

Analisis Cadangan Devisa Indonesia

Directory of Open Access Journals (Sweden)

Lusia Bunga Uli

2016-09-01

Full Text Available Abstract This study aims to determine the relationship between variables export, import, and exchange rate against Foreign Exchange Reserves in Indonesia. The data used in the empirical study of a sequence of data monthly time of year 2011.01 through 2014.12 from Bank Indonesia and the Central Statistics Agency (BPS. The analysis tool used is Auto Regression Vector Model (VAR. The results of this study indicate that the one-way relationship between the variables of foreign reserves and export. Then one-way relationship between exchange rate and exports. Lastly, there is a two-way relationship between imports and foreign exchange reserves, two-way relationship between exchange rate and foreign exchange reserves, two-way relationship between imports and exports, two-way relationship between the exchange rate and imports. The results also showed foreign exchange reserves are significantly influenced by the movement itself at a probability of 1 %. Export variable negative and not significantly affect the foreign exchange reserves. While imports of positive and not significant to the foreign exchange reserves. Foreign Exchange Reserves Indonesia is positively influenced by the exchange rate and not significant. Keywords: Foreign exchange reserves, exports, imports, exchange rate   Abstrak. Penelitian ini bertujuan untuk mengetahui seberapa keterkaitan antar variabel ekspor, impor, dan nilai tukar rupiah terhadap Cadangan Devisa Indonesia. Data yang digunakan dalam kajian empiris ini merupakan data runtutaan waktu bulanan dari tahun 2011.01 sampai 2014. 12 yang berasal dari Bank Indonesia dan Badan Pusat Statistik (BPS. Alat analisis yang digunakan yaitu Vector Autoregression Model (VAR. Hasil dari penelitian ini menunjukkan bahwa hubungan searah antara variabel cadangan devisa ke ekspor. Lalu hubungan searah antara kurs terhadap ekspor Terakhir, terdapat hubungan dua arah antara impor dan cadangan devisa, hubungan dua arah antara kurs dan cadangan

SOLASE: a conceptual laser fusion reactor design

International Nuclear Information System (INIS)

Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

1977-12-01

The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion reactors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

What have fusion reactor studies done for you today?

International Nuclear Information System (INIS)

Kulchinski, G.L.

1985-01-01

The University of Wisconsin examines the fusion program and puts into perspective what return is being made on investments in fusion reactor studies. Illustations show financial support for fusion research from the four major programs, FY'82 expenditures on fusion research, and the total expenditures on fusion research since 1951. Topics discussed include the estimated number of scientists conducting fusion research, the conceptual design study of a fusion reactor, scoping study of a reactor, the chronology of fusion reactor design studies, published fusion reactor studies 1967-1983, conceptual fusion reactor design studies, STARFIRE reference design, MARS central cell, HYLIFE reaction chamber, and selected contributions of reactor design studies to base programs

Failure analysis to the weights of balance of a 350 MW turbo-generator; Analisis de falla a los pesos de balanceo de un turbogenerador de 350 MW

Energy Technology Data Exchange (ETDEWEB)

Vital Flores, Francisco; Gamero Arroyo, Jose Manuel [LAPEM, Comision Federal de Electricidad (Mexico)

2007-11-15

The selection of materials and the quality control in the supply of the components, as well as the involved operative variables in the process of work to which an equipment, device or a system of a power station of electrical generation are subjected, impact in the same in their useful life in a decisive way. In this document it is presented an analysis of a failure occurred in a 350 MW turbo-generator by the loosening of the balance weights, in which it is mentioned the flaws occurred by this cause and a metallographic analysis that indicates the main fault for the happening. [Spanish] La seleccion de material y el control de calidad en los suministros de los componentes, asi como las variables operativas involucradas en el proceso de trabajo al cual es sometido un equipo, dispositivo o un sistema de una central de generacion electrica, impactan en los mismos de manera decisiva en su vida util. En este documento se presenta un analisis de falla ocurrido en un turbogenerador de 350 MW, por el desprendimiento de los pesos de balanceo, el cual se menciona de los desperfectos ocurridos por esta causa y un analisis metalografico que indica la falla principal por lo ocurrido.

Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

OpenAIRE

Nurul Dzakiya; MGS. Dwiki Nugraha; Nenden L. Sidik; Trias Galena

2017-01-01

Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m), lempung pasiran (11-30 m) dan lapukan batuan diorit (30-55 m) yang berada di kedalaman berbeda. Ketebalan batuan di pe...

Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan

OpenAIRE

Fachri, Yusrizal

2017-01-01

130306044 YUSRIZAL FACHRI, 2017. “Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan”. Dibimbing oleh ARMYN HAKIM DAULAY dan NEVY DIANA HANAFI. Penelitian ini bertujuan untuk mengidentifikasi karakteristik lembaga pemasaran, bentuk saluran, fungsi pemasaran, dan menganalisis nilai tambah di lembaga-lembaga pemasaran ayam ras pedaging di pasar tradisional Kota Medan pada April sampai Mei 2017. Penelitian ini menggunakan data primer yang didapatkan dari observasi dan waw...

Neutronic reactor

International Nuclear Information System (INIS)

Wende, C.W.J.

1976-01-01

A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

The fast reactor and electricity supply, a utility view

International Nuclear Information System (INIS)

Wright, J.K.; Hall, R.S.; Kemmish, W.B.; Thorne, R.T.

1982-01-01

The significance of the fast reactor is discussed from the viewpoint of the Central Electricity Generating Board. The need for the fast reactor and a possible timescale for its introduction are examined. It is emphasised that demonstration of the commercial and environmental acceptability of the fuel cycle will be needed before any commitment can be made to fast reactors. (U.K.)

Analisis Kekuatan Struktur Pallet Menggunakan Metode Elemen Hingga

Directory of Open Access Journals (Sweden)

Tria Mariz Arief

2015-07-01

Full Text Available Pallet sebagai suatu alat bantu untuk mempermudah proses bongkar-muat logistik. Palletdigunakan hampir dalam berbagai lingkungan transportasi logistik. Pada bahasan berikutdikhususkan dalam lingkup transportasi di dalam pesawat udara khususnya pada pesawatangkut militer. Di lingkungan militer pallet digunakan untuk transport logistik baik secara normalmuat (loading dan bongkar (unloading maupun kondisi bongkar dengan diterjunkan daripesawat udara. Untuk pemenuhan penggunaan tersebut dilakukan perancangan ulang (reverseengineering struktur pallet yang dapat dimanufaktur secara lokal. Hipotesis awal menunjukkanbahwa berdasarkan kondisi pembebanan pada pallet dapat diperkirakan bahwa kondisitegangan dan regangan maksimum akan terjadi pada posisi sudut struktur pallet yang ditransferbebannya ke komponen plat besi penahan siku-siku dan baut. Material yang digunakan padastruktur pallet adalah Allumunium Alloy 7075-T6 dengan kekuatan tarik sebesar 503 MPa.Analisis dilakukan dengan menggunakan simulasi numerik dengan metoda elemen hingga(FEM. Proses simulasi numerik kekuatan struktur pallet difokuskan pada pembebanan statis(termasuk pengaruh factor G dalam interval beban statis 4 ton sampai 7 ton. Analisis dilakukanpada perubahan variabel tegangan dan regangan terhadap variasi beban yang diberikan untukmendapatkan tingkat keamanan struktur (margin safety. Pemodelan dilakukan denganidealisasi model ¼ bagian menggunakan elemen terstruktur dengan jenis elemen hexahedral(brick dengan jumlah 73803 elemen dan 360323 node. Hasil analisis menunjukkan teganganekuivalen maksimum struktur Pallet adalah 94 MPa yang terjadi di penguat sudut (anglebracket. Sedangkan pada struktur penguat lapis (sandwich structure berbahan thick blockyang mempunyai kekuatan sebesar 20 MPa adalah sebesar 0.84 MPa. Tingkat keamanansecara keseluruhan struktur dengan mempertimbangkan factor G hingga 2 adalah 5.3.Kata kunci: Analisis struktur, pallet, logistik, reverse engineering, FEM

Analisis Tata Kelola Teknologi Informasi Menggunakan Kerangka Kerja COBIT 4.1 pada Fakultas Teknik Undip

Directory of Open Access Journals (Sweden)

Arini Arumana

2014-06-01

Full Text Available Peran teknologi informasi dalam suatu instansi sudah tidak dapat dielakkan lagi, mengingat perkembangannya yang begitu pesat seiring berjalannya waktu. Namun masalah yang sering terjadi di instansi adalah penggunaan teknologi informasi yang kadang tidak sesuai dengan harapan. Oleh karena itu diperlukan tata kelola terhadap penggunaan teknologi informasi yang biasa disebut dengan IT Governance. Fakultas teknik UNDIP adalah salah satu fakultas yang dalam operasionalnya sangat mengandalkan teknologi informasi, baik dalam aktifitas belajar mengajar maupun dalam menjalankan operasional bisnis. Kondisi sekarang di Fakultas Teknik sendiri tidak terdapat suatu indikator yang dapat menyatakan bahwa kinerja TI yang berjalan telah sesuai dengan visi dan misi Fakultas Teknik, oleh karena itu perlu dilakukan analisis tata kelola teknologi informasi, guna mengetahui performa TI sekarang sesuai dengan yang diharapkan oleh managemen atau tidak. Hasil dari analisis ini berupa tingkat kematangan tata kelola TI yang mecerminkan kondisi tata kelola TI di Fakultas Teknik dengan mengacu pada maturity level yang disediakan kerangka kerja COBIT 4.1, yakni dari level 0 (non-existent sampai 5 (optimized. Berdasarkan analisis yang dilakukan, secara garis besar kondisi kematangan tata kelola TI Fakultas Teknik berada pada level 2 yakni repeatable but intuitive. Kondisi ini mengacu pada beberapa kelemahan dalam proses-proses TI yang berjalan, diantaranya penetapan dan dokumentasi tindakan, kebijakan dan prosedur yang minim, serta tidak tersedianya service level yang disetujui bersama.

ANALISIS KEBUTUHAN UNTUK PENGEMBANGAN MODUL INKUIRI BERBASIS PERTANYAAN (MIBP DI SMP

Directory of Open Access Journals (Sweden)

Desak Made Citrawathi

2016-08-01

Full Text Available melakukan analisis kebutuhan untuk pengembangan dan penyusunan modul inkuri berbasis pertanyaan (MIBP. MIBP disusun untuk memfasilitasi pembelajaran sains agar dapat meningkatkan penguasaan konsep biologi, keterampilan proses sains, dan kemampuan berpikir siswa SMP. Pengembangan MIBP menggunakan model ADDIE. Prosedur pengembangan terdiri dari 5 tahap, yaitu 1 Menganalisis, 2 Mendisain, 3 Mengembangkan dan produksi, 4 Mengimplementasikan, dan 5 Mengevaluasi. Penelitian dilakukan dalam waktu 3 tahun. Pada tahun pertama ini dilakukan analisis kebutuhan dan mendisain MIBP. Subjek penelitian adalah guru IPA SMP Negeri dan Swasta di Kecamatan Buleleng. Pengumpulan data dilakukan dengan wawancara, penyebaran angket, observasi, dan dokumentasi. Analisis data dilakukan secara deskriptif dan interpretatif. Dari hasil analisis diperoleh bahwa kurikulum yang digunakan di SMPN 1,SMPN 2, dan SMPN 4 adalah kurikulum 2013, sedangkan di SMP lainnya masih menggunakan kurikulum 2006. Kemampuan guru bertanya untuk meningkatkan keterampilan proses sains, penguasaan konsep, dan kemampuan berpikir belum optimal. Hal ini ditunjukkan dari jenis pertanyaan yang diajukan guru 85,8 persen bersifat konvergen, dan 14,2 persen bersifat divergen. Berdasarkan pertanyaan menurut Taksonomi Bloom, pertanyaan yang diajukan guru 74,4 persen pertanyaan ingatan, 22,6 persen pemahaman, 2,68 persen aplikasi, dan 0,32 persen analisis. Salah satu yang dapat dilakukan untuk meningkatkan kemampuan guru adalah memfasilitasi pembelajarannya dengan MIBP. Dari karakteristik perkembangan kognitifnya, siswa SMP dapat dibelajarkan dengan strategi inkuiri, dan guru setuju dengan pengembangan MIBP. Kata kunci: Kemampuan berpikir, keterampilan proses sains, Modul Inkuiri Berbasis Pertanyaan, penguasaan konsep Pertanyaan, penguasaan konsep Abstract The purpose of this study was to analyze the need for the development and preparation of question-based inquiry module (QBIM. QBIM was designed conceiv to

Determination of the neutrons energy spectrum in the central thimble of the reactor core TRIGA Mark III

International Nuclear Information System (INIS)

Parra M, M. A.; Luis L, M. A.; Raya A, R.; Cruz G, H. S.

2013-10-01

This work presents the measurement of the neutrons spectrum in energies in the central thimble of the reactor TRIGA Mark III to a power of 1 MW in stationary state, with the core in the center of the pool. To achieve this objective, several thin sheets were irradiated (one at the time) in the same position of the core. The activation probes were selected in such a way that covered the energy range (1 x 10 -10 to 20 MeV) of the neutrons spectrum in the reactor core, for this purpose thin sheets were used of 197 Au, 58 Ni, 115 In, 24 Mg, 27 Al, 58 Fe, 59 Co and 63 Cu. After the irradiation, the high energy gamma emissions of the activated thin sheets were measured by means of gamma spectrometry, in a counting system of high resolution, with a Hyper pure Germanium detector, obtaining this way the activity induced in the thin sheets whose magnitude is proportional to the intensity of the neutrons flow, this activity together to a theoretical initial spectrum are the main entrance data of the computational code SANDBP (Hungarian version of the code Sand-II) that uses the unfolding method for the calculation of the spectrum. (Author)

Nuclear reactor fuel assembly

International Nuclear Information System (INIS)

Sakurai, Shungo; Ogiya, Shunsuke.

1990-01-01

In a fuel assembly, if the entire fuels comprise mixed oxide fuels, reactivity change in cold temperature-power operation is increased to worsen the reactor shutdown margin. The reactor shutdown margin has been improved by increasing the burnable poison concentration thereby reducing the reactivity of the fuel assembly. However, since unburnt poisons are present at the completion of the reactor operation, the reactivity can not be utilized effectively to bring about economical disadvantage. In view of the above, the reactivity change between lower temperature-power operations is reduced by providing a non-boiling range with more than 9.1% of cross sectional area at the inside of a channel at the central portion of the fuel assembly. As a result, the amount of the unburnt burnable poisons is decreased, the economy of fuel assembly is improved and the reactor shutdown margin can be increase. (N.H.)

ANALISIS STRATEGI PENGEMBANGAN SEKTOR PERTANIAN SUB SEKTOR BAHAN PANGAN DI KABUPATEN BOYOLALI

Directory of Open Access Journals (Sweden)

Muhammad Zaenuri

2017-06-01

Full Text Available Permasalahan yang dikaji dalam penelitian ini adalah 1. Komoditas tanaman bahan makanan unggulan apa saja yang ada di masing-masing kecamatan di Kabupaten Boyolali, 2 Bagaimana strategi perencanaan pengembangan subsektor tanaman bahan makanan dilihat dari kelengkapan infrastruktur di Kabupaten Boyolali, 3 Bagaimana laju pertumbuhan sektor tanaman bahan makanan yang dimiliki tiap kecamatan di Kabupaten Boyolali. Data yang digunakan adalah data sekunder. Metode analisis data menggunakan analisis Location Quotient (LQ, Shift Share (SS, Klassen Typologi. Berdasarkan hasil penelitian dengan menggunakan analisis Location Quotient (LQ diketahui pengembangan komoditas padi terdapat di Kecamatan Ngemplak, Kecamatan Banyudono, Kecamatan Sawit. Komoditas tanaman jagung terdapat di Kecamatan Selo, Kecamatan Ampel, Kecamatan Cepogo dan Kecamatan Musuk. Komoditas ubi kayu di Kecamatan Klego, kecamatan Simo. Komoditas ubi jalar di Kecamatan Selo, Kecamatan Simo dan Kecamatan Mojosongo. Komoditas kacang tanah ada di Kecamatan Boyolali dan Kecamatan Nogosari. Komoditas kedelai di Kecamatan Juwangi, Kecamatan Sambi, Kecamatn Kemusu dan Kecamatan Wonosegoro. The problems that were in this research is 1 Commodities food plants seed material what it was in each carpel kecamatan in kabupaten boyolali, 2 how strategy sub planning the development of the food crops sector seen from the completeness of the infrastructure in boyolali district, 3 how sector growth rate of plants of food material possessed every sub-district in boyolali district. The data used was secondary data. Data analysis methods using analysis loqation quotient (LQ, shift share (SS, klassen typologi . According to the research using analysis loqation quotient (LQ development rice is in in ngemplak, in banyudono, in palm. Corn is crops in district violoncello, in ampel, in cepogo and in musuk. Commodities cassava in district klego, in simo. Commodities sweet potatoes in in violoncello, in simo and

ANALISIS SPASIAL FAKTOR LINGKUNGAN PADA KEJADIAN DEMAM BERDARAH DENGUE DI KECAMATAN GENUK

Directory of Open Access Journals (Sweden)

Kartika Kirana

2017-10-01

Full Text Available ABSTRAK Kecamatan Genuk merupakan salah satu kecamatan yang endemis DBD di Kota Semarang. Secara berturut-turut sejak tahun 2012 hingga 2014, Kecamatan Genuk masuk sebagai tiga besar kasus DBD terbanyak. Salah satu faktor yang mempengaruhi kejadian DBD adalah faktor lingkungan. Tujuan penelitian ini adalah untuk mengetahui gambaran dari hasil analisis spasial faktor lingkungan dengan kejadian DBD di Kecamatan Genuk. Jenis penelitian ini deskriptif dengan pendekatan kuantitatif. Fokus penelitian ini adalah kondisi SPAL, penumpukan ban bekas dan sumur gali. Penelitian ini dilakukan di Kecamatan Genuk (Kelurahan Genuksari, Karangroto, Bangetayu Kulon dan Banjardowo pada bulan Maret 2016. Instrumen meliputi lembar observasi, peta lokasi, Global Positioning System (GPS, alat fotografi dan AcrGIS. Analisis data menggunakan SIG. Hasil penelitian menunjukkan bahwa kejadian DBD menggerombol pada beberapa RW yang berdekatan dengan keberadaan penumpukan ban bekas sekitar permukiman dan sumur gali terbuka.   Kata Kunci        : demam berdarah (DBD, lingkungan, analisis spasial     ABSTRACT Genukis one of dengue fever endemic district in Semarang city. Since 2012 until 2014, Genuk involve as the place that has high incidence of Dengue Fever. One of the factors in the incidence Dengue Fever areenvironmental factors.The goals of this research wasto analize spatial environmental factorsin the incidence Dengue Fever in Genukdistrict. This was a quantitative descriptive research with descriptive survey. The unit this research was water puddle on the pilling of the tire, the dug wells, and waste water pipeline that located in Genuk District (Subdistrict of Genuksari, Karangroto, Bangetayu Kulon and Banjardowo at March 2016. The instruments were paper of observation,the  map, GPS, camera and ArcGIS. Data was analyzed with GIS. The study showed that dengue fever transmission was inthe area with pilling of the tire, and the dug wells.   Keywords �

WATER BOILER REACTOR

Science.gov (United States)

King, L.D.P.

1960-11-22

As its name implies, this reactor utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical reactor vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the reactor vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the reactor vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.

Profiling, analisi delle prestazioni e proposte per l'ottimizzazione del RDBMS MySQL utilizzato dal progetto DIRAC/LHCbDIRAC

CERN Document Server

Mesin, Alberto

Il lavoro presentato in questa tesi riguarda lo studio, l'analisi e la formula- zione di proposte per il miglioramento del database di back-end del progetto DIRAC/LHCbDIRAC. LHCbDIRAC, basato su DIRAC, e il sistema di sot- tomissione per l'accesso all'infrastruttura distribuita Grid per l'esperimento LHCb del CERN. Ad esso e adata la gestione dei job di Produzione, Mer- ge, Ricostruzione degli Eventi e Analisi per i dati sperimentali e simulati. Il sistema utilizza un RDBMS MySQL per la gestione di numerosi databa- se. La volonta di passare ad un motore relazionale e transazionale per la denizione schemi e la possibilita che, in un recente futuro, il DBMS possa rappresentare un serio limite alle prestazioni del sistema stesso hanno reso necessario questo studio. Il lavoro svolto si e concentrato sul proling di un singolo schema relazionale per il quale sono stati utilizzati metodi di analisi e fornite soluzioni ai problemi riscontrati il quanto piu possibile generali e per tanto validi per l'intero sistema. L...

Il difficile cammino dell’analisi musicale in Italia

Directory of Open Access Journals (Sweden)

Claudio Annibaldi

2014-10-01

Full Text Available Si immaginino gli atti d’un convegno sull’analisi musicale che abbia avuto luogo in un paese come la Francia, la Germania, l’ Inghilterra o gli Stati Uniti. Potrebbe mai accadere che essi vengano pubblicati sostituendo il discorso ufficiale d’apertura dei lavori con un testo tutto nuovo epperò simulante d’esser quello effettivamente pronunciato dall’autore? E potrebbe mai accadere - essendo costui un noto critico musicale e il direttore della collana editoriale comprendente gli atti in questione - che questo nuovo testo sia da lui dedicato a uno sfoggio della propria competenza analitica capace solo di esibire una visione dilettantesca della tecnica musicale tout court? Penso proprio di no. Eppure questo è accaduto in Italia non molti anni fa, quando le Edizioni Unicopli pubblicarono, nella collana dei "Quaderni di Musica/Realtà", gli atti di un convegno sull’analisi musicale tenuto nel 1989 a Reggio Emilia: il primo del genere negli annali della musicologia italiana. L’episodio rende bene l’idea dei pericoli incombenti sul cammino di quegli studiosi che, a far data dal convegno suddetto, si sono adoperati a che la pratica analitica acquisisse anche da noi la dignità scientifica di cui gode, appunto, in paesi come la Francia, la Germania, l’Inghilterra o gli Stati Uniti. Quei pericoli si chiamano ‘dilettantismo tecnico’, ‘arroganza intellettuale’, ‘ vezzo d’ imporre l’uno e l’altra grazie a un qualche tipo di potere personale’, ‘necessità di subire tale imposizione in cambio di qualche vantaggio pratico’.

Regionalization and classification of bioclimatic zones in the central-northeastern region of Mexico using principal component analysis (PCA)

Energy Technology Data Exchange (ETDEWEB)

Pineda-Martinez, L.F.; Carbajal, N.; Medina-Roldan, E. [Instituto Potosino de Investigacion Cientifica y Tecnologica, A. C., San Luis Potosi (Mexico)]. E-mail: lpineda@ipicyt.edu.mx

2007-04-15

Applying principal component analysis (PCA), we determined climate zones in a topographic gradient in the central-northeastern part of Mexico. We employed nearly 30 years of monthly temperature and precipitation data at 173 meteorological stations. The climate classification was carried out applying the Koeppen system modified for the conditions of Mexico. PCA indicates a regionalization in agreement with topographic characteristics and vegetation. We describe the different bioclimatic zones, associated with typical vegetation, for each climate using geographical information systems (GIS). [Spanish] Utilizando un analisis de componentes principales, determinamos zonas climaticas en un gradiente topografico en la zona centro-noreste de Mexico. Se emplearon datos de precipitacion y temperatura medias mensuales por un periodo de 30 anos de 173 estaciones meteorologicas. La clasificacion del clima fue llevada a cabo de acuerdo con el sistema de Koeppen modificado para las condiciones de Mexico. El analisis de componentes principales indico una regionalizacion que concuerda con caracteristicas de topografia y vegetacion. Se describen zonas bioclimaticas, asociadas a vegetacion tipica para cada clima, usando sistemas de informacion geografica (SIG).

Neutron dosimetry. Environmental monitoring in a BWR type reactor; Dosimetria de neutrones. Monitoreo ambiental en un reactor del tipo BWR

Energy Technology Data Exchange (ETDEWEB)

Tavera D, L; Camacho L, M E

1991-01-15

The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

Analisis Algoritma Pergantian Cache Pada Proxy Web Server Internet Dengan Simulasi

OpenAIRE

Nurwarsito, Heru

2007-01-01

Pertumbuhan jumlah client internet dari waktu ke waktu terus bertambah, maka respon akses internet menjadi semakin lambat. Untuk membantu kecepatan akses tersebut maka diperlukan cache pada Proxy Server. Penelitian ini bertujuan untuk menganalisis performansi Proxy Server pada Jaringan Internet terhadap penggunaan algoritma pergantian cache-nya.Analisis Algoritma Pergantian Cache Pada Proxy Server didesain dengan metoda pemodelan simulasi jaringan internet yang terdiri dari Web server, Proxy ...

Analysis and application of a simulator of a nuclear reactor AP-600; Analisis y aplicacion de un simulador de un reactor nuclear AP-600

Energy Technology Data Exchange (ETDEWEB)

Medina S, V. S. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: medina_victor@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Division de Ingenieria Electrica, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (MX)

2011-11-15

In front of the resurgence of interest in the nuclear power production, several national organizations have considered convenient to have highly specialized human resources in the technologies of nuclear reactors of III + and IV generation. For this task, the intensive and extensive applications of the computation should been considered, as the virtual instrumentation. The present work analyzes the possible applications of a nuclear simulator provided by the IAEA with base in the design of the reactor AP-600, using a focusing of modular model developed in FORTRAN. One part of the work that was made with the simulator includes the evaluation of 21 transitory events of operation, including the recreation of the accident happened in the nuclear power plant of Three Mile Island in 1979, comparing the actions flow and the answer of the systems under the intrinsic security of a III + generation reactor. The impact that had the mentioned accident was analyzed in the growing of the nuclear energy sector and in the public image with regard to the nuclear power plants. An application for this simulator was proposed, its use as tool for the instruction in the nuclear engineering courses using it to observe the operation of the different security systems and its interrelation inside the power plant as well as a theoretical/practical approach for the student. (Author)

ANALISIS FAKTOR-FAKTOR YANG MENDORONG WISATAWAN MELAKUKAN KEPUTUSAN PEMBELIAN TIKET PESAWAT MELALUI MOBILE BOOKING PADA SITUS TRAVELOKA.COM

Directory of Open Access Journals (Sweden)

Erni Muliana

2016-07-01

Full Text Available Pembelian kebutuhan perjalanan wisata secara online merupakan bagian dari transaksi business to-customer (B2C. Produk yang ditawarkan biasanya terdiri dari: pemesanan paket wisata, penjualan tiket pesawat dan kereta api, kamar hotel dan penyewaan transportasi. Penelitian dilakukan dengan tujuan untuk mengetahui faktor-faktor yang mendorong wisatawan melakukan keputusan pembelian tiket pesawat melalui mobile booking pada situs Traveloka.com serta faktor yang paling banyak berkontribusi dalam menentukan keputusan pembelian tersebut. Teknik pengumpulan data yang digunakan adalah kuesioner online dan kuesioner yang disebarkan secara langsung (offline kepada 250 responden, penentuan responden ditetapaka menggunakn metode purposive sampling, sedangkan teknik analisis data yang digunakan adalah teknik analisis faktor. Hasil analisis faktor yang didapatakan menjelaskan 67,066% dari keseluruhan total variance, dan hasil analisis data menunjukkan empat faktor terbentuk yang mendorong wisatawan melakukan keputusan pembelian tiket pesawat melalui mobile booking pada situs Traveloka.com, yaitu: kemudahan dan sistem informasi website (24,396 %, pelayanan konsumen/customer service (15,211%, citra perusahaan (14,681 %, dan motivasi pembelian (12,779%, adapun faktor yang paling berkontribusi dalam mendorong wisatawan melakukan keputusan pembelian tiket pesawat melalui mobile booking pada situs Traveloka.com adalah faktor terbentuk yang memiliki faktor laoding tertinggi dari keseluruhan faktor yang terbentuk, yaitu faktor “Kemudahan dan Sistem Informasi Website”, faktor ini terdiri dari 13 variabel yakni: (1 Kemudahan pencarian situs web, (2 kecepatan waktu mengakses (load time, (3 nama domain perusahaan, (4 kemudahan pemesanan, (5 Informasi yang lengkap, (6 Informasi yang akurat, (7 Informasi yang menarik, (8 Pemaparan informasi yang tepat, (9 Ketersediaan dan aksesibilitas, (10 Harga yang kompetitif, (11 Pengalaman secara keseluruhan, (12 Keamanan data

Fuel burn analysis of a sodium fast reactor with KANEXT and Serpent; Analisis de quemado de combustible de un reactor rapido de sodio con KANEXT y SERPENT

Energy Technology Data Exchange (ETDEWEB)

Lopez S, R. C.; Francois L, J. L., E-mail: rcarlos.lope@gmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

2015-09-15

The fast reactors cooled by sodium are one of the options considered in the Generation IV. Since most of the reactors of Fourth Generation are still in development stage, is necessary to have efficient and reliable computational tools, this in order to obtain accurate results in reasonable computational times. In this paper is introduced and describes the deterministic code KANEXT (KArlsruhe Neutronic EXtended Tool) and is compared against a Monte Carlo code of more diffusion: Serpent. KANEXT, being a modular code requires the interaction of different modules to perform a job, this interaction of modules is described in this article. The parameters to be compared are the results of the neutron multiplication effective factor and the evolution of isotopes during the burning. The mentioned comparison is carried out for a fast reactor cooled by sodium of relatively small size compared to commercial size reactors. In this paper the particularities of the reactor are described, important for the analysis such as geometry, enrichments, reflector, etc. The considerations in the implementation in both codes are also described, as are simplifications, length of the burning steps, possible solutions of the Bateman equations for the burning fuel in Serpent and the solution options for transport (P3) and diffusion (P1) in KANEXT. The results show good correspondence between Serpent and KANEXT, which give confidence to continue using KANEXT as the main tool. Respect to computation time, time saving is evident with the use of deterministic codes instead of Monte Carlo codes, in this particular case, the time savings using KANEXT is about 98.5% of the time used by Serpent. (Author)

PENGKLASIFIKASIAN KARAKTERISTIK MAHASISWA BARU DALAM MEMILIH PROGRAM STUDI MENGGUNAKAN ANALISIS CLUSTER

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Maxsi Ary

2016-03-01

Full Text Available Abstract - Object Clustering is one of the object mining process which aims to partition an existing object into one or more cluster objects based on their characteristics. Private Universities is one of the alternatives for the community colleges to meet increased demand for educational needs. The number of private colleges, especially in Bandung and generally in Indonesia is quite a lot. The number of colleges and universities means used to attract prospective students to be an interesting thing to study. As a reason for the intense competition in the search for new students, no doubt there are some ways that actually do not need to be done. Issues raised, namely classify new students of characteristics in selecting a course using cluster analysis. Data obtained from the questionnaire prospective new students in February 2014 Data processing using SPSS. The results using analysis SPSS aiming easier to describe the characteristics of each group of new students in choosing courses. Keywords: Clustering, characteristics of students, courses, cluster analysis Abstrak - Pengelompokan Objek (object clustering adalah salah satu proses dari objek mining yang bertujuan untuk mempartisi objek yang ada kedalam satu atau lebih cluster objek berdasarkan karakteristiknya. Perguruan tinggi swasta merupakan salah satu perguruan tinggi alternatif bagi masyarakat untuk menghadapi peningkatan permintaan terhadap kebutuhan pendidikan. Jumlah perguruan tinggi swasta khususnya di Bandung dan umumnya di Indonesia berjumlah cukup banyak. Jumlah perguruan tinggi dan cara yang digunakan perguruan tinggi untuk menarik minat calon mahasiswa menjadi hal yang menarik untuk dikaji. Sebagai alasan ketatnya persaingan dalam mencari calon mahasiswa baru, tidak dipungkiri terdapat beberapa cara yang dilakukan yang sebetulnya tidak perlu dilakukan. Persoalan yang dikemukakan yaitu mengklasifikasikan karakteristik mahasiawa baru dalam memilih program studi menggunakan analisis

10 years Institute for Reactor Development

International Nuclear Information System (INIS)

1975-05-01

Ten years ago the Institute of Reactor Development was founded. This report contains a review about the research work of the institute in these past ten years. The work was mainly performed within the framework of the Fast Breeder Project, the Nuclear Safety Project and Computer Aided Design. Especially the following topics are discussed: design studies for different fast breeder reactors, development works for fast breeders, investigations of central safety problems of sodium cooled breeder reactors (such as local and integral coolant disturbances and hypothetical accident analysis), special questions of light water reactor safety (such as dynamic stresses in pressure suppression systems and fuel rod behaviour under loss of coolant conditions), and finally computer application in various engineering fields. (orig.) [de

FBR type reactor

International Nuclear Information System (INIS)

Inoue, Kotaro; Kawashima, Katsuyuki; Zuketen, Atsushi.

1982-01-01

Purpose: To flatten the power distribution of a reactor core and shorten the breeding time. Constitution: The reactor core comprises a core region having fission products, an outer blanket region surrounding the outer side of the core region and having fertile material and an inner blanket region disposed within the core region and having fertile material. The axial thickness of the inner blanket region is made greater at the central portion and smaller at the peripheral portion of the inner blanket region, and the outermost peripheral end at the peripheral portion of the inner blanket region is opposed by way of the core region to the outer blanket region. In such an arrangement, the power decrease in the peripheral portion of the core region can be suppressed to thereby flatten the power distribution in the reactor core and shorten the breeding time. (Moriyama, K.)

The safety of the fast reactor

International Nuclear Information System (INIS)

Matthews, R.R.

1977-01-01

Verbatim of an address by R.R. Matthews, Chief Nuclear Health and Safety Officer, UK Central Electricity Generating Board given on January 15th 1977. The object of this address was to give some opinions on the safety issues of fast reactors as seen from an operational point of view. An outline of the basic responsibilities for nuclear safety is first given, and it is emphasized that the Central Electricity Generating Board has a statutory responsibility for the safe operation of its nuclear plant. The Nuclear Installations Act places absolute responsibility on the operator for ensuring that injury to persons and damage to property do not occur, and the new Health and Safety at Work Act does likewise. In addition the Board has a Nuclear Health and Safety Department that has to ensure that adequate provision for safety is made in the design, construction, and operation of nuclear plant, and safety at operational stations is monitored continuously by inspectors. In addition the requirements of the Nuclear Installations Inspectorate, laid down in the site licence conditions, must be satisfied. All these requirements are here discussed in the light of application to commercial fast reactors. It is considered that the hazards to fast reactor operating personnel are small and little different from those of other types of reactor, and in some respects the fast reactor has advantages, particularly in regard to the use of a Na coolant. The possibility of various types of accident is considered. Radioactive effluent discharge is also considered. The fast reactor as an international problem is discussed, including security matters. The extensive experience gained in operation of the experimental and prototype fast reactors at Dounreay is emphasized. (U.K.)

Stability analysis of a recycling circuit of a BWR type reactor. Theoretical study; Analisis de estabilidad de un circuito de recirculacion de un reactor del tipo BWR. Estudio teorico

Energy Technology Data Exchange (ETDEWEB)

Salinas H, J.G.; Espinosa P, G. [Universidad Autonoma Metropolitana-Iztapalapa, 09000 Mexico D.F. (Mexico); Gonzalez M, V.M. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 04000 Mexico D.F. (Mexico)

2000-07-01

The Technology, Regulation and Services Management of the National Commission of Nuclear Safety and Safeguards financed and in coordinate form with the I.P.H. Department of the Metropolitan Autonomous-Iztapalapa University developed the present project with the purpose of studying the effect of the recycling system on the linear stability of a BWR reactor whose reference central is the Laguna Verde power station. The present project forms part of a work series focused to the linear stability of the nuclear reactor of the Unit 1 at Laguna Verde power station. The components of the recycling system considered for the study of stability are the recycling external circuit (recycling pumps, valves) and the internal circuit (downcomer, jet pumps, lower full, driers, separators). The mathematical model is obtained applying mass balances and movement quantity in each one of the mentioned circuits. With respect to the nucleus model two regions are considered, the first one is made of a flow in one phase and the second one of a flow in two phases. For modelling the biphasic region it is considered homogenous flow. Generally it is studied the system behavior in the frequency domain starting from the transfer function applied to four operational states which correspond to the lower stability zone in the map power-flow of the Unit 1 of Laguna Verde power station. The Nyquist diagrams corresponding to each state as well as their characteristic frequency were determined. The results show that exists a very clear dependence of the power-flow relation on the stability of the system. It was found that the boiling length is an important parameter for the linear stability of the system. The obtained results show that the characteristic frequencies in unstability zones are similar to the reported data of the Unit 1 of the Laguna Verde power station in the event of power oscillations carried out in January 1995. (Author)

Proceedings of the International Conference Nuclear Energy in Central Europe 2001

International Nuclear Information System (INIS)

Jencic, I.; Glumac, B.

2001-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 98 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: reactor physics, thermal hydraulics, probabilistic safety assessment (PSA) and severe accidents, nuclear materials, NPP and research reactor operation, environmental issues and radiation measurement, fusion, radioactive waste and regulatory issues and public relations

ANALISIS KELAYAKAN FINANSIAL WISATA AIR WADUK JATIGEDE KABUPATEN SUMEDANG

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Bambang Susanto

2016-04-01

pendahuluan agar manfaatnya jauh lebih besar dari biaya yang dikeluarkan. Oleh sebab itu untuk kepentingan ilmiah perlu dilakukan kajian akademisnya berupa Analisis kelayakan Finansial. Berdasarkan analisis kelayakan keuangan   ,dapat  disimpulkan bahwa wisata air di Waduk jatigede Kabupaten Sumedang  memberikan manfaat yang lebih dibandingkan dengan biaya yang dikeluarkan . ini dapat dilihat dari hasil analisis net present value yang positif, internal rate of return yang lebih besar dari tingkat bunga bank serta benefit cost yang lebih besar dari satu. Kata Kunci: Kelayakan Finansial; Wisata Air.

ANALISIS PENGEMBANGAN POTENSI EKONOMI DAERAH DI KAWASAN BANGLOR TAHUN 2007-2011

Directory of Open Access Journals (Sweden)

Abdul Bakhirnudin

2013-11-01

Full Text Available Abstrak ___________________________________________________________________ Kawasan Banglor merupakan salah satu Kawasan di Provinsi Jawa Tengah yang memiliki tingkat pertumbuhan yang paling rendah dan terletak jauh lebih rendah dibandingkan dengan kawasan lainnya. Diantara kawasan-kawasan lainnya hanya kawasan Banglor sajalah yang memiliki pertumbuhan di bawah 4 persen yaitu 3,5 dan hal tersebut terletak jauh dibawah rata-rata dengan nilai rata-rata sebesar 4,89 persen pada tahun 2011. Sedangkan untuk kawasan lainnya memiliki pertumbuhan diatas 4 persen pada tahun 2011. Populasi penelitian ini adalah PDRB Kabupaten Rembang dan Blora atas dasar harga konstan tahun 2000, sedangkan sampel penelitian ini adalah PDRB Kab. Rembang dan Blora serta Jawa Tengah tahun 2007-2011 atas dasar harga konstan tahun 2000. Variabel yang dikaji dalam penelitian ini yaitu PDRB, pertumbuhan ekonomi, sektor-sektor ekonomi, penduduk, komponen Shift Share, dan SWOT. Metode pengumpulan data yang digunakan adalah metode dokumentasi dan kuesioner. Dalam penelitian ini digunakan analisis SLQ, DLQ dan Shift Share guna menentukan potensi ekonomi daerah yang dapat dijadikan sektor basis atau sektor unggulan. Selain itu penelitian ini juga bertujuan mengetahui tingkat ketimpangan antar daerah dalam kawasan Banglor. Berdasarkan analisis LQ dan Shift Share dapat diketahui potensi ekonomi daerah di kabupaten dalam kawasan Banglor, yaitu sektor industri pengolahan, sektor pertambangan dan penggalian, sektor Listrik,Gas, dan Air bersih, sektor perdagangan, hotel dan restoran di Kabupaten Rembang. Sedangkan di Kabupaten Blora Potensi Ekonomi Daerahnya adalah sektor Pertambangan dan Penggalian, sektor Industri Pengolahan, sektor perdagangan, hotel dan restoran, sektor Keuangan, Persewaan dan jasa perusahaan serta sektor Listrik,Gas, dan Air bersih. Selanjutnya digunakan analisis SWOT guna menganalisis strategi kebijakan pengembangan sektor Industri Pengolahan, sektor Perdagangan

Metode Pengumpulan dan Analisis Data : Lang Kah Vital Proses Penelitian

OpenAIRE

Suprapto, Agus .

2005-01-01

The process of data collection and. analysis is one of chains in scientific method that should be done in a research. This part later on will determine the right method in searching and analyzing a way in solving a problem. The data collected should be the ones which are relevant which the essence of research problems, so that the next interpreted data will eventually be concluded as valid. keywords: Pengumpulan data, analisis data,dan metode ilmiah

Economical analysis to utilize MTR fuel elements using silicides in research reactors; Analisis economico sobre el uso de elementos combustibles MTR a base de siliciuros en reactores de investigacion

Energy Technology Data Exchange (ETDEWEB)

Bergallo, Juan E; Novara, Oscar E; Adelfang, Pablo [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Combustibles Nucleares

2000-07-01

According to international programs on reducing enrichment in research reactors and the necessity to maintain their operation, new fuel elements have been developed in order to meet both objectives. Thus, U-Si alloy fuel elements for research reactors are becoming of greater interest for the international markets. It became necessary to make an economic study about the convenience of introducing this type of fuel elements in the RA-3 reactor and to know the potentiality of this fuel. The economical behavior of the reactor operation has been evaluated comparing the actual U{sub 3}O{sub 8} nuclear fuel cycle with U{sub 3}Si{sub 2} nuclear fuels. Results obtained show that the main economical factor to determine the change of fuels is the cost of fabrication, and the change is advisable up to an 80% difference. The other factors related to the cost of nuclear fuel cycle are not relevant or have real minor impacts. (author)

Measurement of the physics properties of gas-cooled fast reactors in the zero energy reactor PROTEUS and analysis of the results

International Nuclear Information System (INIS)

Richmond, R.

1982-12-01

The main aim of the fast reactor physics measurements carried out in the zero energy reactor PROTEUS was to check the performance of data sets and calculation methods used in the design of fast breeder reactors. This allowed the accuracy of the power reactor calculations to be determined and enabled an assessment to be made of whether this accuracy would be sufficient to allow the design, construction and licensing of the GCFR power reactor. In order to carry out the physics measurements an existing zero energy reactor was converted to a form in which a central fast reactor lattice was surrounded by thermal zones to drive the reactor critical. One of the most important measuring techniques used to check the performance of data sets and calculation methods was the determination of reaction rate ratios and, by using an appropriate range of nuclides, it was possible to obtain a detailed picture covering 70% of reactions taking place in the central part of the fast reactor zone and with an accuracy of +-1.5% in a typical ratio. A further technique used during the work on GCFR-PROTEUS was the measurement of neutron spectrum which was carried out in a wide range of environments and, in the later stages of the work, covered the energy range from 9 keV to 2.3 MeV. These measurements, in particular, indicated significant errors in the FGL4 scattering cross-sections. A third technique, which was developed to a high degree of accuracy, was the measurement of reactivity worths. This was used in measurements of the worths of small samples and also in the application of the null reactivity technique to determine k-infinity and hence the absorption cross-sections of reactor structural materials. (Auth.)

MLR reactor

International Nuclear Information System (INIS)

Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

1998-01-01

The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

Fuel analysis of a PBMR; Analisis de combustible de un PBMR

Energy Technology Data Exchange (ETDEWEB)

Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

2015-09-15

In this paper a neutronic analysis of fuel for a Pebble Bed Modular Reactor is presented, based on their composition and geometric distribution, having as main objective the use and utilization of thorium for the production of fuel for the operation of this reactor. For the study of these characteristics is necessary to use a code capable of carry out a reliable calculation of the main parameters of the fuel. Using the Monte Carlo method is suitable for simulating the neutron transport in the reactor core, which is the basis of Serpent code, with which the calculations for the analysis will be made. The results show the desirability of the use of thorium, since presents good conversion levels of fertile material to fissile, to produce U{sup 233} by neutron capture, taking as a very important factor the distribution of materials in the core, which in this work had better results based on the neutron multiplication effective factor, formed by three right circular cylinders circumscribed, making that the core has three areas constituted by a mixture of plutonium oxide in the central and external areas, and thorium oxide in the intermediate area. (Author)

Text Mining Untuk Analisis Sentimen Review Film Menggunakan Algoritma K-Means

OpenAIRE

Setyo Budi

2017-01-01

Kemudahan manusia didalam menggunakan website mengakibatkan bertambahnya dokumen teks yang berupa pendapat dan informasi. Dalam waktu yang lama dokumen teks akan bertambah besar. Text mining merupakan salah satu teknik yang digunakan untuk menggali kumpulan dokumen text sehingga dapat diambil intisarinya. Ada beberapa algoritma yang di gunakan untuk penggalian dokumen untuk analisis sentimen, salah satunya adalah K-Means. Didalam penelitian ini algoritma yang digunakan adalah K-Means. Hasil p...

ANALISIS KEAMANAN DATA PADA BLOCK CIPHER ALGORITMA KRIPTOGRAFI RSA

Directory of Open Access Journals (Sweden)

Fadhillah Azmi

2017-01-01

Full Text Available Komunikasi adalah proses dasar dari pertukaran informasi. Efektifitas komunikasikomputer secara umum adalah melalui internet atau beberapa saluran komunikasi lainnya.Tujuan utama tulisan ini adalah berdasarkan pada analisis hasil yang diberikan Weinermengatakan bahwa jika private key d digunakan dalam algoritma kriptografi RSA kurang darin292, maka sistem tersebut kurang aman. Di sini penulis menganalisa pada hasil yang diberikanoleh Weiner dan mencoba untuk meningkatkan range dari private key d sampai n0.5. Karena nadalah perkalian p dan q, yang mana bilangan relative prima. Sehingga mempengaruhi kinerjaenkripsi algoritma yang lebih aman.

Optimal operating parameters of the reactor oscillator in the channel of 6.5/10 MW reactor; Odredjivanje optimalnih radnih tacaka za reaktorski oscilator u kanalu na reaktoru 6,5/10 MW

Energy Technology Data Exchange (ETDEWEB)

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

1961-07-01

Operating conditions for the reactor oscillator in the central vertical experimental channel (VK5) in the RA reactor were studied during 1960. Channel VK5 was chosen because the sensitivity of the reactor is highest in this case. The central vertical experimental channel is placed in the center of the core and its bottom is placed 200 mm from the bottom of the reactor core. Diameter of the channel is is 110 mm and its length 5706 mm. During operation of the reactor oscillator with total modulation of the reactor power, it is very important to determine the oscillator operating point and the oscillation amplitude in such a way to avoid any change in reactor power level. Positive reactivity changes originating from oscillations of the samples should be compensated by the negative reactivity changes so that the effect should be nil. Operating points of the reactor oscillator are in the middle of the straight part of the figure showing the reactivity change dependent on the position of the absorber.

Reproduction of the PSBR reactor with Exterminator-2; Reproduccion del reactor PSBR con exterminador-2

Energy Technology Data Exchange (ETDEWEB)

Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1983-08-15

To reproduce the reactor PSBR reported in (1), with the available version of the Exterminator-II in the ININ, they took the dimensions, composition specifications, effective sections of the different compositions (excepting those of the central thimble and of the moderator), the K{sub eff} and the factors of power (FP) for the different burners. Based on the comparison of the K{sub eff} and of the FP obtained with those reported the precision it is determined before in the reproduction of the reactor mentioned. (Author)

ANALISIS SOAL JENJANG KOGNITIF TAKSONOMI BLOOM REVISI PADA BUKU SEKOLAH ELEKTRONIK (BSE BIOLOGI SMA

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Aa Juhanda

2016-11-01

Penelitian ini bertujuan untuk menganalisis kemunculan soal jenjang kognitif Bloom Revisi pada Buku Sekolah Elektronik (BSE Biologi SMA. Subjek penelitian adalah 1.650 soal yang terdapat pada BSE Edisi 2009. Instrumen yang digunakan adalah lembar analisis dokumen yang di dalamnya memuat informasi seperti kode soal, soal, dan jenis tingkatan kognitif taksonomi Bloom Revisi. Analisis data dilakukan secara kuantitatif dan kualitatif. Hasil penelitian menunjukkan bahwa rerata persentase kemunculan cukup tinggi diperoleh pada soal yang mengembangkan keterampilan berpikir tingkat rendah (Lower-Order Thinking Skills yaitu soal C1 (mengingat sebesar 46,60% dan C2 (memahami sebesar 47,99%, meskipun untuk C3 (menerapkan persentasenya masih rendah (0,28%. Rerata persentase kemunculan soal yang mengembangkan keterampilan tingkat tinggi (Higher-Order Thinking Skills mulai dari soal C4 (menganalisis sampai dengan C6 (mencipta memiliki rerata persentase yang rendah. Oleh karena itu, kemunculan soal jenjang kognitif Bloom Revisi pada BSE khususnya yang mengembangkan Higher-Order Thinking Skills masih perlu untuk ditingkatkan.

Deteksi Kerusakan Batang Rotor Pada Motor Induksi Menggunakan Analisis Arus Mula Berbasis Hilbert Transform

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Isti Qomah

2017-01-01

Full Text Available Kerusakan batang rotor merupakan salah satu jenis kerusakan pada motor induksi yang dapat menyebabkan masalah serius. Kerusakan tersebut dapat mencapai 5% - 10% dari seluruh kasus gangguan motor induksi. Oleh karena itu, perlu adanya diagnosis awal yang mendeteksi adanya gangguan pada rotor motor induksi, agar dapat dilakukan perbaikan lebih cepat dan tanggap sebelum terjadi gangguan yang lebih besar. Tugas Akhir ini membahas terkait teknik deteksi kerusakan batang rotor pada motor induksi dengan menggunakan analisis arus mula. Sistem yang digunakan berbasis  decomposition wavelet transform terlebih dahulu kemudian dilanjutkan dengan analisis berbasis hilbert transform sebagai perangkat pengolahan sinyal sehingga mampu mendeteksi motor dalam keadaan sehat atau mengalami kerusakan. Pengujian sistem dilakukan dalam beberapa kondisi, yaitu kondisi tanpa beban dan berbeban. Selain itu, kondisi yang diberikan adalah kecacatan mulai dai 1BRB hingga 3BRB. Hasil pengujian membuktikan bahwa decomposition wavelet transform dan Hilbert transform mampu mendeteksi perbedaan kondisi pada motor induksi normal ataupun rusak pada batang rotor.

International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Gortnar, O; Stritar, A [Nuclear Society of Slovenia (Slovenia)

1999-07-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations.

International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

International Nuclear Information System (INIS)

Gortnar, O.; Stritar, A.

1999-01-01

International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations

Analisis Arus Kas Terkait Kebijakan Uang Kuliah Tunggal di Perguruan Tinggi Negeri Badan Hukum

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Surtiati Surtiati

2017-05-01

Full Text Available The aims of the research were to analyze cash flow and compare tuition income in a State University with Legal Entity of “XYZ” for its first year TPB students (the First Common Year and of the first year until the fourth year before and after implementation of the single tuition fee system and formulate the management policies for the tuition income after the single tuition fee system. Analysis of cash flows consisted of cash ratio, quick ratio and current ratio. Paired t-test was used to analyze differences between single tuition fee income and non single tuition fee income. Based on the cash flow analysis, it is found that the University of “XYZ” has a liquid financial condition. The significant difference is, moreover, detected from the paired t-test analysis between single and non single tuition fee of total income from the first year student tuition. However, there is no difference detected when the analysis was conducted for total income from all four year tuitions. Management policies tuition income after the single tuition fee system payment delays should be minimized so that tuition fee funds can be completely collected. The allocation of fees to the faculty/department was originally based on the BPMP, and BPMK uses a tariff system so that cost per subject does not necessarily correspond with the needs. This is not in accordance with the single tuition fee system that is based on the unit cost. This means that the cost of the course is based on real needs, not based on the rates set.Keywords: cash flow analysis, state university with legal entity, single tuition feeABSTRAKPenelitian ini bertujuan menganalisis arus kas, mengkaji perbedaan penerimaan SPP S1 Reguler satu tahun pertama bagi mahasiswa TPB dan tahun pertama sampai tahun ke empat sebelum dan sesudah kebijakan UKT di PTN Badan Hukum “XYZ. Selanjutnmya, merumuskan kebijakan pengelolaan SPP S1 reguler sesudah UKT. Analisis arus kas terdiri dari rasio kas, rasio cepat

ANALISIS DEREPLIKASI UNTUK IDENTIFIKASI SENYAWA ANTIBAKTERI SPONGE Axinella sp. DARI PERAIRAN KEPULAUAN KARIMUNJAWA

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Hedi Indra Januar

2009-06-01

Full Text Available Riset ini bertujuan untuk mengidentifikasi senyawa antibakteri pada Axinella sp. yang diambil dari kepulauan Karimunjawa dengan metode dereplikasi menggunakan LCMS (Liquid Chromatography Mass Spectrometer dan FT-MS (Fourier Transfer Mass Spectrometer. Data pola spektra massa dan LC-MS menunjukkan adanya tiga senyawa terbrominasi yang mungkin memiliki bioakfivitas antibakteri. Analisis massa akurat (limit kesalahan di bawah 20 ppm menggunakan FT-MS menemukan bahwa ketiga senyawa tersebut memliki monosotop negatif (M-H pada m/z 321,9931 [senyawa (a]; m/z 383,9089 [senyawa (b]; dan m/z 385,9249 [senyawa (c]. Analisis komposisi kimia dari besaran massa tersebut yang menggunakan Elemental Composition Calculator menemukan bahwa komposisi kimia dari ketiga senyawa tersebut adalah C11H10N5O2Br (a, C11H9N5Br2 (b dan C11H11Br2N5O (c. Penelusuran struktur kima yang didasarkan pada komposisi tersebut di database MarinLit 2008 (Database struktur kimia senyawa-senyawa dari biota laut menemukan bahwa ketiga senyawa tersebut merupakan hymeniadisine (a, 3-bromohymenialdiside (b, dan dibromophakelin (c.

Analisis interferensi T-DAB dan TV Analog pada pita Very High Frequency (VHF

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Kasmad Ariansyah

2014-09-01

Full Text Available Kehadiran teknologi digital telah membawa perubahan di dalam berbagai aspek kehidupan, tak terkecuali di dunia penyiaran. Digitalisasi dibidang penyiaran diyakini dapat memberikan manfaat dalam hal efisiensi spektrum frekuensi radio. Berkaitan dengan penyiaran radio, Menteri  Komunikasi  dan  Informatika telah menetapkan DAB family sebagai standard penyiaran radio digital di Indonesia. Kajian dilakukan untuk mendapatkan jarak minimum yang diperlukan  antara sistem T-DAB dan TV analog sebagai solusi terhadap kemungkinan interferensi. Analisis dilakukan dengan bantuan SEAMCAT. Berdasarkan hasil analisis disimpulkan bahwa  kanal  A  T-DAB  merupakan  kanal yang paling rentan terhadap interferensi; Untuk mencapai probabilitas interferensi maksimum 5%, separasi geograpis minimum antara cakupan terluar TV analog kanal n dan transmitter terluar pada jaringan SFN T-DAB untuk kanal (n- 1D, nA, nB, nC berturut-turut adalah 220 Km, 290 Km, 145 Km dan  40  Km.  Sedangkan  untuk  kanal  nD  dan  (n+1A  dapat dioperasikan tanpa separasi geograpis dengan TV analog.

ANALISIS CURAH HUJAN PANTAI BARAT SUMATERA BAGIAN UTARA PERIODE 1994-2007

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Indra Gustari

2009-07-01

Full Text Available Dari data curah hujan di pantai barat Sumatera bagian utara dilakukan analisis spektrum daya untuk mengetahui pola curah hujan di daerah tersebut, selanjut dilihat hubungannya dengan intensitas monsun,  Indian Ocean Dipole Mode (IODM dan El-Nino Southern Oscillation (ENSO. Hasil analisis menunjukkan bahwa pola curah hujan di pantai barat Sumatera bagian utara memiliki dua puncak dan sangat dipengaruhi oleh faktor cuaca dengan dengan osilasi satu tahunan (annual oscillation, dan setengah tahunan (semi-annual oscillation dan ditemukan hubungan yang kuat antara variabilitas monsun dan IODM. Pola hujan didaerah ini tidak memperlihatkan pengaruh ENSO.   The data of Rainfall in the west coast of northern Sumatera were analyzed through power spectrum analyzer to find out the rainfall pattern in that area and to look at the relationship between rainfall pattern and monsoon intensity, Indian Ocean Dipole Mode (IODM and El-Nino Southern Oscillation (ENSO. The result of this analysis shows that the main rainfall pattern in the west coast of northern Sumatera has two peaks and is very much influenced by the factor of weather with annual oscillation and semi-annual oscillation, there is a strong relationship between monsoon variability and IODM, and the influence of ENSO on the rainfall in this region is not significant.

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.

Modeling atmospheric dispersion for reactor accident consequence evaluation

International Nuclear Information System (INIS)

Alpert, D.J.; Gudiksen, P.H.; Woodard, K.

1982-01-01

Atmospheric dispersion models are a central part of computer codes for the evaluation of potential reactor accident consequences. A variety of ways of treating to varying degrees the many physical processes that can have an impact on the predicted consequences exists. The currently available models are reviewed and their capabilities and limitations, as applied to reactor accident consequence analyses, are discussed

SOLASE: a conceptual laser fusion reactor design

International Nuclear Information System (INIS)

Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

1977-12-01

The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion ractors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

ANALISIS PENGARUH CUSTOMER RELATIONSHIP MANAGEMENT TERHADAP KEPUASAN PELANGGAN PADA PT TELKOMSEL DI MAKASSAR

OpenAIRE

ANANDA, RACHMA RESKY

2015-01-01

2015 Analisis Pengaruh Customer Relationship Management Terhadap Kepuasan Pelanggan Pada PT Telkomsel di Makassar Analysis of Customer Relationship Management Influence to Customer Satisfaction at PT Telkomsel in Makassar Rachma Resky Ananda Muh. Asdar Yansor Djaya Tujuan dari penelitian ini adalah untuk menganalisis pengaruh Customer Relationship (continuity marketing, one to one marketing dan partnering atau co-marketing) terhadap k...

Method of inspecting the function of reactor noise monitoring device

International Nuclear Information System (INIS)

Yamanaka, Hirohito.

1985-01-01

Purpose: To enable to inspect the function of a reactor noise monitoring device used for monitoring the operation abnormality in coolant circuits during reactor operation. Constitution: A cylinder incorporating a steel ball moved laterally by a pneumatic pressure is disposed to the main body of a reactor coolant circuit. A three-way solenoid valve disposed to a central control room outside to a radiation controlled area is connected with the cylinder by way of pneumatic pipeways. The three-way solenoid valve is operated for a certain period of time by a timer in the central control room to thereby impinge the steel ball in the cylinder against the main body of the coolant circuit and it is inspected as to whether the reactor noise monitoring system can detect the impinging energy or not. Accordingly, the remote control is possible from out of the radiation controlled area and the inspection work can be simplified. (Seki, T.)

KERAGAAN WARNA IKAN CLOWN BIAK (Amphiprion percula POPULASI ALAM DAN BUDIDAYA BERDASARKAN ANALISIS GAMBAR DIGITAL

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Ruby Vidia Kusumah

2015-09-01

Full Text Available Penelitian ini bertujuan untuk mengkaji keragaan warna ikan clown Biak (Amphiprion percula populasi alam dan budidaya berdasarkan analisis gambar digital sebagai dasar upaya pemuliaannya. Gambar digital diambil dari koleksi ikan clown Biak Balai Besar Perikanan Budidaya Laut Lampung, Balai Besar Penelitian dan Pengembangan Budidaya Laut Gondol, Bali; serta pengumpul ikan hias di Denpasar, Bali menggunakan kamera digital Canon EOS 600D. Pola warna dikarakterisasi secara visual terhadap variasi strip hitam dan putih pada dasar badan oranye, jenis warna dianalisis menggunakan ImageJ 1.49s, persentase penutupan warna dilakukan dengan Adobe Photoshop CS5. Pola warna dikarakterisasi oleh strip hitam tebal, tipis, gelap, pudar, terputus, bergabung, serta strip putih normal, pelana, spot, melebar, dan terputus. Warna hitam alam dikarakterisasi oleh hue (H: 300-60º, saturation (S: 8%-56%, brightness (B: 3%-19%, sedangkan budidaya H: 300-23º, S: 9%-71%, B: 4%-20%. Warna oranye alam H: 19-33º, S: 88%-98%, B: 47%-85%, dan budidaya H: 14-29º, S: 86%-99%, B: 38%-82%. Warna putih alam H: 36-270º; S: 1%-13%, B: 66%-88%, dan budidaya H: 0-229º, S: 0%-14%, B: 55%-87%. Persentase penutupan warna badan didominasi warna oranye dengan rata-rata 45% untuk populasi alam dan 57% untuk populasi budidaya. Keragaan warna ikan clown Biak dapat diarahkan pada pembentukan strain misbar, picasso, spot (domino, dan onyx. Metode analisis gambar digital sangat potensial digunakan untuk analisis keragaan warna ikan hias.

Analisis Kelembagaan Rantai Pasok Telur Ayam Ras Peternakan Rakyat Di Jawa Barat

OpenAIRE

Sejati, Wahyuning K

2011-01-01

Dalam konteks pengembangan pasar komoditas dan peningkatan kesejahteraan peternak rakyat perlu dipahami secara baik karakteristik dan kelembagaan petani, pemasok, dan pasar. Tulisan ini bertujuan untuk menganalisis kelembagaan rantai pasok peternak-pemasok-pasar komoditas telur ayam ras yang meliputi: (1) identifikasi kelembagaan peternakan rakyat ayam ras petelur; (2) analisis kelembagaan rantai pasok komoditas telur; dan (3) antisipasi kelembagaan introduksi rantai pasok telur ayam ras pete...

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

matieres nucleaires ne se limite pas S de simples travaux d'inventaire mais sert de base a beaucoup d'autres activites qui font partie integrante du programme d'operations de tout reacteur, par exemple les expeditions de combustible irradie, le traitement chimique du combustible epuise et la comptabilite du combustible recupere et des matieres produites au cours du fonctionnement du reacteur, et l'institution et l'application d'un regime d'assurance satisfaisant. (author) [Spanish] Combustible relativamente nuevo y sumamente valioso para la produccion de energia electrica, el uranio requiere un control muy minucioso desde el momento en que la direccion de una central asume la responsabilidad financiera inherente a su posesion hasta que como combustible parcialmente agotado se transfiere a otra instalacion en la que se recupera la parte que no se ha consumido. Antes de que se descubriera la posibilidad de emplear la energia nuclear para producir electricidad, la mayor parte de las empresas que actualmente explotan centrales nucleares explotaban centrales alimentadas con combustibles fosiles y hablan establecido sistemas de control relativamente completos y adecuados para los combustibles de ese tipo. Los responsables de las centrales nucleoelectricas deben disponer de sistemas no menos adecuados para controlar los materiales nucleares especiales que utilizan. La explotacion de los reactores de potencia no es una ciencia antigua, pero durante el tiempo relativamente corto que ha transcurrido desde que se inicio su empleo los ingenieros y hombres de ciencia han mejorado continuamente el diseflo del equipo y los metodos de trabajo con objeto de disminuir los costos de produccion y de lograr que las centrales nucleares puedan competir en el plano economico con las centrales clasicas. La administracion de los materiales nucleares debe efectuarse con metodos modernos y eficientes a fin de que los adelantos tecnologicos que han permitido reducir los costos no resulten inutiles

ANALISIS BAURAN PEMASARAN KENDARAAN RODA TIGA MEREK KAISAR PADA PT KAISAR MOTORINDO INDUSTRI PEKANBARU

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Bambang Suroto

2015-04-01

Full Text Available Abstrak: Banyaknya perusahaan atau operator yang melayani jaringan internet secara otomatis akan timbul suatu proses yang dinamakan pemasaran. Di dalam dunia usaha, pemasaran merupakan salah satu fungsi penting didalam suatu perusahaan, karena dalam pemasaran mencakup beberapa hal kegiatan penting yang kita kenal dengan marketing mix yang diantaranya adalah perencanaan produk (product, penetapan harga (price, program promosi (promotion, sangat penting dalam keberhasilan suatu perusahaan namun ada satu hal yang perlu diperhatikan dan perlu dianalisis apabila perusahaan menginginkan atau mempunyai daur hidup atau life cycle produk yang lebih lama, maka perusahaan harus melakukan analisis perilaku pelanggan. Selain kegiatan pemasaran yang sangat penting perusahaan juga tidak boleh mengabaikan apa yang dibutuhkan oleh seorang konsumen, faktor apa saja yang dapat merangsang pelanggan untuk melakukan pembelian suatu barang, serta mengapa konsumen mempunyai banyak kebutuhan dalam waktu yang relatif singkat dan tentunya hal itu semua menggambarkan arti penting sebuah kegiatan analisis perilaku konsumen. Keluhan yang dirasakan konsumen atau pelanggan adalah promosi yang diberikan atau ditawarkan terkadang sering tidak sesuai dengan kenyataan yang ada di lapangan, seperti akses internet yang lama, dan jaringan yang sering terputus karena adanya gangguan dan sistem perbaikan jaringan. Masalah dalam penelitian ini adalah faktor-faktor apakah yang menyebabkan tidak tercapainya target pemasaran pemasangan jaringan internet speedy pada PT.Kaisar Motorindo Industri Pekanbaru. Metode yang digunakan dalam penelitian ini adalah dengan menggunakan metode deskriptif, yaitu menggunakan analisis data kualitatif serta analisis data dengan menghubungkan antara teori dan permasalahan yang diteliti. Hasil penelitian diperoleh variabel produk, dalam hal ini merupakan kombinasi barang dan jasa yang ditawarkan oleh perusahaan kepada pasar sasaran terhadap pemasaran jaringan

Gamma monitoring system 'Hyperion' at the research nuclear reactor RB

International Nuclear Information System (INIS)

Zigic, A.; Saponjic, Dj.; Arandelovic, V. . E-mail address of corresponding author: alex@vin.bg.ac.yu

2005-01-01

While performing experiments at the research reactor RB at Vinca institute it is mandatory to measure the intensity of gamma radiation at reactor RB since the reactor has no biological protection. the stationary distributed measurement system 'Hyperion' implemented at reactor RB, performs measurements and monitoring of gamma radiation at 10 specified measuring sites within and in the vicinity of the reactor RB in the required absorbed dose in air range of 50 nGy/h to 10 mGy/h. the 'Hyperion' monitoring system have three hierarchically organized layers. the basic layer consists of the network of 10 intelligent gm probes located at predetermined measuring sites. the medium layer represents the PC-based local control node where measured data from all intelligent probes are separately acquired, stored in the local database and processed for local visualization and printed measurements reports for network operator. the information on the status of the intelligent gm probes are also provided, enabling the verification of measured results at the local control node. the central control node represents the pc-based highest monitoring network layer connected to the local control node using already existing lan infrastructure. the central control node hosts the central database, provides full insight into instantaneous gamma radiation levels at all measuring sites, provides archives on daily bases for all monitored locations and printed reports on measurements for all measuring sites at any time of gamma radiation measurement. (author)

Neutron dosimetry. Environmental monitoring in a BWR type reactor

International Nuclear Information System (INIS)

Tavera D, L.; Camacho L, M.E.

1991-01-01

The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

ANALISIS USAHA PENGOLAHAN AMPLANG IKAN PIPIH (Notopterus chilata SKALA RUMAH TANGGA DI KOTA PALANGKA RAYA PROVINSI KALIMANTAN TENGAH

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Saptami Utami Evi

2016-06-01

Full Text Available Usaha pengolahan amplang ikan  pipih di Kota Palangka Raya untuk pengembangan usaha kedepan sangat baik.  Dengan adanya dukungan tersedianya terus menerus bahan baku ikan pipih, baik dari tangkapan perairan, tangkapan alam, maupun usaha budidaya ikan pipih dan modal yang dikucurkan oleh pemerintah baik berupa peralatan usaha maupun pelatihan-pelatihan bagi para pengusaha untuk dapat terus berkembang. Penelitian ini dilakukan dengan tujuan Penelitian ini dilakukan di Kota Palangka Raya Provinsi Kalimantan Tengah. Data yang digunakan adalah data primer dan sekunder. Metode yang digunakan dalam pengolahan dan analisis data dalam penelitian ini adalah purposive sampling Amplang datar ikan pengolahan rumah tangga bisnis keuntungan sebesar Rp. 12.169 juta, - per tahun. Dari lapangan menunjukkan fakta bahwa bisnis ini tetap menguntungkan dengan kelangsungan hidup dalam waktu yang lamaBerdasarkan nilai analisis keuangan dengan menggunakan kriteria investasi Net Benefit Cost Ratio ( Net BCR 5 % = 3,032073039 dan B / C ratio Bersih 13,5% = 1,526361382 lebih besar dari 1 berarti bahwa usaha ini layak untuk dilanjutkan .Khusus untuk datar usaha pengolahan ikan amplang ( Notopterus chilata rumah tangga di kota Palangka Raya Kalimantan Tengah Provinsi amplang permintaan produk ikan dengan menawarkan flat atau D = S yang sama , berarti ampalng produksi ikan untuk memenuhi pasar datar. Flat fish processing business amplang household in the city of Palangka Raya for future business development very well with the support of continuous availability of raw materials and capital flat fish are disbursed by the government in cash, business equipment and training for entrepreneurs to be able to continue developed.  The research was conducted in the City of Palangka Raya Central Kalimantan Province. The data used were primary and secondary data. The method used in processing and analyzing data in this study was purposive sampling. Amplang flat fish processing

Material and geometry options and performance characteristics for a test reactor

International Nuclear Information System (INIS)

Jahshan, S.N.; Fletcher, C.D.; Terry, W.K.

1993-01-01

For the past 3 yr, an Idaho National Engineering Laboratory (INEL) design team has studied design options for a new test reactor to provide continued testing services after several aging test reactors in the United States are decommissioned. This new reactor, the Broad Application Test Reactor (BATR), would also fill other currently unmet needs, such as medical isotope production and space reactor component testing. Consideration of user needs, safety requirements, developmental uncertainties, and other factors led to the selection of an evolutionary design with plate fuel and several independently cooled test loops. The fuel would be cooled by light water, but most neutron moderation would come from heavy water or beryllium. The BATR design was tentatively scaled to the Advanced Test Reactor (ATR), an existing reactor at INEL: The power output of BATR is 250 MW(thermal), and the active core heights is 1 m. For safety in loss-of-flow events, the coolant flows upward through the core. The BATR design has one large test loop (with a test space diameter of 15.0 cm) along the central axis of the core and six smaller test loops (with test space diameters of 8.0 cm) centered at 6-deg azimuthal intervals on a 24.71-cm-diam circle around the central core axis

Bacterial Colonization of Pellet Softening Reactors Used during Drinking Water Treatment

NARCIS (Netherlands)

Hammes, F.; Boon, N.; Vital, M.; Ross, P.; Magic-Knezev, A.; Dignum, M.

2010-01-01

Pellet softening reactors are used in centralized and decentralized drinking water treatment plants for the removal of calcium (hardness) through chemically induced precipitation of calcite. This is accomplished in fluidized pellet reactors, where a strong base is added to the influent to increase

Open-ended fusion devices and reactors

International Nuclear Information System (INIS)

Kawabe, T.; Nariai, H.

1983-01-01

Conceptual design studies on fusion reactors based upon open-ended confinement schemes, such as the tandem mirror and rf plugged cusp, have been carried out in Japan. These studies may be classified into two categories: near-term devices (Fusion Engineering Test Facility), and long-term fusion power recators. In the first category, a two-component cusp neutron source was proposed. In the second category, the GAMMA-R, a tandem-mirror power reactor, and the RFC-R, an axisymetric mirror and cusp, reactor studies are being conducted at the University of Tsukuba and the Institute of Plasma Physics. Mirror Fusion Engineering Facility parameters and a schematic are shown. The GAMMA-R central-cell design schematic is also shown

Analisis pengaruh capital adequacy ratio (CAR) dan operational efficiency ratio (OER) terhadap return on assets (ROA) (Studi pada bank umum syariah devisa di Indonesia)

OpenAIRE

Maryadi, Eldi

2017-01-01

Tujuan dari penelitan ini adalah untuk menganalisis (1) perkembangan ROA, CAR dan OER pada bank umum syariah devisa di Indonesia. (2) CAR dan OER terhadap ROA pada bank umum syariah devisa di Indonesia periode 2009-2014. Data yang digunakan adalah data time series dari Laporan Keuangan tahunan Bank Umum Syariah Devisa di Indonesia periode 2009-2014, yaitu Bank BNI Syariah, Bank Mega Syariah, Bank Muamalat Indonesia, dan Bank Mandiri Syariah. Alat analisis yang digunakan adalah analisis deskri...

Analisi comparativa della dieta di alcuni carnivori opportunisti (Vulpes vulpes, Martes foina, Meles meles in Europa

Directory of Open Access Journals (Sweden)

Anna Maria De Marinis

2003-10-01

Full Text Available L'ecologia alimentare della volpe, del tasso ed in misura minore della faina è stata ampiamente studiata in diverse aree comprese all'interno degli areali di queste 3 specie. La variazione geografica delle abitudini alimentari di questi carnivori definiti opportunisti è al contrario decisamente poco nota. Scopo del presente lavoro è la descrizione della variazione della dieta di faina, tasso e volpe attraverso l'Europa ed in secondo luogo l'analisi comparativa delle strategie alimentari adottate da questi carnivori. Sono stati analizzati 19 studi per la volpe, 11 per la faina e 23 per il tasso. Sono stati presi in considerazione soltanto gli studi della durata di almeno un anno nei quali la composizione della dieta, determinata tramite analisi delle feci, fosse espressa in percentuale di volume o biomassa e le categorie alimentari fossero dettagliatamente descritte. Gli studi sono stati divisi in gruppi in base alla regione climatica di appartenenza (mediterranea, centroeuropea, atlantica e boreale. Le categorie alimentari utilizzate nell'analisi della variabilità geografica sono: mammiferi, uccelli, anfibi, artropodi, lombrichi, altro animale, frutta, cereali, rifiuti. L'analisi delle componenti principali, condotta separatamente sulle 3 specie, ha consentito l'individuazione su di un grafico bidimensionale di due gruppi riferibili all'Europa centro-settentrionale ed alla regione mediterranea, con una percentuale di variabilità spiegata > 76% per ognuna delle 3 specie. La composizione della dieta del primo gruppo risulta caratterizzata da elevate percentuali di mammiferi e secondariamente uccelli per la volpe, uccelli ed altro animale per la faina e lombrichi, cereali ed anfibi per il tasso. La composizione della dieta nella regione mediterranea risulta invece caratterizzata da elevate percentuali di artropodi e frutta per tutte e 3 le specie di carnivori. L'analisi dicriminante ha consentito di differenziare gli studi condotti in ambiente

Developments in the regulation of research reactors

International Nuclear Information System (INIS)

Loy, J.

2003-01-01

The International Atomic Energy Agency (IAEA) has data on over 670 research reactors in the world. Fewer than half of them are operational and a significant number are in a shutdown but not decommissioned state. The International Nuclear Safety Advisory Group (INSAG) has expressed concerns about the safety of many research reactors and this has resulted in a process to draw up an international Code of Conduct on the Safety of Research Reactors. The IAEA is also reviewing its safety standards applying to research reactors. On the home front, regulation of the construction of the Replacement Research Reactor continues. During the construction phase, regulation has centred around the consideration of Requests for Approval (RFA) for the manufacture and installation of systems, structures and components important for safety. Quality control of construction of systems, structures and components is the central issue. The process for regulation of commissioning is under consideration

Significance assessment of small-medium sized reactors

Energy Technology Data Exchange (ETDEWEB)

Kanno, Minoru [Japan Atomic Power Co., Research and Development Dept., Tokyo (Japan)

2002-12-01

Preliminary assessment for deployment of small-medium sized reactor (S and M reactor) as a future option has been conducted at the JAPCO (Japan Atomic Power Company) under the cooperation with the CRIERI (Central Research Institute of Electric Power Industry). Significance of the S and M reactor introduction is listed as follows; lower investment cost, possible siting near demand side, enlarged freedom of siting, shorter transmission line, good compatibility with slow increase of demand and plain explanation of safety using simpler system such as integral type vessel without piping, natural convection core cooling and passive safety system. The deployment of simpler plant system, modular shop fabrication, ship-shell structured building and longer operation period can assure economics comparable with that of a large sized reactor, coping with scale-demerit. Also the S and M reactor is preferable in size for the nuclear heat utilization such as hydrogen production. (T. Tanaka)

Operational and reliability experience with reactor instrumentation

International Nuclear Information System (INIS)

Dixon, F.; Gow, R.S.

1978-01-01

In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

ANALISIS VARIABEL KEUANGAN YANG MEMPENGARUHI KEBIJAKAN DEVIDEN

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Sumiadji -

2012-03-01

Full Text Available Penelitian ini dilakukan untuk menguji pengaruh variabel keuangan yang terdiri dari: rasio pro-fitabilitas (return on assets, likuiditas (cash ratio, rasio hutang (debt to equity ratio, market value (earnings per share, dan perputaran total aset (total assets turnover terhadap kebijakan dividen yang diproksikan dengan dividend payout ratio (DPR pada perusahaan manufaktur yang terdaftar di Bursa Efek Indonesia tahun 2004-2008. Prosedur pemilihan sampel penelitian menggunakan purposive sampling sehingga menghasilkan 8 perusahaan yang memenuhi kriteria sampel. Data sekunder dikumpulkan dengan teknik dokumentasi bersumber dari Indonesian Capital Market Directory (ICMD, laporan keuangan, dan hasil Rapat Umum Pemegang Saham (RUPS. Teknik analisis yang digunakan dalam penelitian ini adalah analisis regresi linear berganda. Hasil penelitian ini adalah secara simultan variabel ROA, CR, DER, EPS dan TATO berpengaruh terhadap DPR. Secara parsial variabel yang mempengaruhi DPR adalah CR, EPS dan TATO. Varabel lainnya, yaitu ROA dan DER ditemukan tidak berpengaruh terhadap DPR. This research was conducted to examine the influence of the financial variables which consists of: return on assets (ROA, cash ratio (CR, debt to equity ratio (DER, earnings per share (EPS, and total asset turnover (TATO to the dividend policy that indicated by the dividend payout ratio (DPR of listed manufacturing company in Indonesia Stock Exchange  2004 to 2008. The sample selection procedure used was a purposive sampling so that it produced eight companies that met the sample criteria. Se-condary data was collected by the documentation technique were obtained from the Indonesian Capital Market Directory (ICMD, financial statements, and the results of the Annual General Meeting of Shareholders. The analysis technique used was multiple linear regression analysis. The research found that five variables of kind of ROA, CR, DER, EPS dan TATO simultaneously influence to dividend

Space reactor preliminary mechanical design

International Nuclear Information System (INIS)

Meier, K.L.

1983-01-01

An analysis was performed on the SABRE reactor space power system to determine the effect of the number and size of heat pipes on the design parameters of the nuclear subsystem. Small numbers of thin walled heat pipes were found to give a lower subsystem mass, but excessive fuel swelling resulted. The SP-100 preliminary design uses 120 heat pipes because of acceptable fuel swelling and a minimum nuclear subsystem mass of 1875 kg. Salient features of the reactor preliminary design are: individual fuel modules, ZrO 2 block core mounts, bolted collar fuel module restraints, and a BeO central plug

A trolley mounted magazine for reactor maintenance

International Nuclear Information System (INIS)

Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

2009-01-01

This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

A trolley mounted magazine for reactor maintenance

Energy Technology Data Exchange (ETDEWEB)

Brennan, P.J.; Madani, M.; Ridgway, G.H. [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada)], E-mail: patrick1.brennan@ge.com, mehdi.madani@ge.com, guy.ridgway@ge.com; Lundy, E.; Knight, D. [IM and CS (Inspection, Maintenance and Commerical Services), Ontario Power Generation, Ajax, Ontario (Canada)], E-mail: erroll.lundy@opg.com, david.knight@opg.com

2009-03-15

This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

A trolley mounted magazine for reactor maintenance

Energy Technology Data Exchange (ETDEWEB)

Brennan, P.J.; Madani, M.; Ridgway, G.H., E-mail: patrick1.brennan@ge.com, E-mail: mehdi.madani@ge.com, E-mail: guy.ridgway@ge.com [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada); Lundy, E.; Knight, D., E-mail: erroll.lundy@opg.com, E-mail: david.knight@opg.com [Ontario Power Generation, Inspection, Maintenance and Commercial Services, Ajax, Ontario (Canada)

2008-07-01

This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

A trolley mounted magazine for reactor maintenance

International Nuclear Information System (INIS)

Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

2008-01-01

This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

Analisis Pengaruh Monetary Policy Shock Terhadap Jumlah Deposito Perbankan Islam Dalam Sistem Perbankan Ganda: Studi Kasus Indonesia Dan Malaysia

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Ade Mutiah

2014-03-01

Full Text Available Tujuan dari penelitian ini adalah ingin menguji secara empiris, apakah perilaku nasabah perbankan Islam di Indonesia dan di Malaysia terpengaruh oleh kebijakan moneter yang dikeluarkan oleh bank sentral pada masingmasing negara. Selain itu, apakah negara dengan karakteristik ekonomi dan kebijakan yang hampir sama – Indonesia dan Malaysia -, akan menghasilkan perilaku nasabah terhadap deposito perbankan Islam yang sama atau tidak. Metode analisis yang digunakan dalam penelitian ini adalah yang pertama , metode ekonometrika VAR (Vector Auto Regression yang bila terjadi kointegrasi pada data yang stasioner di 1st difference akan dilanjutkan pada VECM (Vector Error Correction Models dan yang kedua, analisis elastisitas permintaan deposito perbankan Islam terhadap variabel-variabel yang diuji dalam penelitian ini pada periode Januari 2005 sampai dengan Desember 2009. Hasil dari penelitian ini menujukkan bahwa dalam jangka panjang variabel moneter di Indonesia berpengaruh secara signifikan terhadap deposito perbankan Islam. Berbeda dengan di Malaysia di mana variable moneter tidak berpengaruh secara signifikan terhadap deposito perbankan Islam. Begitupun hasil analisis elastisitas permintaan deposito perbankan Islam di kedua negara. Dengan demikian dapat disimpulkan bahwa deposito perbankan Islam di Indonesia lebih sensitif terhadap perubahan kebijakan moneter, dibandingkan dengan yang ada di Malaysia.JEL Classifications : E41, E52, G21.Keywords : Kebijakan Moneter; Deposito; Perbankan Islam; VECM; Elastisitas.

Reactor

International Nuclear Information System (INIS)

Fujibayashi, Toru.

1976-01-01

Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

Core construction in a pressure tube type heavy water reactor

International Nuclear Information System (INIS)

Ueda, Makoto; Aoki, Katsutada.

1975-01-01

Object: To replace a centrally positioned fuel assembly of a fuel assembly unit with a reactor controlling machinery to decrease a distance between the fuel assemblies thereby saving use of heavy water and enhancing economy. Structure: A centrally positioned fuel assembly of a fuel assembly unit, which is composed of a plurality of fuel assemblies orderly arranged in lattice fashion, is replaced with a reactor controlling members such as control rods, poison tubes and the like to provide an arrangement of lattice-free type fuel assembly, thus reducing the pitch as small as possible. (Kamimura, M.)

Analisis Highest and Best Use (HBU pada Lahan Jl. Gubeng Raya No. 54 Surabaya

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Akmaluddin Akmaluddin

2013-03-01

Full Text Available Laju pertumbuhan penduduk dan tingkat perekonomian yang semakin meningkat di  kota-kota besar seperti Surabaya, bertolak belakang dengan  ketersediaan lahan yang terbatas. Selayaknya properti yang akan dibangun di atas suatu lahan dapat memberikan manfaat yang maksimal serta efisien agar hasilnya dapat dirasakan demi pembangunan wilayah tersebut. Oleh karena itu, perlu dilakukan perhitungan  penggunaan yang paling memungkinkan dan diizinkan dari suatu tanah kosong atau tanah yang  sudah dibangun, dimana secara fisik dimungkinkan, didukung atau dibenarkan oleh peraturan, layak secara keuangan dan menghasilkan nilai tertinggi. Dalam penelitian ini dilakukan analisis Highest and Best Use (HBU pada lahan di Jl. Gubeng Raya No. 54 Surabaya seluas 1.150 m2 yang direncanakan akan dibangun hotel. Lahan tersebut berpotensi untuk dikembangkan menjadi properti komersial seperti hotel, apartemen, perkantoran dan pertokoan. Analisis tersebut menggunakan tinjauan terhadap aspek fisik, legal, finansial dan produktivitas maksimumnya. Dari hasil penelitian ini didapatkan alternatif properti komersial hotel yang memiliki penggunaan tertinggi dan terbaik pada pemanfaatan lahan dengan nilai lahan Rp. 67.069.980,31/ m2.

ANALISIS SUMBER-SUMBER KEBERMAKNAAN HIDUP NARAPIDANA YANG MENJALANI HUKUMAN SEUMUR HIDUP

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Siska Marliana

2012-04-01

Full Text Available Narapidana yang mendapat hukuman seumur hidup akan mengalami perubahan besar dalam kehidupannya, seperti keterbatasan dalam melakukan aktivitas, pekerjaan, kehidupan sosial bahkan dalam tujuan hidup. Kondisi tersebut akan  mengubah pandangannya mengenai makna dari hidupnya ataupun mengalami ketidakbermaknaan hidup. Fokus penelitian ini adalah analisis sumber-sumber kebermaknaan hidup pada narapidana yang divonis hukuman seumur hidup dengan mengacu pada konsep kebermaknaan hidup Viktor Frankl. Penelitian ini merupakan penelitian kualitatif dengan pendekatan studi kasus pada seorang narapidana di Lembaga Pemasyarakatan Klas 1 Sukamiskin Bandung yang sudah menjalani dua tahun masa hukuman dari vonis hukuman seumur hidup atas kasus pembunuhan. Teknik pengambilan data dilakukan dengan wawancara, observasi dan analisis dokumen. Hasil penelitian ini menunjukkan bahwa sumber-sumber kebermaknaan hidup bagi subjek adalah : 1.  Adanya nilai-nilai kreatif (creative values untuk dapat berkarya, bekerja, mencipta serta melaksanakan tugas dan kewajiban sebaik-baiknya. 2. Adanya nilai-nilai penghayatan (experiential values, yakni dengan cara memperoleh pengalaman tentang sesuatu atau seseorang yang bernilai bagi subjek. 3. Nilai-nilai bersikap (attitudinal values atas hukuman seumur hidup yaitu subjek memilih sikap menerima kondisi tersebut sebagai tanggung jawab yang harus dijalani akibat perbuatannya dan berusaha menikmati kehidupan di penjara dengan menjadikan penjara sebagai tempat untuk belajar menjadi manusia yang lebih baik. Kata Kunci: hukuman seumur hidup, sumber-sumber kebermaknaan hidup, creative values, experiential values, attitudinal values

Workers doses in central European PWR NPPs

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2003-01-01

As is stated, the ISOE database which was established in 1992 forms an excellent basis for studies and comparisons of occupational exposure data between nuclear power plants. In the year 2001, 69% of all participating reactors were pressurised water reactors. The ISOE database presents workers' exposure from 213 participating pressurised reactors (PWR) from 27 countries in that year. Among these 32 PWRs belong to six Central European Countries. The analysis of the exposure of workers based on radiation protection performance indicators (collective dose, average dose etc.) in these PWRs could be related to some nuclear safety performance indicators for recent years using ISOE database. The comparison is made to ISOE world - wide data. In the six Central European Countries altogether 32 PWR operated in the year 2001.The international databases of performance indicators related to radiation protection as for example the ISOE or the UNSCEAR database can be use as an efficient tool in the management of radiation protection of workers in a nuclear facilities and regulatory bodies. The databases enable the study of performance trends and the improvement of radiation protection. (authors)

Incertezza e processo finanziario: le conseguenze per il potere della banca centrale. ( Uncertainty and the financial process and its consequences for the power of the central bank

Directory of Open Access Journals (Sweden)

J.C.R. DOW

2013-12-01

Full Text Available La maggior parte dei teorici monetari sostengono che l'offerta di moneta determina il livello dei prezzi e che le autorità fissano i tassi di interesse per  influenzare gli investimenti e i consumi . L'autore chiede come le banche centrali , relativamente piccole istituzioni finanziarie ,siano in grado di influenzare il mondo reale . Nell'analisi , l'articolo si occupa di determinazione dei tassi di cambio , tassi di interesse e l'offerta di moneta . L'autore conclude che le banche centrali hanno influenza , all'interno di una gamma limitata , solo a causa di incertezza . A causa dell'incertezza , i legami tra attività finanziarie e reali sono deboli nel breve -medio periodo consentendo una certa influenza da maneggiato da un'autorità centraleMost monetary theorists claim that the money supply determines the price level and that the authorities set interest rates to influence investment and consumption. The author asks how central banks, relatively small financial institutions, can affect the real world. In analysis, the article deals with determination of exchange rates, interest rates and the money supply. The author concludes that central banks have influence, within a limited range, only because of uncertainty. Because of uncertainty, the links between financial and real assets are weak in the short- to medium-term allowing some influence to be wielded by a central authority.JEL: E52, E58

Reactors set for mini market

International Nuclear Information System (INIS)

Knox, Richard.

1988-01-01

Commercial nuclear power generation on a large-scale has an uncertain future. However, it is hoped that a small nuclear reactor could form the basis for providing heating, cooling or electricity in large buildings. Based on the Slowpoke research reactor, the Slowpoke energy system concept is simple. The concept and the way in which the small-scale reactor would work are discussed. The system consists of a stainless steel tank surrounded by reinforced concrete and let into the ground. The tank is full of light water which is heated to about 90 deg C by a central core of 2.4 percent enriched uranium fuel. The resulting natural circulation causes the water to pass through a heat exchanger. The water from the heat exchanger can be used for building or district heating, to operate air-conditioners or to generate small quantities of electricity. It is hoped to automate the operation of the reactor so that continuous supervision by a team of engineers would be unnecessary. A single operator on call in the building would be able to take control actions if the reactor's safety system failed. (UK)

ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI KEPUASAN KONSUMEN BERBELANJA ONLINE DI PROVINSI PULAU JAWA

Directory of Open Access Journals (Sweden)

Januar Israhmawan Putra

2017-11-01

Full Text Available Penggunaan internet di Indonesia yang tumbuh dengan pesat diikuti dengan banyak ber - munculan situs e-commerce yang merubah budaya dan gaya berbelanja masyarakat menjadi serba online. Pertumbuhan pasar e-commerce ini harus dibarengi dengan pelayanan yang akan diberikan kepada konsumennya secara baik agar konsumen merasa puas ketika bertran - saksi kepada perusahaan. Tujuan penelitian ini yaitu untuk mengetahui faktor apa saja yang mempengaruhi kepuasan konsumen berbelanja online pada situs jual beli Lazada, Zalora, dan Mataharimall. Variabel independent yang digunakan dalam penelitian ini yaitu Website Design, Security, Information Quality, Payment Method, E-service Quality, Product Quality, Product Variety, Delivery Service dan variebel dependent adalah Customer Satisfaction. �e- �e- �e - sponden dalam penelitian ini adalah konsumen Lazada, Zalora, dan Mataharimall yang be - rada di wilayah Provinsi Jawa Barat, Jawa Tengah, dan Jawa Timur dengan jumlah responden sebanyak 400 orang. Teknik sampling yang digunakan adalah nonprobability sampling yaitu porposive sampling. Penelitian ini menggunakan metode kuantitatif dengan teknik analisis data regresi berganda dan teknik analisis deskriptif. Hasil peneltian ini menunjukan bahwa website design, information quality, product vaiety, delivery service berpengaruh signifikan terhadap kepuasan konsumen dalam berbelanja online.

Creation of reactor's reliable system of emergency energy supply

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Brovkin, A.Yu.; Petukhov, V.K.; Chekushin, A.I.; Chernyaev, V.P.; Yagotinets, N.A.

1998-01-01

System of reliable power supply of the WWR-K reactor complex is described, which completely provides safety operation of reactor equipment in the case of total voltage loss from external power transmission lines as well as under destruction of accumulation batteries by earthquake more than 6 balls. Switching on in operation of diesel-generators and system of constant current supply from accumulator batteries is occurred automatically under cessation of voltage supply from centralized power system. Reliable reactor dampening in case it work on capacity has been ensured. Reactor cooling under its emergency shutdown during both the partial or the total loss of coolant in first counter has been carried out. Under full coolant loss the system of emergency reactor cooling has been switched on in operation

Effect of removal of a central thimble on coolant flow distribution in a research reactor fuel element

International Nuclear Information System (INIS)

Green, W.J.

1977-01-01

Using two twice full-size models of a HIFAR research reactor fuel element, experiments have been performed to determine how the flow distribution of coolant gas through the element in a transfer flask is affected by removal of the central instrumentation thimble. With the thimble present, experimental flow results agree with theoretical predictions. Over the range of total flowrates considered, mass flow apportioning among the five annular channels was independent of annular channel Reynolds number (in the range 3500 to 10,500) and ranged between 13% and 27% of the total flowrate. For the case with the thimble removed, interesting experimental flow characteristics were obtained which could not have been predicted. Flow apportioning among the annular channels was found to be uniquely dependent upon total flowrate and ranged between 3% and 8% for the experimental conditions investigated (annular channel Reynolds numbers in the range 800 to 4000). (Author)

Reactor head shielding apparatus

International Nuclear Information System (INIS)

Schukei, G.E.; Roebelen, G.J.

1992-01-01

This patent describes a nuclear reactor head shielding apparatus for mounting on spaced reactor head lifting members radially inwardly of the head bolts. It comprises a frame of sections for mounting on the lifting members and extending around the top central area of the head, mounting means for so mounting the frame sections, including downwardly projecting members on the frame sections and complementary upwardly open recessed members for fastening to the lifting members for receiving the downwardly projecting members when the frame sections are lowered thereto with lead shielding supported thereby on means for hanging lead shielding on the frame to minimize radiation exposure or personnel working with the head bolts or in the vicinity thereof

Burn up calculations for the Iranian miniature reactor: A reliable and safe research reactor

International Nuclear Information System (INIS)

Faghihi, F.; Mirvakili, S.M.

2009-01-01

Presenting neutronic calculations pertaining to the Iranian miniature research reactor is the main goal of this article. This is a key to maintaining safe and reliable core operation. The following reactor core neutronic parameters were calculated: clean cold core excess reactivity (ρ ex ), control rod and shim worth, shut down margin (SDM), neutron flux distribution of the reactor core components, and reactivity feedback coefficients. Calculations for the fuel burnup and radionuclide inventory of the Iranian miniature neutron source reactor (MNSR), after 13 years of operational time, are carried out. Moreover, the amount of uranium burnup and produced plutonium, the concentrations and activities of the most important fission products, the actinide radionuclides accumulated, and the total radioactivity of the core are estimated. Flux distribution for both water and fuel temperature increases are calculated and changes of the central control rod position are investigated as well. Standard neutronic simulation codes WIMS-D4 and CITATION are employed for these studies. The input model was validated by the experimental data according to the final safety analysis report (FSAR) of the reactor. The total activity of the MNSR core is calculated including all radionuclides at the end of the core life and it is found to be equal to 1.3 x 10 3 Ci. Our investigation shows that the reactor is operating under safe and reliable conditions.

Burn up calculations for the Iranian miniature reactor: A reliable and safe research reactor

Energy Technology Data Exchange (ETDEWEB)

Faghihi, F. [Department of Nuclear Engineering, School of Engineering, Shiraz University, Shiraz 71345 (Iran, Islamic Republic of); Research Center for Radiation Protection, Shiraz University, Shiraz (Iran, Islamic Republic of)], E-mail: faghihif@shirazu.ac.ir; Mirvakili, S.M. [Department of Nuclear Engineering, School of Engineering, Shiraz University, Shiraz 71345 (Iran, Islamic Republic of)

2009-06-15

Presenting neutronic calculations pertaining to the Iranian miniature research reactor is the main goal of this article. This is a key to maintaining safe and reliable core operation. The following reactor core neutronic parameters were calculated: clean cold core excess reactivity ({rho}{sub ex}), control rod and shim worth, shut down margin (SDM), neutron flux distribution of the reactor core components, and reactivity feedback coefficients. Calculations for the fuel burnup and radionuclide inventory of the Iranian miniature neutron source reactor (MNSR), after 13 years of operational time, are carried out. Moreover, the amount of uranium burnup and produced plutonium, the concentrations and activities of the most important fission products, the actinide radionuclides accumulated, and the total radioactivity of the core are estimated. Flux distribution for both water and fuel temperature increases are calculated and changes of the central control rod position are investigated as well. Standard neutronic simulation codes WIMS-D4 and CITATION are employed for these studies. The input model was validated by the experimental data according to the final safety analysis report (FSAR) of the reactor. The total activity of the MNSR core is calculated including all radionuclides at the end of the core life and it is found to be equal to 1.3 x 10{sup 3}Ci. Our investigation shows that the reactor is operating under safe and reliable conditions.

Dynamics and Control of Chemical Reactors-Selectively Surveyed

DEFF Research Database (Denmark)

Jørgensen, S. B.; Jensen, N.

1989-01-01

The chemical reactor or bioreactor is physically at a central position in a process, and often with a decisive role on the overall technical and economical performance. Even though application of feedback control on reactors is gaining momentum and on-line optimization has been implemented....... For bioreactors the theory and practice of reactor design, dynamics and control have to be adapted to the peculiarities of the biological catalysts. Enzymes, the protein catalysts, are the simplest ones, which have many common features with chemical catalysts. The living cells are much more complex, these growing...... in industry, many reactor control problems are still left unsolved or only partly solved using open loop strategies where disturbance rejection and model inaccuracies have to be handled through manual reactor control and feedback control of raw material preprocessing and product purification operations...

ANALISIS STRUKTUR AKTANSIAL DAN FUNGSIONAL DALAM VOYAGE AUCENTREDELA TERRE KARYA JULES VERNE

OpenAIRE

Ade Yolanda Latjuba, Dr. M.A

2017-01-01

Berdasarkan hasil analisis, maka dapat disimpulkan sebagai berikut: 1. Roman Voyage au centre de la terre menceritakan tentang Prof. Lidenbrock, Axel, dan Hans Bjelke melakukan perjalanan luar biasa menuju pusat bumi berdasarkan petunjuk dari Ame Saknussemm yang Axel dan si Professor dapatkan secara tidak sengaja terselip di dalam sebuah buku tua karya Snorre Tarlesson. 2. Prof. Lidenbrock, Axel dan Hans Bjelke memulai perjalanan mereka menuju pusat bumi dengan cara menuruni gunung bera...

ANALISIS SEGMENTASI PASAR PRODUK YOGHURT BERDASARKAN PERILAKU KONSUMEN PADA HYPERMART CABANG PANAKUKANG, MAKASSAR

OpenAIRE

-, ANDRIANI

2014-01-01

2014 v ABSTRAK Andriani. I311 04 049. Analisis Segmentasi Pasar Berdasarkan Perilaku Konsumen pada Hypermart Cabang Panakukang, Makassar. Dibawah Bimbingan Ir. Hastang, M.Si sebagai Pembimbing Utama dan Muh. Ridwan, S.Pt, M.Si. sebagai Pembimbing Anggota. Perkembangan dan peningkatan bisnis khususnya pada usaha peternakan akhir-akhir ini menunjukkan banyak peningkatan. Salah satu strategi yang dapat diterapkan dalam menunjang aktivitas pemasaran oleh perusahaan dalam memasarkan pr...

ANALISIS PENERAPAN TAX PLANNING ATAS PAJAK PENGHASILAN BADAN PADA PT SEMEN TONASA PANGKEP

OpenAIRE

WIJAYA, AKBAR

2014-01-01

2014 ABSTRAK ANALISIS PENERAPAN TAX PLANNING ATAS PAJAK PENGHASILAN BADAN PADA PT SEMEN TONASA PANGKEP Implementation Analysis of Tax Planning on Board Incoming Tax of Semen Tonasa Ltd. Pangkep Akbar Wijaya Amiruddin Darmawati Penelitian ini bertujuan untuk mengetahui tax planning yang dilakukan oleh PT Semen Tonasa Pangkep, dan untuk menganalisis penerapan tax planning yang dilakukan oleh PT Semen Tonasa Pangkep dengan undang-undang perpajakan yang berlaku. Data...

The US Liquid Metal Reactor Development Program

International Nuclear Information System (INIS)

Till, C.E.; Arnold, W.H.; Griffith, J.D.

1988-01-01

The US Liquid Metal Reactor Development Program has been restructured to take advantage of the opportunity today to carry out R and D on truly advanced reactor technology. The program gives particular emphasis to improvements to reactor safety. The new directions are based on the technology of the Integral Fast Reactor (IFR). Much of the basis for superior safety performance using IFR technology has been experimentally verified and aggressive programs continue in EBR-II and TREAT. Progress has been made in demonstrating both the metallic fuel and the new electrochemical processes of the IFR. The FFTF facility is converting to metallic fuel; however, FFTF also maintains a considerable US program in oxide fuels. In addition, generic programs are continuing in steam generator testing, materials development, and, with international cooperation, aqueous reprocessing. Design studies are carried out in conjunction with the IFR technology development program. In summary, the US maintains an active development program in Liquid Metal Reactor technology, and new directions in reactor safety are central to the program

Verification of reactor safety codes

International Nuclear Information System (INIS)

Murley, T.E.

1978-01-01

The safety evaluation of nuclear power plants requires the investigation of wide range of potential accidents that could be postulated to occur. Many of these accidents deal with phenomena that are outside the range of normal engineering experience. Because of the expense and difficulty of full scale tests covering the complete range of accident conditions, it is necessary to rely on complex computer codes to assess these accidents. The central role that computer codes play in safety analyses requires that the codes be verified, or tested, by comparing the code predictions with a wide range of experimental data chosen to span the physical phenomena expected under potential accident conditions. This paper discusses the plans of the Nuclear Regulatory Commission for verifying the reactor safety codes being developed by NRC to assess the safety of light water reactors and fast breeder reactors. (author)

Australia needs to replace the HIFAR reactor

International Nuclear Information System (INIS)

Garnett, Helen

1993-01-01

Central to the execution of ANSTO's objectives has been the operation since 1958 of the multipurpose HIFAR research reactor and related infrastructure. However, HIFAR's irradiation facilities, which are used for the provision of radiopharmaceuticals essential for nuclear medicine in Australia, have a limited capacity. The author stated that HIFAR's neutron beam facilities, which are needed by Australian scientists to undertake basic structural studies on a wide range of materials, are unable to provide the resolution and information required to keep Australia in the league of technologically advanced nations. The neutron flux and design limitations of older reactors such as HIFAR inhibit the upgrading of neutron beam facilities to modern standards. It is emphasised that while the cost of the new reactor is a vital issue, what is a prevailing importance is analyses of the cost-benefit and effectiveness of the new reactor, which will be undertaken by the Research Reactor Review. Some of these benefits are briefly outlined. ills

A New In-core Production Method of Co-60 in CANDU Reactors

Energy Technology Data Exchange (ETDEWEB)

Lyu, Jinqi; Kim, Woosong; Kim, Yonghee [KAIST, Daejeon (Korea, Republic of); Park, Younwon [BEES Inc, Daejeon (Korea, Republic of)

2016-05-15

This study introduces an innovative method for Co-60 production in the CANDU6 core. In this new scheme, the central fuel element is replaced by a Co-59 target and Co-60 is obtained after the fuel bundle is discharged. It has been shown that the new method can produce significantly higher amount of Co-60 than the conventional Co production method in CANDU6 reactors without compromising the fuel burnup by removing some (<50%) of the adjuster rods in the whole core. The coolant void reactivity is noticeably reduced when a Co-59 target is loaded into the central pin of the fuel bundle. Meanwhile, the peak power in a fuel bundle is just a little higher due to the central Co-59 target than in conventional CANDU6 fuel design. The basic technology for Co-60 producing was developed by MDS Nordion and Atomic Energy of Canada Limited (AECL) in 1946 and the same technology was adapted and applied in CANDU6 power reactors. The standard CANDU6 reactor has 21 adjuster rods which are fully inserted into the core during normal operation. The stainless steel adjuster rods are replaced with neutronically-equivalent Co-59 adjusters to produce Co-60. Nowadays, the roles of the adjuster rods are rather vague since nuclear reactors cannot be quickly restarted after a sudden reactor trip due to more stringent regulations. In some Canadian CANDU6 reactors, some or all the adjuster rods are removed from the core to maximize the uranium utilization.

Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor

Science.gov (United States)

Grodzki, Marcin; Darnowski, Piotr; Niewiński, Grzegorz

2017-12-01

The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an `early design' variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit). A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.

Monte Carlo Analysis of the Battery-Type High Temperature Gas Cooled Reactor

Directory of Open Access Journals (Sweden)

Grodzki Marcin

2017-12-01

Full Text Available The paper presents a neutronic analysis of the battery-type 20 MWth high-temperature gas cooled reactor. The developed reactor model is based on the publicly available data being an ‘early design’ variant of the U-battery. The investigated core is a battery type small modular reactor, graphite moderated, uranium fueled, prismatic, helium cooled high-temperature gas cooled reactor with graphite reflector. The two core alternative designs were investigated. The first has a central reflector and 30×4 prismatic fuel blocks and the second has no central reflector and 37×4 blocks. The SERPENT Monte Carlo reactor physics computer code, with ENDF and JEFF nuclear data libraries, was applied. Several nuclear design static criticality calculations were performed and compared with available reference results. The analysis covered the single assembly models and full core simulations for two geometry models: homogenous and heterogenous (explicit. A sensitivity analysis of the reflector graphite density was performed. An acceptable agreement between calculations and reference design was obtained. All calculations were performed for the fresh core state.

Nuclear policies in Central Europe. Environmental policy and enlargement of the European Union: Austria's policies towards Nuclear Reactors in neighboring countries

International Nuclear Information System (INIS)

Getzner, M.

2003-01-01

Austria's anti-nuclear policies are rooted in the successful anti-nuclear referendum on the Zwentendorf nuclear power plant (Lower Austria) in 1978 and the great impact of the Chernobyl catastrophe on Austria in 1986. Since about 1990, official Austria has pursued anti-nuclear policies not only at home but also abroad. In particular, reactors in Central and Eastern European Countries (CEEC) are the focal points of Austria's foreign anti-nuclear policies. Strategies include increasing nuclear safety, promoting energy efficiency and sustainable energy sources (such as renewable resources), and extending international legal frameworks to account for nuclear safety. Involvement in domestic energy issues in other countries is not an easy task, and while Austrian policy makers have had some success in increasing awareness of nuclear safety in Europe, they have also made a number of strategic mistakes. Notwithstanding real and substantiated concerns regarding nuclear safety, Austrian policies have lost credibility during recent years. This book explores the history and the development of Austrian anti-nuclear policies, and discusses the political economy of such policies. Particular emphasis is laid on the 2002 referendum against the Temelin reactor in the neighboring Czech Republic. (orig.)

MIT pebble bed reactor project

Energy Technology Data Exchange (ETDEWEB)

Kadak, Andrew C. [Massachusetts Institute of Technology, Cambridge (United States)

2007-03-15

The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis.

MIT pebble bed reactor project

International Nuclear Information System (INIS)

Kadak, Andrew C.

2007-01-01

The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis

Demolition of the FRJ-1 research reactor (MERLIN)

International Nuclear Information System (INIS)

Stahn, B.; Matela, K.; Zehbe, C.; Poeppinghaus, J.; Cremer, J.

2003-01-01

FRJ-2 (MERLIN), the swimming pool reactor cooled and moderated by light water, was built at the then Juelich Nuclear Research Establishment (KFA) between 1958 and 1962. In the period between 1964 and 1985, it was used for. The reactor was decommissioned in 1985. Since 1996, most of the demolition work has been carried out under the leadership of a project team. The complete secondary cooling system was removed by late 1998. After the cooling loops and experimental installations had been taken out, the reactor vessel internals were removed in 2000 after the water had been drained from the reactor vessel. After the competent authority had granted a license, demolition of the reactor block, the central part of the research reactor, was begun in October 2001. In a first step, the reactor operating floor and the reactor attachment structures were removed by the GNS/SNT consortium charged with overall planning and execution of the job. This phase gave rise to approx. The reactor block proper is dismantled in a number of steps. A variety of proven cutting techniques are used for this purpose. Demolition of the reactor block is to be completed in the first half of 2003. (orig.) [de

Analysis of radiological accident emissions of a lead-cooled experimental reactor. LEADER Project; Analisis radiologico de las emisiones en caso de accidente de un reactor experimental refrigerado por plomo. Proyecto LEADER

Energy Technology Data Exchange (ETDEWEB)

Gomez Salcedo, F.; Cortes Martin, A.

2013-07-01

The LEADER project develops a conceptual level industrial size reactor cooled lead and a demonstration plant of this technology. The project objectives are to define the characteristics and design to installation scale reactor using available technologies and short-term components and assess safety aspects conducting a preliminary analysis of the impact of the facility.

Analisi sui pigmenti di ceramica neolitica tramite tecniche Raman e LIBS

Directory of Open Access Journals (Sweden)

Cristina Fabbri

2007-04-01

Full Text Available I dati presentati in questo breve contributo provengono da uno studio condotto in collaborazione dal Dipartimento di Scienze Archeologiche dell’Università di Pisa e dall’Istituto per i Processi Chimico-Fisici di Fisica molecolare del CNR di Pisa. Le metodologie applicate sono basate sull’analisi integrata delle tecniche spettroscopiche Raman e LIBS già ampiamente utilizzate nel campo dei Beni Culturali; i metodi sono infatti essenzialmente non distruttivi, non richiedono di un pre trattamento del campione e l’acquisizione delle misure è immediata.

Historical-statistical analysis of energy consumption in energy management; Analisis historico-estadistico del consumo energetico en la administracion de energia

Energy Technology Data Exchange (ETDEWEB)

Guizar Bejarano, Ruben [IMENOR (Mexico); Oven, Mark [RCG/Hagler, Bailly, Inc., Washington (United States)

1993-12-31

Traditionally the specific consumption of energy has been considered as the most adequate index to evaluate the efficiencies in the productive processes. Nevertheless, this index, in some instances is highly susceptible to suffer significant variations, due to factors such as equipment condition, raw materials quality, operational parameters, climate and production level. This last one definitely is the most important and requires a deeper analysis. In this presentation a methodology is developed to analyze the energy consumption as well as their specific energy consumption with respect to production. Enough historical data are utilized to allow for a statistical analysis. This study is of equal usefulness in an energy diagnosis, as in a management program of energy saving. In presenting the possibility of identifying potential energy saving, stands out the advantages of the analysis and the conclusions that can be derived from it. Through the actual data collected in several industries during the energy diagnosis, various possible results of the analysis are presented. Finally, how this type of analysis can be adapted to a more precise control of the energy consumption is described and be used as a base for establishing goals in energy efficiency in the long term. [Espanol] Tradicionalmente se ha considerado al consumo especifico de energia como el indice energetico mas adecuado para evaluar las eficiencias de los procesos productivos. Sin embargo, este indice es en ocasiones altamente susceptible a sufrir variaciones importantes, debido a factores como el estado de los equipos, la calidad de la materia prima, los parametros operativos, el clima, y el nivel de produccion. Este ultimo es decididamente el mas importante, y requiere un analisis mas profundo. En esta presentacion se desarrolla una metodologia para analizar tanto consumos de energia como consumos especificos de energia con respecto a la produccion. Se utilizan suficientes datos historicos para permitir

Historical-statistical analysis of energy consumption in energy management; Analisis historico-estadistico del consumo energetico en la administracion de energia

Energy Technology Data Exchange (ETDEWEB)

Guizar Bejarano, Ruben [IMENOR (Mexico); Oven, Mark [RCG/Hagler, Bailly, Inc., Washington (United States)

1992-12-31

Traditionally the specific consumption of energy has been considered as the most adequate index to evaluate the efficiencies in the productive processes. Nevertheless, this index, in some instances is highly susceptible to suffer significant variations, due to factors such as equipment condition, raw materials quality, operational parameters, climate and production level. This last one definitely is the most important and requires a deeper analysis. In this presentation a methodology is developed to analyze the energy consumption as well as their specific energy consumption with respect to production. Enough historical data are utilized to allow for a statistical analysis. This study is of equal usefulness in an energy diagnosis, as in a management program of energy saving. In presenting the possibility of identifying potential energy saving, stands out the advantages of the analysis and the conclusions that can be derived from it. Through the actual data collected in several industries during the energy diagnosis, various possible results of the analysis are presented. Finally, how this type of analysis can be adapted to a more precise control of the energy consumption is described and be used as a base for establishing goals in energy efficiency in the long term. [Espanol] Tradicionalmente se ha considerado al consumo especifico de energia como el indice energetico mas adecuado para evaluar las eficiencias de los procesos productivos. Sin embargo, este indice es en ocasiones altamente susceptible a sufrir variaciones importantes, debido a factores como el estado de los equipos, la calidad de la materia prima, los parametros operativos, el clima, y el nivel de produccion. Este ultimo es decididamente el mas importante, y requiere un analisis mas profundo. En esta presentacion se desarrolla una metodologia para analizar tanto consumos de energia como consumos especificos de energia con respecto a la produccion. Se utilizan suficientes datos historicos para permitir

Analisis Biaya, Volume, Laba sebagai Alat Bantu Perencanaan Laba pada Hotel Sedona Manado

OpenAIRE

Samahati, Ricky Budiman

2013-01-01

Manado sebagai kota pariwisata menyediakan sarana dan prasarana kepariwisataan termasuk jasa perhotelan. Hotel Sedona merupakan salah satu hotel yang ada di Kota Manado dan merupakan objek yang dipilih penulis dengan menggunakan data operasional penjualan yang terjadi pada tahun 2011 dan 2012. Tujuan penelitian ini yaitu untuk mengetahui titik break even point, jumlah volume penjualan pada tingkat laba yang direncanakan, serta tingkat margin of safety pada Hotel Sedona Manado. Metode analisi...

ANALISIS POTENSI PEMUNGUTAN PAJAK HOTEL DALAM RANGKA PENINGKATAN PENDAPATAN ASLI DAERAH KOTA MAKASSAR

OpenAIRE

-, MUHAMMAD TRY DHARSANA AMBO ALA DEPARTEMEN AKUNTANSI FAKULTAS EKONOMI DAN BISNIS UNIVERSITAS HASANUDDIN MAKASSAR 2017

2017-01-01

Analisis Potensi Pemungutan Pajak Hotel dalam Rangka Peningkatan Pendapatan Asli Daerah Kota Makassar Analysis of Hotels Tax Collection Potency in Makkasar???s Own-Source Revenue Increase Muhammad Try Dharsana Ambo Ala Andi Kusumawati Yulianus Sampe Tujuan penelitian ini adalah untuk mengetahui besar potensi pajak hotel dan seberapa jauh bentuk usaha yang di lakukan oleh pemerintah daerah dalam menggali potensi pajak hotel di kota Makassar. Untuk menghitung potensi, efektivi...

Analisis Juridis Pelaksanaan Penghapusan Piutang Terhadap Kredit Macet (Studi Pada PT. Bank Sumut)

OpenAIRE

Margareth Eka Purba

2009-01-01

Usaha pokok Bank adalah sektor perkreditan dan pendapatan bank yang terbesar adalah berasal dari sektor perkreditan. Kredit, baik konsumtif maupun produktif memang sudah mejadi target utama perbankan dalam meraih pendapatan, selain fee based income tentunya. Dengan demikian, kelebihan dana masyarakat yang bisa membuat bank memiliki dana idle yang akan lebih produktif lagi karena diberikan dalam bentuk kredit.Walaupun sudah dilakukan analisis kredit, dan kredit sudah dinyatakan layak untuk dib...

Perangkat Lunak Untuk Analisis Gaya Gelombang Di Laboratorium Lingkungan Dan Energi Laut, Jurusan Teknik Kelautan, Ftk-Its

Directory of Open Access Journals (Sweden)

Fendi Hidayat

2013-09-01

Full Text Available Laboratorium Lingkungan dan Energi Laut, Jurusan Teknik Kelautan, FTK-ITS sering digunakan untuk pengujian. Salah satunya menguji gaya mooring pada floating breakwater. Hal tersebut menjadi salah satu alasan untuk membuat suatu perangkat lunak dalam membantu dalam proses analisis gaya mooring tersebut. Perangkat lunak yang dibuat berfungsi untuk membantu proses kalibrasi sensor load cell LUB-B 5 to 50 KB dan melakukan analisis gaya gelombang. Metode yang digunakan dalam penelitian ini adalah dengan menggunakan regresi linier, korelasi linier, perhitungan varian, standar deviasi, dan hukum Newton yang kemudian disusun dengan menggunakan Microsoft Visual Studio 2008. Penyusunan perangkat lunak yang bernama FORYS ini memiliki tampilan antarmuka pengguna yang mudah dalam pemakaian. Perangkat lunak yang telah dibuat juga bersifat portable sehingga bisa digunakan di berbagai komputer atau laptop. Hasil pengujian yang telah dilakukan menghasilkan bahwa semakin besar gaya gelombang yang terjadi, maka semakin besar pula tegangan yang terjadi pada tali.  

EKSLUSI DAN INKLUSI PADA RUBRIK METROPOLITAN HARIAN KOMPAS: ANALISIS WACANA KRITIS BERDASARKAN SUDUT PANDANG THEO VAN LEEUWEN

Directory of Open Access Journals (Sweden)

Harry Andheska

2015-10-01

Full Text Available Penggunaan teori kritis sebagai alat pengkajian dalam penelitian ini disebabkan oleh adanya persoalan tentang penumpang kereta rel listrik (KRL yang sering melanggar aturan dengan menaiki atap kereta tersebut. Penelitian ini pada dasarnya lebih menekankan titik perhatiannya pada sosok penumpang KRL sebagai sosok yang senantiasa termajinalkan dalam kehidupan sosial. Kajian ini merupakan pendekatan kualitatif dengan metode analisis isi. Kajian ini juga terbatas hanya pada satu teks berita yang dimuat dalam satu rubrik metropolitan pada haian Kompas. Model analisis wacana yang digunakan adalah model Theo Van Leuween dengan tujuan untuk mendeteksi dan meneliti bagaimana para penumpang yang duduk di atap KRL dimarjinalkan posisinya dalam suatu wacana. Hasil penelitian ditemukan bahwa terdapat dua jenis eksklusi yang dilakukan, yakni pasivasi dan nominalisasi; sedangkan inklusi ada tiga jenis, yakni diferensiasi, abstraksi, dan identifikasi. Keterbatasan dalam kajian ini disebabkan karena faktor kajian yang hanya terfokus pada satu teks berita.

Control rod for HTGR type reactor

International Nuclear Information System (INIS)

Mogi, Haruyoshi; Saito, Yuji; Fukamichi, Kenjiro.

1990-01-01

Upon dropping control rod elements into the reactor core, impact shocks are applied to wire ropes or spines to possibly deteriorate the integrity of the control rods. In view of the above in the present invention, shock absorbers such as springs or bellows are disposed between a wire rope and a spine in a HTGR type reactor control rod comprising a plurality of control rod elements connected axially by means of a spine that penetrates the central portion thereof, and is suspended at the upper end thereof by a wire rope. Impact shocks of about 5 kg are applied to the wire rope and the spine and, since they can be reduced by the shock absorbers, the control rod integrity can be maintained and the reactor safety can be improved. (T.M.)

Capital cost: gas cooled fast reactor plant

International Nuclear Information System (INIS)

1977-09-01

The results of an investment cost study for a 900 MW(e) GCFR central station power plant are presented. The capital cost estimate arrived at is based on 1976 prices and a conceptual design only, not a mature reactor design

Radiological analysis by the addition of hydrogen and noble metals in the reactors of the Laguna Verde central

International Nuclear Information System (INIS)

Padilla C, I.

2006-01-01

and of the radiological behavior when applying them, its allowed to settle down strategies in the Laguna Verde Central to control and to reduce the magnitude of the radiological increment in the primary steam lines in both units during the initial period of application. The radiological effects by the addition of hydrogen and of the noble metals, and its incorporation sequence to the reactor are the one reason of this work. (Author)

Analisis Pengaruh Kinerja Keuangan terhadap Alokasi Belanja Modal di Provinsi Jambi

Directory of Open Access Journals (Sweden)

Eko Indra Praza

2016-09-01

Full Text Available Abstract. This research aimed to analyze the financial performance of the District/ Municipality in Jambi Province and to determine the effect of financial performance either simultaneously or partially on capital expenditure. The data used in this research is a panel data comprising time series data is data in 2010 - 2013 and cross section data is data of 9 (nine District and 2 (two Municipality is located in the Province of Jambi. The analytical method used panel data regression analysis. The analysis showed that the financial performance of the District/ Municipality in Jambi Province is still relatively low as the PAD contribution to regional revenue is still small so transfer income still dominate the local revenue to finance most of the regional expenditure. The results of panel data regression using the Fixed Effect Model (FEM showed that the financial performance simultaneously significant effect on capital expenditure allocation of the District/Municipality in Jambi Province from 2010 to 2013 and partially Ratio Degree of Decentralization significant positive effect on the allocation of capital expenditure. Financial dependency ratio, Financial Independence Ratio and the ratio degrees contributions public enterprises significant negative effect on capital expenditure . Effectiveness ratio of PAD does not significantly influence the allocation of capital expenditure. Keyword: Financial Performance, Decentralization, Financial Independence,   Abstrak. Penelitian ini bertujuan untuk menganalisis kinerja keuangan Pemerintah Kabupaten/Kota di Provinsi Jambi dan untuk mengetahui pengaruh kinerja keuangan baik secara simultan maupun secara parsial terhadap alokasi belanja modal. Data yang digunakan dalam penelitian ini merupakan data panel yang terdiri dari data time series yaitu data tahun 2010 – tahun 2013 dan data cross section yaitu data 9 (sembilan Kabupaten dan 2 (dua Kota yang berada di Provinsi Jambi. Metode analisis yaitu analisis

Analisis Daya Saing untuk Meningkatkan Kualitas Layanan terhadap Pelanggan dengan Pendekatan CRM di CV. BLITZSPOT

Directory of Open Access Journals (Sweden)

Suryadi Muhammad

2017-04-01

Full Text Available CV. Blitzspot adalah perusahaan yang bergerak di bidang jasa penyediaan layanan internet (internet service provider, yang berkantor pusat di Komplek Padasuka Indah Ruko Blok A-1, Cimahi, Jawa Barat. Berdasarkan hasil wawancara dan hasil observasi pada data transaksi CV. Blitzspot, konsumen CV. Blitzspot yang melakukan transaksi tiap tahunnya selalu berkurang, hal ini dikarenakan konsumen sering membandingkan layanan-layanan yang ditawarkan oleh para pesaing CV. Blitzspot. Bila permasalahan tersebut belum teratasi, konsumen CV. Blitzspot akan menurun tiap tahunnya dan akan selalu berpindah ke pesaing CV. Blitzspot. Direktur Utama CV. Blitzspot ingin menganalisis daya saing untuk menentukan layanan-layanan yang akan diberikan kepada pelanggan CV. Blitzspot dan penentuan strategi untuk mempertahankan konsumen CV. Blitzspot.  Metode Analisis daya saing yang digunakan adalah Model Analisis Berlian Porter dan Metode Pengelompokkan Pelanggan yang digunakan adalah Metode LRFM. Berdasarkan hasil pengujian dan pembahasan yang telah dibuat, maka dapat ditarik kesimpulan bahwa Direktur Utama dapat menganalisis daya saing CV. Blitzspot dengan menggunakan Berlian Porter untuk meningkatkan kualitas layanan terhadap pelanggan CV. Blitzspot.

The development of model generators for specific reactors

Energy Technology Data Exchange (ETDEWEB)

Chow, J.C. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2012-07-01

Authoring reactor models is a routine task for practitioners in nuclear engineering for reactor design, safety analysis, and code validation. The conventional approach is to use a text-editor to either manually manipulate an existing model or to assemble a new model by copying and pasting or direct typing. This approach is error-prone and substantial effort is required for verification. Alternatively, models can be generated programmatically for a specific system via a centralized data source and with rigid algorithms to generate models consistently and efficiently. This approach is demonstrated here for model generators for MCNP and KENO for the ZED-2 reactor. (author)

Effect of a Central Graphite Column on a Pebble Flow in a Pebble Bed Core

International Nuclear Information System (INIS)

In, W. K.; Lee, W. J.; Chang, J. H.

2006-01-01

A pebble bed reactor(PBR) uses coated fuel particles embedded in spherical graphite fuel pebbles. The fuel pebbles flow down through the core during an operation. The pebble bed core is configured as cylindrical or annular depending on the reactor power. It is well known that an annular core can increase a cores' thermal power. The annular inner core zone is typically filled with movable graphite balls or a fixed graphite column. The first problem with this conventional annular core is that it is difficult to maintain a boundary between the central graphite ball zone and the outer fuel zone. The second problem is that it is expensive to replace the central fixed graphite column after several tens of years of reactor operation. In order to resolve these problems, a PBR with a central graphite column in a low core is invented. This paper presents the effect of the central graphite column on a pebble flow by using the computational fluid dynamics(CFD) code, CFX-10

ANALISIS PENGUNGKAPAN SUSTAINABILITY REPORT PADA PERUSAHAAN NON-KEUANGAN TAHUN 2009-2013

Directory of Open Access Journals (Sweden)

Candri Puspita Marwati

2015-10-01

Full Text Available Penelitian ini bertujuan untuk menguji dan menganalisis pengaruh return on asset (ROA, likuiditas (current ratio, ukuran perusahaan (size, earning per share (EPS terhadap pengungkapan sustainability report. Sampel yang digunakan adalah perusahaan non-keuangan terdaftar di Bursa Efek Indonesia (BEI yang menerbitkan sustainability report sesuai standar GRI pada periode 2009-2013 dan diperoleh 12 perusahaan. Teknik analisis data menggunakan uji asumsi klasik: normalitas, multikolinearitas, autokorelasi dan heterokedastisitas. Uji hipotesis menggunakan analisis regresi berganda. Hasil penelitian ini menunjukkan bahwa ROA berpengaruh positif signifikan terhadap sustainability report, current ratio tidak mempengaruhi sustainability report, size memiliki pengaruh negatif dan signifikan terhadap sustainability report, dan EPS memiliki pengaruh negatif dan signifikan terhadap sustainability report.This study aims to examine and analyze the effect of return on assets (ROA, liquidity (current ratio, firm size (size, earnings per share (EPS on the disclosure of sustainability report. Sample are corporate non-financial listed on the Indonesia Stock Exchange (IDX and publishes a sustainability report according to GRI standard in the period 2009-2013 and obtained sample of 12 companies. Data were analyzed using classic assumption test: normality, multicollinearity, autocorrelation and heterokedastisitas. Hypothesis testing using multiple regression analysis. The results showed that, ROA significant positive effect on sustainability report. current ratio does not affect the sustainability report. size has a negative and significant impact on the sustainability report, and EPS has a negative and significant impact on the sustainability report.

Research activity on thermohydraulic problems of PWR reactors

International Nuclear Information System (INIS)

Szabados, L.

1976-06-01

The general review of the experimental and theoretical research works on thermohydraulic investigation of pressurized water type reactors being done in the Central Research Institute for Physics is given. The main results of the theoretical and theoretical-numerical research are summarized. The most important result of the past years is the construction of the High Pressure Water Cooled Loop (NVH) thermohydraulic loop. Another significant achievement was the development of the reactor thermohydraulic program system. (Sz.N.Z.)

Analisis Kelayakan Finansial Usaha Budidaya Bambu

Directory of Open Access Journals (Sweden)

Husnul Khotimah

2015-12-01

Full Text Available Budidaya bambu diperlukan untuk menambah populasi bambu yang cenderung berkurang yang disebabkan oleh beralihnya fungsi lahan yang digunakan untuk pemukiman atau diganti dengan komoditi tanaman lain yang dianggap lebih menguntungkan. Sementara itu kebutuhan bahan baku bambu terus meningkat sejalan dengan pertumbuhan penduduk dan perkembangan kemajuan ilmu pengetahuan. Budidaya bambu bermanfaat selain untuk menjaga ketersediaan suplai juga untuk meningkatkan kualitas bambu untuk memenuhi permintaan pasar. Tulisan ini mengkaji analisis finansial dari penanaman bambu. Kajian finansial dibutuhkan untuk menunjukkan bahwa upaya penanaman atau budidaya bambu ini layak atau tidak secara finansial untuk dilakukan. Data yang digunakan adalah data hasil penelitian di perusahaan perkebunan bambu PT XYZ di Lampung. Hasil penelitian menunjukkan bahwa nilai NPV (Rp 36.644.364,08 lebih besar dari nol, Net B/C (2,56 lebih besar dari satu, IRR (11 % lebih besar dari suku bunga 6 %, serta payback period pada tahun ke-9 umur proyek 15 tahun. Berdasarkan kriteria indikator kelayakan finansial dapat disimpulkan bahwa usaha budidaya bambu layak secara finansial untuk diusahakan. Katakunci: Hasil Hutan Bukan Kayu (HHBK, budidaya bambu, studi kelayakan, analisis finansial   Financial analysis and feasibity study of bamboo cultivation  Abstract Bamboo cultivation is necessary to increase the population of bamboo clumps. The bamboo clumps tend to decrease due to the shift of used lands for residential or replaced by other crop comodities, which are considered more profitable. On the other hand, the need of bamboo for raw materials remain increase in line with population growth and the development of science. The important of the bamboo cultivation are to maintain the availability of its supply and to improve the quality of bamboo, which meet the market demands. This paper examined financial analysis of bamboo cultivation. Financial study was necessary to show whether

Thermal hydraulics model for Sandia's annular core research reactor

International Nuclear Information System (INIS)

Rao, Dasari V.; El-Genk, Mohamed S.; Rubio, Reuben A.; Bryson, James W.; Foushee, Fabian C.

1988-01-01

A thermal hydraulics model was developed for the Annular Core Research Reactor (ACRR) at Sandia National Laboratories. The coupled mass, momentum and energy equations for the core were solved simultaneously using an explicit forward marching numerical technique. The model predictions of the temperature rise across the central channel of the ACRR core were within ± 10 percent agreement with the in-core temperature measurements. The model was then used to estimate the coolant mass flow rate and the axial distribution of the cladding surface temperature in the central and average channels as functions of the operating power and the water inlet subcooling. Results indicated that subcooled boiling occurs at the cladding surface in the central channels of the ACRR at power levels in excess of 0.5 MW. However, the high heat transfer coefficient due to subcooled boiling causes the cladding temperature along most of the active fuel rod region to be quite uniform and to increase very little with the reactor power. (author)

ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI INDEPENDENSI PENAMPILAN AKUNTAN PUBLIK

Directory of Open Access Journals (Sweden)

Ardiani Ika S.

2012-03-01

Full Text Available Tujuan dari penelitian ini adalah untuk menguji secara empiris faktor-faktor yang mempengaruhi independensi penampilan akuntan publik baik secara parsial dan simultan. Faktor-faktor tersebut adalah financial interests, hubungan bisnis dengan klien, pelayanan asuransi dan audit, hubungan antara klien atau yg diaudit dengan auditor, kompetisi antara Kantor Akuntan Publik (KAP, ukuran KAP dan audit fee. Populasi dalam penelitian ini adalah para auditor di akuntan publik di Semarang tahun 2009. Metode penyeleksian sampel yang digunakan adalah convenience sampling dan jumlah respondennya 35. Alat analisis yang digunakan adalah multiple regression analysis. Dimulai dengan analisis kuantitatif untuk mengetes validitas dan reabilitas. Kemudian dilanjutkan uji asumsi klasik termasuk normality, multicollinearity, and heteroscedastisity. Hasil menunjukkan bahwa 6 variabel yang sudah dikaji secara simultan dan partial tersebut mempunyai efek yang signifikan terhadap independensi penampilan akuntan publik dengan R square 0.749. The objective of this study is to test empirically the factors that influence the independence of public accountant appearance both partially and simultaneously. The factors cover financial interests, business relationships with clients, assurance services and audit services, the length of relationship between client or auditee and auditor, the competition between Public Accountan Offices (KAPs, the size of KAP, and audit fee. The population in this study was the auditors who worked in the public accountant’s office in Semarang in 2009. The sample selection method is a convenience sampling and the  number of  respondents are 35. The Analysis tools used is multiple regression analysis. It starts by applying quantitative analysis to test the validity and reliability. Then, it is continued by testing the classical assumptions which include normality, multicollinearity, and heteroscedastisity. The result shows that the six

Nuclear safety in light water reactors severe accident phenomenology

CERN Document Server

Sehgal, Bal Raj

2011-01-01

This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents to teach nuclear professionals

Monitoring and Control Research Using a University Reactor and SBWR Test-Loop

International Nuclear Information System (INIS)

Edwards, Robert M.

2003-01-01

The existing hybrid simulation capability of the Penn State Breazeale nuclear reactor was expanded to conduct research for monitoring, operations and control. Hybrid simulation in this context refers to the use of the physical time response of the research reactor as an input signal to a real-time simulation of power-reactor thermal-hydraulics which in-turn provides a feedback signal to the reactor through positioning of an experimental changeable reactivity device. An ECRD is an aluminum tube containing an absorber material that is positioned in the central themble of the reactor kinetics were used to expand the hybrid reactor simulation (HRS) capability to include out-of-phase stability characteristics observed in operating BWRs

Dove sta andando l'analisi musicale? Riflessioni sul VII EuroMac

Directory of Open Access Journals (Sweden)

Mario Baroni

2014-01-01

Full Text Available Come tutti i lettori della Rivista ormai sapranno, si è svolto a Roma dal 29 settembre al 2 ottobre di quest’anno, presso il Conservatorio di S. Cecilia, il settimo convegno europeo di analisi musicale (VII European Music Analysis Conference ossia VII EuroMac. Nel convegno, organizzato dal GATM e diretto da Giorgio Sanguinetti, sono state presentate 197 relazioni e svolti otto laboratori. Tutti i materiali sono stati riassunti in un volume (Programme and Abstract Book, Iter Edizioni di Subiaco curato da Egidio Pozzi e Antonio Cascelli.

In situ reactor

Science.gov (United States)

Radtke, Corey William; Blackwelder, David Bradley

2004-01-27

An in situ reactor for use in a geological strata, is described and which includes a liner defining a centrally disposed passageway and which is placed in a borehole formed in the geological strata; and a sampling conduit is received within the passageway defined by the liner and which receives a geological specimen which is derived from the geological strata, and wherein the sampling conduit is in fluid communication with the passageway defined by the liner.

ANALISIS PENGARUH IRADIASI FLUENS NEUTRON CEPAT TERHADAP BERILIUM REFLEKTOR REAKTOR RSG-GAS

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Sri Kuntjoro

2015-04-01

Full Text Available Telah dilakukan analisis iradiasi fluens neutron cepat terhadap berilium reflektor reaktor RSG-GAS. Analisis dilakukan dengan cara melakukan pengukuran fluks neutron di posisi berilium elemen dan berilium blok yang berfungsi sebagai reflector. Selanjutnya dilakukan perhitungan untuk menentukan apakah ada pengaruh fluens neutron selama berilium berada di teras reaktor. Selain cara tersebut dilakukan pula visualisasi untuk memastikan ada tidaknya deformasi pada berilium akibat iradiasi. Hasil pengukuran fluks dan fluens neutron cepat maksimal pada daya 200 kW untuk berilium elemen posisi E-2 sebesar 2,30E+07 n/cm2s dan 4,19E+17 n/cm2, J-8 sebesar 3,70E+07 n/cm2s dan 6,74E+17 n/cm2. Hasil pengukutan pada posisi B-3 sebesar 2,19E+12 n/cm2s dan 3,99E+22 n/cm2, G-10 sebesar 2,12E+12 n/cm2s dan 3,86E+22 n/cm2, serta berilium blok posisi (5-6 sebesar 5,02E+07 n/cm2s dan 9,15E+17 n/cm2, (C-D sebesar 2,32E+07 n/cm2s dan 4,23E+17 n/cm2. Deformasi yang diperoleh untuk berilium elemen (∆L/L posisi E-2 sebesar 1,12E-08, J-8 sebesar 1,84E-08, B-3 sebesar 1,60E-03, posisi G-10 sebesar 1,55E-03, sedangkan pada berilium blok di posisi 5-6 sebesar 2,52E-08 dan C-D sebesar 1,13E-08. Dari hasil ini disimpulkan tidak terjadi deformasi pada berilium elemen dan berilium blok. Hasil ini dibuktikan pula dari pengamatan visual, dimana tidak terlihat adanya deformasi pada berilium tersebut. Kata kunci : fluks, fluens, berilium elemen, berilium blok   Analysis of influence fast neutron fluence irradiated to the RSG-GAS beryllium reflector have been done. Methods of analysis was carried out by measuring fluxs neutron in beryllium element and block positio that function as reflector. The calculation done for determination it is there any influence of neutron as long as beryllium in the core. Bisede that, visualization done to make sure it there is any deformation at beryllium as efect of irradiation. Fluxs and fluences of beryllium element measurement result in 200 k

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

radioactivity exposure considerations. Recent full-scale inspection and overhaul of the Dresden turbine provided no maintenance problems, after over 12 000 h of operation on direct-cycle steam and after operation with known failed fuel elements in the reactor. (author) [French] On a maintenant acquis une experience appreciable dans l'exploitation des centrales equipees de reacteurs a eau bouillante. Vers la fin de 1962, on avait produit plus de 2,2.10{sup 9} kWh dans trois centrales nucleaires rattachees a des reseaux de distribution: la centrale de Dresden (Commonwealth Edison Company, Morris, Illinois), la centrale de Vallecitos (Pacific Gas and Electric Company and General Electric Company, Pleasanton, Californie) et la centrale de Kahl (Rheinish-Westfaiisches Elektrizitatswerk et Bayemwerk, a Kahl-sur-le-Main, Republique federale d'Allemagne). Le rendement de ces reacteurs a eau bouillante, exploites dans les conditions normales de production d'electricite, est excellent. On peut donc s'attendre que les centrales a eau bouillante continueront d'etre sures, etant donne le facteur de disponibilite et le facteur de puissance des reacteurs et des installations de ce type. Au cours de 1963, quatre nouvelles centrales equipees de reacteurs a eau bouillante entreront en service: la centrale de Big Rock Point (Consumers Power Company, Charlevoix, Michigan), la centrale de Humboldt Bay (Pacific Gas and Electric Company, Eureka, Californie), la centrale de Garigliano (Societa Elettronucleare Nazionale, Scauri, Italie) et la centrale de demonstration japonaise (Institut de recherches nucleaires du Japon, Tokai Mura, Japon). Les resultats obtenus lors du demarrage et pendant le fonctionnement initial de ces installations confirment les espoirs suscites par les centrales de Dresden, Kahl et Vallecitos. Les journaux de marche des centrales de Dresden, Kahl et Vallecitos mettent en evidence la stabilite et la securite des reacteurs a eau bouillante. De plus, les niveaux de rayonnements

Dynamic stabilization of D—T burn in Tokamak reactors

Institute of Scientific and Technical Information of China (English)

ShiBing－Ren; LongYong－Xing

1997-01-01

A simple,engineeringly feasible dynamic method is supposed to control the deuterium-tritium burn process in Tokamak reactors operated in an advanced scenario.The thermal transport of the D-T plasma is described by an anomalous thermal conduction which is a radially increasing function and the central conduction value is proportional to the central temperature of the plasma.The dynamic external heating power is selected to be inversely proportional to certain power function of this temperature,As a result,the D-T burn can undergo in controllable way in different temperature regimes with different power output.Anomalous alpha particle transport effect is taken into account.It can affect the resultant plasma equilibrium ,the reactor efficency,the operation mode and so on.

ANALISIS DAN PERANCANGAN ARSITEKTUR SISTEM OTENTIKASI TERINTEGRASI ANTARA PLATFORM LINUX, WINDOWS 2000, DAN NOVELL NETWARE: STUDI KASUS JURUSAN TEKNIK INFORMATIKA FTIF ITS

Directory of Open Access Journals (Sweden)

Rully Soelaiman

2003-07-01

Full Text Available Normal 0 false false false IN X-NONE X-NONE MicrosoftInternetExplorer4 /* 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:0cm 5.4pt 0cm 5.4pt; mso-para-margin:0cm; mso-para-margin-bottom:.0001pt; 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; mso-bidi-font-family:"Times New Roman"; mso-bidi-theme-font:minor-bidi;} Jurusan Teknik Infomatika merupakan suatu organisasi yang menggunakan jaringan komputer yang diakses dari beberapa domain dan menggunakan sistem operasi terpisah. Masing-masing sistem tersebut menggunakan pengelolaan autentikasi yang terpisah, dengan kenyataan bahwa seharusnya dapat diakses oleh setiap anggota organisasi ini. Kebutuhan pengguna dan pengelola jaringan akan efisiensi pemakaian informasi autentikasi menjadi permasalahan yang akan dibahasa dana makalah ini. Pada makalah ini, dilakukan analisis kemungkinan dilakukannya otentikasi terintegrasi pada jaringan komputer Teknik Informatika yang menggunakan Windows 2000, Linux, dan Novell Netware. Analisis dilakukan dengan meninjau kemampuan integrasi direktori, metode otentikasi, dan kerjasama dengan sistem lain. Dari hasil pemetaan terhadap kebutuhan dan ketersediaan sumber daya teknologi pada jurusan, dipilih solusi otentikasi menggunakan Samba dan OpenLDAP untuk melayani permintaan otentikasi dari Windows 2000 dan Linux. Uji coba telah dilakukan untuk otentikasi client Windows 2000 dan Linux , mencakup login dari masing-masing sistem operasi, domain yang berbeda, menggunakan satu username dan password. Uji coba juga dilakukan terhadap proses

Nuclear Reactor Sharing Program

International Nuclear Information System (INIS)

1994-01-01

The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

Studies on reactor physics

International Nuclear Information System (INIS)

1960-01-01

Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

Analisis Pengaruh Konsentrasi Gas LPG Menggunakan Sensor TGS 2610 Berbasis Mikrokontroler AVR ATMega8535

OpenAIRE

Nurhalimah

2011-01-01

Telah dilakukan analisis kuantitatif gas dalam LPG. Penelitian ini dilakukan untuk mengukur konsentrasi gas LPG terhadap sensor. Metoda yang digunakan untuk mengukur konsentrasi gas LPG yaitu sensor gas semikonduktor jenis TGS 2610 keluaran Figaro yang digunakan untuk mendeteksi keberadaan gas. Sementara yang menjadi pusat pengendalian dari seluruh alat yang dirancang digunakan mikrokontroler AVR ATMega8535. Selain itu sistem yang dirancang dilengkapi LCD sebagai tampilan nilai konsentrasi ga...

Calculation of prefabricated part of WWR-K reactor building

International Nuclear Information System (INIS)

Belyashova, N.N.; Aptikaev, F.F.; Kopnichev, Yu.F.

1998-01-01

According of factual characteristics a strength and deformation of over-land part of carrier constructions under construction movement is defined. Direct dynamical calculation of design elements under action of inertial loads from supports shifts shows, that seismic stability of enclosing construction is not ensured. Possibly practically total collapse of coating construction is possibly, under which following levels of damages of internal design constructions of reactor central room have been forecasted: 1. Fall of destroyed design construction on reactor vessel in time moment (1.56-1.59 s) after coming to building of earthquake seismic waves of 10 balls. 2. It is possibly cracks formation in radial direction in lower part of reactor cap, but destroying of cap does not incident; 3. It is possibly cracks formation within stretched concrete zone of reactor construction at the mark from - 0.859 up to 0.100. Destroy of concrete's compressive zone of reactor construction have not being expected. 4. Collapse of reactor first contour coating constructions have not being expected

Analisis komoditas unggulan perikanan budidaya Kabupaten Pidie Jaya

Directory of Open Access Journals (Sweden)

Farok Afero

2015-06-01

Full Text Available Abstract. Snapper (Lates calcarifer, grouper (Epinephelus coioides, tiger shrimp (Penaeus monodon, vannamei shrimp (Litopenaeus vannamei and tilapia (Oreochromis niloticus are leading commodity worthly cultivated in Pidie Jaya. Bandar Baru and Tringgadeng an appropriate areas for black tiger shrimp while Jangka Buya and Ulim approriate areas for vannamei cultivation. AHP analysis showed black tiger shrimp is top priority based on the economic value while vannamei shrimp is top priority based on enterprise sustainability. Financial analysis of snapper, grouper, black tiger shrimp, vannamei shrimp and tilapia farming generated positive cash flow and NPV, IRR > 100%, the ratio of benefit to cost of production > 1,30 and payback period of investment costs  < 1 year, thus demonstrating the feasibility of cultivation of these leading commodities. Vannamei shrimp cultivation showed positive prospect as long the market offers premium price. Grouper and snapper had a positive outlook because high demand of high-quality fish in the international market. Keywords: Leading commodity; financial analysis; aquaculture; Pidie Jaya Abstrak. Komoditas kakap (Lates calcarifer, kerapu (Epinephelus coioides,udang windu (Penaeus monodon, udang vannamei (Litopenaeus vannamei dan nila (Oreochromis niloticus adalah komoditas unggulan yang layak dibudidaya di Kabupaten Pidie Jaya. Bandar Baru dan Tringgadeng merupakan kawasan yang layak untuk pengembangan komoditas udang windu sedangkan Jangka Buya dan Ulim layak untuk pengembangan komoditas udang vannamei. Analisis AHP menunjukkan komoditas udang windu menjadi prioritas utama untuk dikembangkan berdasarkan nilai ekonomi sedangkan udang vannamei menjadi prioritas utama berdasarkan keberlanjutan usaha. Analisis indikator keuangan budidaya kakap, kerapu, udang windu, vannamei dan nila menunjukkan usaha budidaya komoditas unggulan menghasilkan arus kas kumulatif dan NPV positif, nilai  IRR diatas 100%, rasio keuntungan

Method of operating water cooled reactor with blanket

International Nuclear Information System (INIS)

Suzuki, Katsuo.

1988-01-01

Purpose: To increase the production amount of fissionable plutonium by increasing the burnup degree of blanket fuels in a water cooled reactor with blanket. Method: Incore insertion assemblies comprising water elimination rods, fertile material rods or burnable poison rods are inserted to those fuel assemblies at the central portion of the reactor core that are situated at the positions not inserted with control rods in the earlier half of the operation cycle, while the incore reactor insertion assemblies are withdrawn at the latter half of the operation cycle of a nuclear reactor. As a result, it is possible to increase the power share of the blanket fuels and increase the fuel burnup degree to thereby increase the production amount of fissionable plutonium. Furthermore, at the initial stage of the cycle, the excess reactivity of the reactor can be suppressed to decrease the reactivity control share on the control rod. At the final stage of the cycle, the excess reactivity of the reactor core can be increased to improve the cycle life. (Kamimura, M.)

The evolution of Canadian research reactors, 1942 to 1992

International Nuclear Information System (INIS)

Lidstone, R.F.

1993-01-01

This report reviews the evolution of Canadian research reactor design over the past fifty years. Canadian research reactors have played a central role in the development of CANDU power reactors and the creation of an international business based on the production of medical and industrial radioisotopes. A focus on neutronic efficiency, which stemmed from the incentive for direct use of Canada's abundant uranium resources, has resulted in several generations of multipurpose reactors with a common heritage of neutronic efficiency. Each successive nuclear design has been engineered with the best available resources to extrapolate slightly from the current technology base to meet specific program requirements and to incorporate the flexibility needed to accommodate evolving priorities. (Author) 19 refs., 2 tabs., 2 figs

Analisis Film Horor Indonesia Produksi Tahun 2014 (Studi Kasus: Mall Klender dan Kamar 207

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Dedi Sukatno Sembiring Meliala

2016-02-01

Full Text Available Abstrak Film horor erat kaitannya dengan tokoh antagonis yang menimbulkan ketakutan pada penonton dalam bentuk makhluk supranatural seperti hantu, roh jahat dan sebagainya. Karakteristik film dengan genre horor membuat penonton terbawa suasana dengan alur ceritanya yang menakutkan. Namun, beberapa dari film horor Indonesia menyajikan adegan-adegan yang kurang sopan bahkan tergolong asusila atau porno. Untuk itu, penelitian ini ingin melihat apakah terdapat konten pornografi pada film Mall Klender dan Kamar 207 yang merupakan film horor Indonesia terlaris di tahun 2014. Analisis dilakukan dengan melihat pandangan dan penilaian 30 responden dengan karakteristik yaitu penonton film horor Indonesia yang berusia 20-40 tahun. Berdasarkan hasil analisis, tidak didapatkan konten pornografi pada film Mall Klender dan Kamar 207. Adegan-adegan yang terindikasi sebagai konten pornografi ternyata masih dapat diterima oleh penonton sebagai adegan yang berada dalam batas kewajaran dan mendukung pembawaan suasana dan kesan dalam cerita yang disampaikan. Kata Kunci: film horror Indonesia, analisis konten, pornografi Abstract The horror film is closely related to the antagonist that causes fear for audience in the form of supernatural creatures such as ghosts, demons and so on. Characteristic of the horor film is to make the audience carried away with the scary plot. However, some of the existing Indonesian horror film presents scenes that classified as obscene or pornographic. Therefore, this study wanted to see if there are any pornographic content on the film Klender Mall and Room 207 is the best-selling Indonesian horror movie in 2014. The analysis was done by looking at the view and assessment of 30 respondents which are Indonesian horror movie goers aged 20-40 years. Based on the analysis, there is no founding of pornographic content on the film Klender Mall and Room 207. The scenes that indicated as pornographic content was still acceptable by the audience

Characteristics and uses of a 250 kW TRIGA reactor

International Nuclear Information System (INIS)

Dimic, V.

1985-01-01

The 250 kW TRIGA Mark II reactor is a light water reactor with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. Therefore the reactor has the large prompt negative temperature coefficient of reactivity, the fuel also has very high retention of radioactive fission products. The reactor core is a cylindrical configuration with an annular graphite reflector. The experimental facilities include a rotary specimen rack, a central incore radiation thimble, a pneumatic transfer system, and pulsing capability. Other experimental facilities include two radial and two tangential beam tubes, a graphite thermal column, and a graphite thermalizing column. At the steady state power of 250 kW the peak flux is 1x10 13 n/cm 2 s in the central test position. In addition, pulsing to about 2000 MW is usually provided giving peak fluxes of about 2x10 16 n/cm 2 sec. All TRIGA reactors produce a core-average thermal neutron flux of about 10 7 n.v per watt. Only with very large accelerators could such a high neutron flux be achieved. In order to give an appreciation for the research conducted at research reactors, the types of research could be summarized as follows: thermal neutron scattering, neutron radiography, neutron and nuclear physics, activation analysis, radiochemistry, biology and medicine, and teaching and training. Typical applied research with a 250 kW reactor has been conducted in medicine in biology, archeology, metallurgy and materials science, engineering and criminology. It is well known that research reactors have been used routinely to produce isotopes for industry and medicine. In some instances, reactors are the preferred method of isotope production. We can conclude that the 250 kW TRIGA research reactor is a useful and wide ranging source of radiation for basic and applied research. The operation cost for this instrument is relatively low. (author)

Analysis system and remote monitoring of atmospheric discharges; Sistema de analisis y monitoreo remoto de descargas atmosfericas

Energy Technology Data Exchange (ETDEWEB)

Zabre Borgaro, Eric; Rodriguez Padilla, Ma. Consuelo [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1996-12-31

A system for analysis and monitoring of atmospheric discharges (SAMDA (Sistema de Analisis y Monitoreo de Descargas Atmosfericas) (lightnings)) in an electronic device that subsequently transmits these data as automatic processing or by request of a user from a computer operating as a remote station, is described. Also, the characteristics of the SAMDA, its evolution, and the challenges encountered along the development of this project and comments on possible improvements to the equipment and data recordings of this nature, are described. [Espanol] Se presenta el sistema de analisis y monitoreo de descargas atmosfericas (SAMDA) utilizado en la deteccion y registro de descargas atmosfericas (rayos) en un equipo electronico que posteriormente transmite estos datos como procesamiento automatico o por peticion de un usuario desde una computadora, operando como estacion remota. Asimismo, se describen las caracteristicas del SAMDA, su evolucion, los retos encontrados a lo largo del desarrollo de este proyecto y comentarios sobre posibles mejoras a equipos y registros de datos de esta naturaleza.

Analysis system and remote monitoring of atmospheric discharges; Sistema de analisis y monitoreo remoto de descargas atmosfericas

Energy Technology Data Exchange (ETDEWEB)

Zabre Borgaro, Eric; Rodriguez Padilla, Ma Consuelo [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1997-12-31

A system for analysis and monitoring of atmospheric discharges (SAMDA (Sistema de Analisis y Monitoreo de Descargas Atmosfericas) (lightnings)) in an electronic device that subsequently transmits these data as automatic processing or by request of a user from a computer operating as a remote station, is described. Also, the characteristics of the SAMDA, its evolution, and the challenges encountered along the development of this project and comments on possible improvements to the equipment and data recordings of this nature, are described. [Espanol] Se presenta el sistema de analisis y monitoreo de descargas atmosfericas (SAMDA) utilizado en la deteccion y registro de descargas atmosfericas (rayos) en un equipo electronico que posteriormente transmite estos datos como procesamiento automatico o por peticion de un usuario desde una computadora, operando como estacion remota. Asimismo, se describen las caracteristicas del SAMDA, su evolucion, los retos encontrados a lo largo del desarrollo de este proyecto y comentarios sobre posibles mejoras a equipos y registros de datos de esta naturaleza.

Thermohydraulic accident behavior of reactors

International Nuclear Information System (INIS)

Horche, W.; Kirmse, R.; Reichenbach, D.; Weber, J.P.

1992-01-01

GRS, on behalf of the German Federal Ministry for the Environment, conducted an assessment of the technical safety of the Greifswald nuclear generating units of the Soviet WWER-440/W-230 and W-213 reactor lines, respectively. The evaluation of existing accident analyses and the execution of some first calculations by GRS added to the know-how of GRS. This is reflected in the increased participation by GRS in international expert bodies investigating safety problems of WWER-440 plants. The contributions made towards international WWER projects within the framework of IAEA missions or as a result of bilateral consultations strengthen international partnership in the field of reactor safety in Central and Eastern Europe. (orig.) [de

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.

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-01-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testings of CENDL-2 and ENDF/B-6. (4 tabs., 2 figs.)

ANALISIS KENDALA POTENSIAL PENERAPAN TOTAL QUALITY MANAGEMENT HOTEL PLAZA SEMARANG

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Hendrajaya -

2010-03-01

Full Text Available Penelitian ini bertujuan untuk menemukan faktor-faktor yang terbentuk dari kendala penerapan Total Quality Management (TQM, sebagai upaya untuk menganalisis masalah-masalah potensial dari penerapan TQM di Hotel Plaza, Semarang. Sampel dari penelitian ini sejumlah 65 karyawan Hotel Plaza, Semarang yang terdiri dari manajer dan staf. Teknik analisis menggunakan Faktor Analisis. Hasil penelitian menunjukkan, bahwa kendala potensial dari implementasi TQM dapat disimpulkan menjadi lima faktor, yaitu faktor inkonsistensi, visi-misi, transformasi budaya, manajerial dan manajemen kualitas. Penelitian ini memberikan rekomendasi bahwa peningkatan fungsi-fungsi korporat melalui optimalisasi kualitas sebagai strategi bisnis dan orientasi pada kepuasan konsumen dengan melibatkan seluruh anggota organisasi, akan menjadi dasar untuk memaksimalkan daya saing perusahaan dalam hal produk, layanan, SDM, lingkungan dan seluruh proses yang dapat mendukung upaya perbaikan produktivitas. This study aims to determine the constraint factors and to analyze the potential problems of TQM implementation of Plaza Semarang Hotel. The sample of 65 employees of TQM implementation of Plaza Semarang Hotel, consist of managers and staffs. Factor analysis is used to achieve the results of the potential constraint implementation of Total Quality Management which can be summarized into five factors, they are: the factor of inconsistencies, the factor of vision and mission, cultural transformation factors, managerial factors and the factors of quality management. In order to increase the corporate functions through the optimization of quality as a business strategy and to achieve customer satisfaction, this study suggests that all members of the organization should be involved by the company as on-going basis to maximize the competitiveness of the organization on products, services, human resources, environment and all processes that support productivity improvement.

Analisis Zona Permeabel Fluida Sistem Panas Bumi Gunungapi Slamet Berdasarkan Analisis Kerapatan Kelurusan Citra SRTM Dan Struktur Geologi

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Sachrul Iswahyudi

2016-03-01

Full Text Available Keberadaan manifestasi panasbumi di sekitar Gunungapi Slamet tidak dapat dipisahkan dari zona-zona permeabilitas yang berkembang. Lokasi-lokasi lulus air tersebut (zona permeabel yang memungkinkan terbentuknya sirkulasi fluida tempat air masuk untuk mengisi reservoir panas bumi dan air keluar ke permukaan bumi sebagai manifesatasi mata air panasbumi di sekitar Gunungapi Slamet. Publikasi yang berupa hasil penelitian ini mencoba mengidentifikasi zona-zona permeabel tersebut berdasarkan anaslisis kerapatan kelurusan yang terekam dalam citra SRTM. Identifikasi kelurusan-kelurusan pada citra berdasarkan komponen-komponen interpretasi citra, yaitu tona, tekstur, pola, bentuk dan relief. Hasil analisis tersebut dikompilasi dengan data struktur geologi regional yang sebelumnya telah diidentifikasi dan data lapangan berupa manifestasi mata air panas. Lokasi-lokasi dengan kerapatan kelurusan yang tinggi pada citra SRTM umumnya bersesuaian dengan zona struktur geologi regional keberadaan manifestasi mata air panas. Daerah tersebut memanjang relatif utara-selatan di bagian barat dan timur-barat di bagian selatan peta. Daerah-daerah inilah yang merupakan daerah lulus air tempat fluida bersirkulasi membentuk sistem panasbumi Gunungapi Slamet.

Analisis Pengaruh Parameter Operasional dan Penggunaan Stabilizer terhadap Perilaku Arah Belok Mobil Toyota Fortuner 4.0 V6 SR (AT 4X4

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Deva Andriansyah

2017-01-01

Full Text Available Salah satu tipe mobil yang diminati oleh masyarakat Indonesia yaitu Toyota Fortuner yang termasuk dalam kelas mobil SUV (sport utility vehicle. Dalam pengoperasiannya mobil SUV harus mampu memberikan keamanan dan kenyamanan bagi pengendaranya. Salah satu faktor penunjang dari segi keamanan mobil ini yaitu perilaku arah beloknya. Dengan harga jual yang relatif tinggi di Indonesia, diharapkan mobil ini dapat memberikan perilaku arah belok yang baik. Terdapat dua tahapan dalam peneltian ini yaitu tahap analisis dan uji jalan pada radius belok tetap, 10 meter. Pada tahap analisis dilakukan perhitungan berdasarkan analisa slip, skid, dan guling untuk mengetahui perilaku arah belok mobil dengan variasi pada parameter operasionalnya yaitu: jumlah penumpang, kecepatan, sudut belok, kondisi permukaan jalan, dan tekanan ban. Selain itu, analisis pengaruh penggunaaan stabilizer terhadap perilaku arah belok mobil juga dilakukan. Uji jalan dilakukan untuk mengetahui Koefisien Understeer (KUS dari mobil tersebut pada jalan aspal dan tanah dengan kondisi mobil tanpa dan menggunakan stabilizer. Hasil yang didapatkan dari uji jalan akan dibandingkan dengan hasil dari analisis perhitungan. Hasil penelitian ini menunjukkan bahwa mobil Toyota Fortuner mengalami kondisi belok paling baik ketika dinaiki oleh 2 orang penumpang dengan tekanan ban sebesar 35 Psi dan melintas pada jalan aspal karena kendaraan lebih sedikit mengalami oversteer dan memiliki (KUS positif terkecil serta tidak mudah mengalami skid. Penggunaan stabilizer pada mobil Toyota Fortuner tidak berpengaruh terhadap perilaku arah beloknya karena KUS yang dihasilkan pada uji jalan nilainya hampir sama yaitu 1,8045 dan 1,8115 pada jalan aspal serta 2,151 dan 2,1641 pada jalan tanah. Namun, penggunaan stabilizer bermanfaat untuk memperkecil sudut guling ketika mobil berbelok.

Analisis Faktor Pembentuk Ekuitas Merek Toyota dan Daihatsu di Indonesia (Studi Komparasi pada Masyarakat Bandung)

OpenAIRE

Sigiro, Cristine Afriani; Rachma Putri, Yuliani; Ilfandy Imran, Ayub

2016-01-01

Toyota dan Daihatsu merupakan dua merek otomotif (mobil) yang sangat fenomenal di kalangan masyarakat Indonesia. Produk dari kedua merek tersebut memiliki persamaan yang identik, namun Toyota memasarkan produknya lebih mahal dibandingkan Daihatsu. Tujuan penelitian ini untuk mengetahui perbandingan ekuitas merek Toyota dan Daihatsu menurut masyarakat Bandung. Penelitian ini menggunakan paradigma penelitian positivistik dengan metode penelitian studi komparatif melalui teknik analisis data yan...

Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

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Nurul Dzakiya

2017-05-01

Full Text Available Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m, lempung pasiran (11-30 m dan lapukan batuan diorit (30-55 m yang berada di kedalaman berbeda. Ketebalan batuan di permukaan sekitar 225-231 meter berdasarkan penampang peta geologi dengan arah sebaran dari Barat Laut hingga Tenggara. Proses pelapukan dan alterasi di daerah ini intensif (alterasi argilik dengan jenis morfologi perbukitan intrusi terdenudasi dan dataran Alluvial.

Physics design of the upgraded TREAT reactor

International Nuclear Information System (INIS)

Bhattacharyya, S.K.; Lell, R.M.; Liaw, J.R.; Ulrich, A.J.; Wade, D.C.; Yang, S.T.

1980-01-01

With the deferral of the Safety Test Facility (STF), the TREAT Upgrade (TU) reactor has assumed a lead role in the US LMFBR safety test program for the foreseeable future. The functional requirements on TU require a significant enhancement of the capability of the current TREAT reactor. A design of the TU reactor has been developed that modifies the central 11 x 11 fuel assembly array of the TREAT reactor such as to provide the increased source of hard spectrum neutrons necessary to meet the functional requirements. A safety consequence of the increased demands on TU is that the self limiting operation capability of TREAT has proved unattainable, and reliance on a safety grade Plant Protection System is necessary to ensure that no clad damage occurs under postulated low-probability reactivity accidents. With that constraint, the physics design of TU provides a means of meeting the functional requirements with a high degree of confidence

Status and some safety philosophies of the China advanced research reactor CARR

International Nuclear Information System (INIS)

Luzheng Yuan

2001-01-01

The existing two research reactors, HWRR (heavy water research reactor) and SPR (swimming pool reactor), have been operated by China Institute of Atomic Energy (CIAE) since, respectively, 1958 and 1964, and are both in extending service and facing the aging problem. It is expected that they will be out of service successively in the beginning decade of the 21 st century. A new, high performance and multipurpose research reactor called China advanced research reactor (CARR) will replace these two reactors. This new reactor adopts the concept of inverse neutron trap compact core structure with light water as coolant and heavy water as the outer reflector. Its design goal is as follows: under the nuclear power of 60MW, the maximum unperturbed thermal neutron flux in peripheral D 2 O reflector not less than 8 x 10 14 n/cm 2 . s while in central experimental channel, if the central cell to be replaced by an experimental channel, the corresponding value not less than 1 x 10 15 n/cm 2 . s. The main applications for this research reactor will cover RI production, neutron scattering experiments, NAA and its applications, neutron photography, NTD for monocrystaline silicon and applications on reactor engineering technology. By the end of 1999, the preliminary design of CARR was completed, then the draft of preliminary safety analysis report (PSAR) was submitted to the relevant authority at the end of 2000 for being reviewed. Now, the CARR project has entered the detail design phase and safety reviewing procedure for obtaining the construction permit from the relevant licensing authority. This paper will only briefly introduce some aspects of safety philosophy of CARR design and PSAR. (orig.)

Logistical and economic obstacles to a fast reactor programme

International Nuclear Information System (INIS)

Sweet, C.

1982-01-01

Fast reactor studies used to place great emphasis on its role as a breeder of plutonium, thereby raising the prospect of a nuclear power system free from the constraint of uranium supplies. Today, not only the timing of fast reactor introduction has slipped (by two or three decades) but the perspective which was central to energy policy has changed dramatically. This article first examines the fast reactor as a system and looks at the interaction of four key variables in its logistics. It then looks at the rise in real costs, especially capital costs. Given the parameters that determine the plutonium balance and the economics of the fast reactor system, the author questions whether there is a sound basis for its introduction, and concludes by suggesting that the most pressing requirement is a study of the opportunity costs of fast reactor R and D expenditures. (author)

ANALISIS FUNDAMENTAL MAKRO DAN INTEGRASI PASAR SAHAM DUNIA DENGAN BURSA EFEK INDONESIA

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Luh Gede Sri Artini

2017-11-01

Full Text Available Penelitian ini merupakan gabungan dari penelitian sebelumnya mengenai hubungan antara harga saham dengan kinerja ekonomi makro, dan penelitian mengenai integrasi Pasar Modal internasional.Variabel ekonomi makro dalam penelitian ini dibatasi pada pertumbuhan PDB, tingkat suku bunga SBI dan nilai Kurs dolar Amerika terhadap Rupiah dan Indeks saham digunakan adalah Indeks Dow Jones, Indeks Saham Australia, Indeks Shanghai dan Indeks Singapura. Data dikumpulkan dari tahun 2011 sampai tahun 2015 secara bulanan dengan teknik analisis regresi linier dengan bantuan Statistical Package For Social Science (SPSS

TUGAS DAN WEWENANG PUSAT PELAPORAN DAN ANALISIS TRANSAKSI KEUANGAN (PPATK DALAM PEMBERANTASAN TINDAK PIDANA PENCUCIAN UANG

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Johari Johari

2014-03-01

Full Text Available Tugas dan wewenang Pusat Pelaporan dan Analisis Transaksi Keuangan (PPATK terdapat di dalam Pasal 26 dan Pasal 27 Undang-Undang No. 25 Tahun 2003 tentang Tindak Pencucian Uang. Berdasarkan ketentuan tersebut, tugas dan wewenang PPATK tersebut bertujuan untuk mendeteksi terjadinya tindak pidana pencucian uang, dan membantu penegakan hukum yang berkaitan dengan pencucian uang, termasuk tindak pidana asal yang melahirkannya (predicate offences. Namun, Peranan PPATK akan berjalan secara efektif apabila aparat penegak hukum seperti Kepolisian, Kejaksaan, Pengadilan, Bea dan Cukai, para regulator seperti Bank Indonesia, Departemen Keuangan, Badan Pengawas Pasar Modal serta Penyedia Jasa Keuangan, industri perbankan, asuransi, perusahaan pembiayaan, dana pensiun, perusahaan efek, pengelola reksadana, media massa, masyarakat bekerjasama secara terorganisir dan terpadu dalam pemberantasan tindak pencucian uang di Indonesia. Dengan kewenangan yang dimilikinya, PPATK dapat mengejar hasil dari kejahatan, apabila hasil kejahatan tersebut dapat dikejar dan disita maka negara dengan sendirinya akan mengurangi tindak kejahatan itu sendiri. Kata kunci : Pencucian uang, tindak pidana pencucian uang (money laundering, kejahatan terorganisir, dan Pusat Pelaporan dan Analisis Transaksi Keuangan (PPATK.

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-11-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testing of CENDL-2 and ENDF/B-6. (author). 8 refs, 2 figs, 4 tabs

ANALISIS KELAYAKAN DAN SENSITIVITAS HARGA INPUT PADA USAHA BUDIDAYA IKAN LELE DALAM KOLAM TERPAL DI KOTA BANJARBARU PROVINSI KALIMANTAN SELATAN

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Idiannor Mahyudin

2016-10-01

Full Text Available Salah satu kegiatan ekonomi berbasis sumberdaya hayati pada sektor perikanan adalah kegiatan budidaya ikan.  Tetapi dengan keterbatasan lahan yang dimiliki dan untuk memanfaatkan lahan pekarangan supaya bernilai produktif maka masyarakat Banjarbaru banyak mengusahakan budidaya ikan lele di kolam terpal. Penelitian ini bertujuan untuk (1 menganalisis layak atau tidaknya usaha budidaya ikan lele di kolam terpal; (2 menganalisis pengaruh perubahan harga input terhadap usaha budidaya ikan lele di kolam terpal; (3 mengetahui permasalahan yang dihadapi oleh pelaku usaha budidaya  ikan lele di kolam terpal di Kotamadya Banjarbaru. Penelitian ini menggunakan metode survei dan wawancara. Data yang dikumpulkan meliputi data primer dan data sekunder. Lokasi sampel ditentukan secara sengaja (purposive, yakni Kotamadya Banjarbaru. Wawancara dilakukan terhadap petani ikan  yang aktif mengelola kegiatan usaha budidaya  ikan lele di kolam terpal, yakni sebanyak 200 petani ikan.  Penetapan jumlah sampel dilakukan secara random mengingat populasi yang homogen. Analisis data untuk menjawab tujuan pertama, yakni menganalisis kelayakan investasi usaha budidaya ikan lele di kolam terpal , digunakan perhitungan pada kriteria investasi yang meliputi Net Present Value (NPV, Net Benefit Cost Ratio (Net BCR, Internal Rate of Return (IRR dan Payback Period.   Untuk menjawab tujuan kedua dilakukan pengujian terhadap hasil kelayakan usaha pada metode di atas dengan mempertimbangkan adanya kenaikan harga pakan. Selanjutnya untuk menjawab tujuan ketiga, yakni mengetahui permasalahan yang dihadapi pelaku usaha budidaya ikan lele di kolam terpal, digunakan analisis deskriptif dengan cara mengkaji data-data primer/sekunder dan selanjutnya memaparkannya secara tertulis. Hasil analisis kelayakan usaha diperoleh nilai NPV 12% sebesar Rp 96.600,081 > 0, nilai B/C 12% = 2,089 > 1 dan nilai IRR = ~ (tidak terhingga  > dari tingkat bunga berlaku. Dari hasil kelayakan usaha

Analisis Gameplay Game Genre Virtual Pet

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Abi Senoprabowo

2015-02-01

Full Text Available Game adalah struktur interaktif yang membuat pemain berjuang menuju sebuah tujuan. Game dapat memberikan emosi dan mood, menghubungkan dengan orang latihan, sarana latihan, serta dapat memberikan edukasi. Salah satu game yang berkembang saat ini adalah game bergenre Virtual pet. Game virtual pet merupakan game simulasi memelihara sesuatu. Virtual pet memiliki gameplay yang menarik dan menyenangkan yang membuat pemain seolah-olah benar-benar memiliki binatang peliharaan mereka sendiri. Virtual pet dianggap oleh sebagian besar penggunanya dapat memberikan kegembiraan serta rasa kasih sayang karena tingkat interaksinya yang baik. Banyak pengembang game pemula yang mengembangkan genre ini sebagai game yang mereka buat karena kemudahaan dan tingkat penggunanya yang banyak. Akan tetapi banyak dari pengembang game pemula tidak memperhatikan tingkat keberlanjutan game virtual pet yang mereka buat sehingga membuat pemain cepat bosan. Pada penelitian ini, analisis game bergenre virtual pet yang sudah sukses dibuat seperti Zombigotchi, Tamagotchi Unicorn, dan Bird Land, diharapkan dapat membantu para pengembang game pemula agar mengetahui cara merancang dan mengembangkan game virtual pet dengan baik. Kata Kunci: game, gameplay, virtual pet

ANALISIS RESIDU PESTISIDA PIRETRIN DALAM TOMAT DAN SELADA DARI BEBERAPA PASAR DI JAKARTA

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D. Mutiatikum

2012-10-01

Full Text Available Penggunaan pestisida untuk budidaya komoditi pertanian memungkinkan adanya residu pestisida dalam sayuran sehingga konsumen berisiko tercemar pestisida yang merupakan zat toksik  sehingga diperlukan pemantmwn kadar residu dalam sayuran terutama yang langsung dikonsumsi tanpa dimasak. Penetapan  residu pestisida dilakukan dengan menggunakan kromatografi gas (GC. Hasil analisis residu pestisida golongan peretrin dalam tomat dan selada yang disampling dari pasar induk, pasar tradisional. pasar swalayan dan hipermarket yang berada diwilayah Jakarta menunjukkan hasil yang negatif (tidak terdeteksi.

The present situations and perspectives on utilization of research reactors in Thailand

Science.gov (United States)

Chongkum, Somporn

2002-01-01

The Thai Research Reactor 1/Modification 1, a TRIGA Mark III reactor, went critical on November 7, 1977. It has been playing a central role in the development of both Office of Atomic Energy for Peace (OAEP) and nuclear application in Thailand. It has a maximum power of 2 MW (thermal) at steady state and a pulsing capacity of 2000 MW. The highest thermal neutron flux at a central thimber is 1×10 13 n/cm 2/s, which is extensively utilized for radioisotope production, neutron activation analysis and neutron beam experiments, i.e. neutron scattering, prompt gamma analysis and neutron radiography. Following the nuclear technological development, the OAEP is in the process of establishing the Ongkharak Nuclear Research Center (ONRC). The center is being built in Nakhon Nayok province, 60 km northeast of Bangkok. The centerpiece of the ONRC is a multipurpose 10 MW TRIGA research reactor. Facilities are included for the production of radioisotopes for medicine, industry and agriculture, neutron transmutation doping of silicon, and neutron capture therapy. The neutron beam facilities will also be utilized for applied research and technology development as well as training in reactor operations, performance of experiments and reactor physics. This paper describes a recent program of utilization as well as a new research reactor for enlarging the perspectives of its utilization in the future.

Decommissioning of multiple-reactor stations: facilitation by sequential decommissioning

International Nuclear Information System (INIS)

Moore, E.B.; Smith, R.I.; Wittenbrock, N.G.

1982-01-01

Reductions in cost and radiation dose can be achieved for decommissionings at multiple reactor stations because of factors not necessarily present at a single reactor station: reactors of similar design, the opportunity for sequential decommissioning, a site dedicated to nuclear power generation, and the option of either interim or permanent low-level radioactive waste storage facilities onsite. The cost and radiation dose reductions occur because comprehensive decommissioning planning need only be done once, because the labor force is stable and need only be trained once, because there is less handling of radioactive wastes, and because central stores, equipment, and facilities may be used. The cost and radiation dose reductions are sensitive to the number and types of reactors on the site, and to the alternatives selected for decommissioning. 3 tables

Method for calculating the forces and deformations in the fast reactor fuel assembly accounting for the effects of reactor control system elements and shutdown

International Nuclear Information System (INIS)

Likhachev, Yu.I.; Vashlyaev, Yu.N.; Kravchenko, I.N.

1980-01-01

Methods for calculating deformations and interaction forces of heat-generating assemblies (HGA) of fast reactor core with account for the effect of control and protection system (CPS) elements at the reactor operation and change of interaction efforts between HGA at the reactor shutdown, are described. The results of testing the suggested methods on example of estimate of HGA behaviour of the BN-350 reactor are presented. For estimating the effect of CPS elements on HGA bending the sector model has been used. It is assumed that HGA deformation inside each sector is independent of HGA deformation of other sectors. A higher calculation accuracy is attained by means of laying out of sectors into regions of preferable influence of emergency protection elements and compensating packets. When determining deformation and interaction efforts between HGA caused by temperature change in the course of shutdown it is supposed that the HGA deformation is purely elastic. The methods described are realized in the form of ABRI-CPS and ABRI-HOL programs written in FORTRAN for the BESM-6 computer. The results of HGA calculations of the BN-350 reactor core show that CPS elements decrease contact efforts in the middle of the central packet, increase contact efforts in the peak of the central packet, increase contact efforts in the peaks of packets from the eight row to the periphery and increase contact efforts in the middles of packets from the 5th to 9th row [ru

Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

International Nuclear Information System (INIS)

Ene, D.; Cepraga, D.G.

2002-01-01

The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

Analisi dei cicli del mercato immobiliare: un applicazione sui dati italiani

Directory of Open Access Journals (Sweden)

Maurizio Festa!

2012-06-01

Full Text Available Utilizzando i dati italiani, sulla base dell'approccio teorico del ciclo "a nido d'ape" proposto da Janssen, Kruijt e Needham nel 1994, questo articolo propone un ulteriore contributo allo studio delle dinamiche del mercato immobiliare italiano. Utilizzando alcuni indicatori del mercato, si presentano i grafici del ciclo a nido d'ape per tutte le regioni e per le principali città. Tecniche di cluster analysis sono utilizzate per raggruppare le regioni che mostrano andamenti simili. L'obiettivo finale dell'analisi è quindi quello di esaminare il territorio nazionale in termini di sviluppo ed evoluzione del mercato delle abitazioni.

PENINGKATAN KEMAMPUAN ANALISIS MASALAH EKONOMI DENGAN MODEL PEMBELAJARAN PROBLEM BASED LEARNING (STUDI PADA SISWA KELAS X IIS 3 SMA 1 BAE KUDUS TAHUN AJARAN 2014/2015

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Kurnia Norma Handayani

2015-02-01

Full Text Available atar belakang penelitian ini adalah karena kurangnya kemampuan analisis masalah ekonomi sehingga menyebabkan kurangnya pemahaman siswa akan materi dan berpengaruh terhadap hasil belajar siswa kurang optimal, selain itu karena metode pembelajaran yang digunakan tidak tepat yaitu menggunakan ceramah tanpa variasi sedangkan karakter materinya adalah teoritis dan membutuhkan analisis. Penelitian ini bertujuan untuk mengetahui peningkatan kemampuan analisis masalah ekonomi dengan model pembelajaran Problem Based Learning dan mengetahui penerapan model pembelajaran Problem Based Learning untuk meningkatkan kemampuan analisis masalah ekonomi. Subyek penelitian ini adalah siswa kelas X IIS 3 SMA 1 Bae Kudus. Penelitian ini merupakan penelitian tindakan kelas yang dilakukan dalam 2 siklus. Hasil penelitian ini diperoleh data kemampuan analisis siswa siklus I nilai rata-rata 73,94 dengan ketuntasan klasikal sebesar 52,94%, pada siklus II nilai rata-rata meningkat menjadi 82,29 dengan ketuntasan klasikal sebesar 82,35%, aktivitas siswa pada pembelajaran siklus I cukup dan pada siklus II meningkat menjadi sangat baik. The background of this research is the lack of knowledge in economic problems so students learning outcomes less optimal, moreover because the learning method that is used is not appropriate to use the oral speech without variation while the character is doctrinaire and needing analysis. This research aims to know improving the analysis ability on the subject economic problems with problem based learning model and how the use problem based learning can improving the analysis ability on the subject economic problems. The subject of this research is the class X IIS 3 SMA 1 Bae Kudus. This study is an action research conducted in two cycles. The research finding showed that analysis ability in learning cycle I average grade is 73,94 with percentage of classical completeness is 52,94%, in cycle II average grade increase to 82,29 with percentage of

Heavy water moderated tubular type nuclear reactor

International Nuclear Information System (INIS)

Oohashi, Masahisa.

1986-01-01

Purpose: To enable to effectively change the volume of heavy water per unit fuel lattice in heavy water moderated pressure tube type nuclear reactors. Constitution: In a nuclear reactor in which fuels are charged within pressure tubes and coolants are caused to flow between the pressure tubes and the fuels, heavy water tubes for recycling heavy water are disposed to a gas region formed to the outside of the pressure tubes. Then, the pressure tube diameter at the central portion of the reactor core is made smaller than that at the periphery of the reactor core. Further, injection means for gas such as helium is disposed to the upper portion for each of the heavy water tubes so that the level of the heavy water can easily be adjusted by the control for the gas pressure. Furthermore, heavy water reflection tubes are disposed around the reactor core. In this constitution, since the pitch for the pressure tubes can be increased, the construction and the maintenance for the nuclear reactor can be facilitated. Also, since the liquid surface of the heavy water in the heavy water tubes can be varied, nuclear properties is improved and the conversion ratio is improved. (Ikeda, J.)

ANALISIS FAKTOR KEHADIRAN DOSEN DI UNIVERSITAS X

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Annisa Mulia Rani

2016-10-01

Full Text Available Aspek kualitas pekerjaan berkaitan langsung dengan waktu yang khusus digunakan dosen untuk mengembangkan kemampuan. Maka untuk merealisasikan kualitas dosen yang terbaik , pihak manajemen khusunya dekan membuat peraturan untuk kehadiran dosen adalah minimal 25 jam/minggu. Dengan peraturan ini diharapkan dosen dapat melaksanakan beban kerja dosen sebaik-baiknya. Peraturan ini tertulis dan tertuang pada SK Dekan No 20/2006 pada kampus X. Dengan Menggunakan Analisis faktor mencoba menemukan hubungan atar sejumlah variable-variabel yang awalnya saling independen satu dengan yang lain dimana variable penyebab kekurangan jam dosen datang/minggu adalah keluaraga, manajemen, hubungan social, fasilitas pengajaran, jarak/lokasi, kompensasi transport. Berdasarkan uji Bartley test dan Measure sample of adequate yang pertama maka dengan nilai sig 0.04 dan msa 0.540 . Dengan menggunakan metode principal component analysis maka pembentukan factor hanya ada 1 componen karena nilai eigen value yang mempunyai nilai diatas 1. Faktor pembentuk baru yaitu manajemen, kompensasi dan jarak menjadi satu component.

ANALISIS PSAK NO. 27 TENTANG AKUNTANSI PERKOPERASIAN DAN PENGARUHNYA TERHADAP KESEHATAN USAHA PADA KPRI

Directory of Open Access Journals (Sweden)

Muhammad Khafid

2012-03-01

Full Text Available Tujuan dari penelitian ini adalah untuk menganalisis kepatuhan penerapan PSAK 27 (Cooperative Accounting, dan untuk menganalisa dampak  kepatuhan penerapan PSAK 27 (Cooperative Accounting  pada pengoperasian kinerja KPRI di kota Semarang. Populasinya adalah 62 KPRI di kota Semarang, dan sempel yang digunakan adalah 29 KPRI. Metode pengumpulan datanya adalah dokumentasi dan kuesioner. Metode analisis data adalah analisis deskriptif  dan statistik inferensial. Hasil penelitian memperlihatkan bahwa KPRI di kotamadya Semarang dikategorikan cukup dan terbukti bahwa hipotesis menyatakan bahwa tingkat kepatuhan penerapan PSAK 27 berpengaruh terhadap pertumbuhan usaha. Abstract The purposes of this research are to analyze the implementation compliance of PSAK 27 (Cooperative Accounting, and to analyze the effects of implementation compliance of PSAK 27 (Cooperative Accounting on KPRI performance  in Semarang Municipality. The population are 62 KPRIs in Semarang.However, there are only twenty nine KPRIs become the samples. The methods for collecting the data are documentation and questionairre. Then, for analyzing the data, it requires descriptive analysis and inferential analysis. The results of study shows that KPRIs in Semarang Municipality are categorized as fair and hypothesis states that the level of implementation compliance of PSAK 27 is influencial to the business has successfully proven.Keywords:  cooperative accounting; compliance

ANALISIS POSISI BERSAING UNTUK MENENTUKAN STRATEGI PEMASARAN INDUSTRI KRIPIK TEMPE DI KOTA MALANG

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Rusno Rusno

2014-11-01

Full Text Available Industri kripik tempe di desa Sanan Malang merupakan bagian dari UMKM mengalami perkembang-an yang cukup baik. Hingga akhir tahun 2013 kemarin berjumlah kurang lebih 65 pengrajin, bahkan saat ini Sanan sudah menjadi sentra industri kecil penghasil kripik tempe dan menjadi salah satu pro-duk unggulan kota Malang. Namun dalam perjalanannya industri ini banyak mengalami masalah diantaranya banyak pesaing yang terus masuk dalam bisnis ini. Hal ini mengakibatkan persaingan yang semakin ketat sehingga para pelaku harus dapat menentukan strategi untuk dapat memenangkan persaingan, maka Tujuan dalam penelitian ini adalah untuk mengetahui bagaimana posisi bersaing dan penetapan strategi pemasaran produsen kripik tempe di kota Malang. Jenis penelitian ini adalah confirmatory research. Sebagai populasinya adalah pengusaha kripik tempe yang berlokasi di kecamatan Blimbing kota Malang yang berjumlah 65 pemilik home industri. Sampel dilakukan dengan teknik Simple random sampling berjumlah 33 pengusaha industri kripik tempe. Pengambilan data dilakukan dengan kuesioner, dan teknik analisis data dengan teknik deskriptif dan tabulasi silang. Berdasarkan analisis data didapatkan hasil penelitian bahwa posisi bersaing industri kripik tempe di Sanan terdapat 4 cluster yang terbagi dalam : Cluster 1 (pemimpin pasar/market leader beranggota-kan 1 perusahaan. Cluster 2(penceruk pasar/market nicher beranggotakan 13 perusahaan, Cluster 3 (penantang pasar/market challenger beranggotakan 8 perusahaan dan cluster 4 (pengikut pasar /market follower beranggotakan 11 perusahaan. 

Preliminary Study of Potential Market for Small Reactors

International Nuclear Information System (INIS)

Minato, A.; Brown, N. W.

2008-01-01

Small reactors are an energy supply for a specific purpose and oriented for a different market than large reactors. Small reactors will provide a local solution for developed and developing countries, such as, in remote areas, on small grids, or for non-electricity applications such as, district heating, seawater desalination and process heat. Single or medium sized power stations with small reactors should be compared with single fissile or renewable energy source and not be compared with large reactors. CRIEPI and LLNL have studied the business opportunities for small reactors. The small reactor concept is planned for initial use in small remote communities and in developing countries with small power distribution grid. Rapid installation and simple operation of the small plants is intended to support use in these communities without requiring development of a substantial nuclear technology infrastructure. In this study, two approaches were used in the assessment of the potential market. The first approach took a global look at the need for small nuclear plants. Then selected countries and sites were identified based on countries expressing interest in small reactors to the IAEA and consideration of sites in the US and Japan. (1) Tunisia, Mexico, Indonesia, Uruguay, Egypt and Argentina have demonstrated interest in nuclear power. Selecting one of these is dependent on political and socioeconomic factors, some of which have been identified, that require direct interaction with the countries to establish if they represent real opportunities. (2) The states of Hawaii and Alaska in the United States have high power cost and remote or island communities that may benefit from small nuclear plants. Alaska has shown greater interest in power alternatives including small than Hawaii and there is clearly less public resistance to nuclear power in Alaska. (3) The countries in Central America are actively expanding their power grids but have not demonstrated great interest

ANALISIS PERANCANGAN BUSINESS INTELLIGENCE BERBASIS SAAS CLOUD COMPUTING

Directory of Open Access Journals (Sweden)

I Gede Adnyana

2014-05-01

Full Text Available Persaingan bisnis yang ketat, mendorong setiap perusahaan menyusun strategi bisnis agar dapat bertahan dari para pesaing. Penyusunan strategi bisnis mutlak memerlukan informasi yang tepat dan akurat, pengolahan hingga analisis data yang menghasilkan informasi yang tepat dan akurat menjadi proses yang sangat penting. Business Intelligence (BI menawarkan solusi bisnis untuk menganalisis data dan memungkinkan suatu perusahaan untuk mengambil keputusan untuk meningkatkan keuntungan dan kinerja bisnis. Namun, BI mahal untuk diimplementasikan, memerlukan biaya pemeliharaan yang tidak sedikit dan infrastruktur yang kuat. Hal ini mendorong perusahaan mengurangi biaya tetapi masih memiliki teknologi yang tepat untuk memungkinkan mereka untuk membuat keputusan, mengidentifikasi peluang dan proaktif mengidentifikasi risiko yang dapat mempengaruhi bisnis. Konsep Software as a Service (SaaS Cloud Computing dapat menjawab tantangan yang dihadapi BI. Sebelum merancang BI berbasis SaaS perlu diketahui parameter-parameter evaluasi hingga kelebihan dan kekurangannya.

Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors; Calificacion del programa WIMS de calculo neutronico para diseno, seguimiento de operacion y analisis de accidentes de reactores nucleares

Energy Technology Data Exchange (ETDEWEB)

Lerner, A M [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina)

1997-12-31

A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

ANALISIS PERILAKU PENYUSUN ANGGARAN DALAM PERSPEKTIF KEAGENAN PADA KABUPATEN DAN KOTA DI PROVINSI SULAWESI SELATAN

OpenAIRE

ILMI, A. NURUL

2016-01-01

2016 Analisis Perilaku Penyusun Anggaran dalam Perspektif Keagenan pada Kabupaten dan Kota di Provinsi Sulawesi Selatan Analysis of Budget Compiler???s Behavior within the Agency Perspective in Regency and City of South Sulawesi Province A. Nurul Ilmi Mediaty Aini Indrijawati Penelitian ini bertujuan untuk menganalisis pengaruh perubahan Pendapatan Asli Daerah dan perubahan Dana Perimbangan terhadap perilaku oportunistik penyusun anggaran yang menjelaskan mengenai hubungan k...

Analisis Peranan Franchisor Terhadap Suksesnya Bisnis Franchise Pada Mc. Donald’s Cabang Ring Road Medan

OpenAIRE

Simarmata, Leonardo

2012-01-01

Tujuan penelitian ini adalah untuk mengetahui dan menganalisis peranan franchisor dalam promotion, support service, training, control system dan communication terhadap suksesnya bisnis franchise pada Mc Donald’s Cabang Ring Road Medan. Pengumpulan data primer diperoleh dengan cara memberikan daftar pertanyaan (questionaire) dan melakukan wawancara (interview) secara mendalam (depth interview) kepada pemilik usaha M. Donald’s Cabang Ring Road Medan. Teknik analisis data penelitian ini ad...

System for bearing a nuclear reactor vessel cooled by liquid metal

International Nuclear Information System (INIS)

Mahe, A.; Jullien, G.

1976-01-01

The invention relates to a bearing system for supporting a nuclear reactor vessel of the kind which is suspended from the reactor closure slab. The bearing system comprises a ring connected at one end to a collar and at the other end to two collars. The collar connected to the bottom end of the ring forms the top part of the vessel to be supported while the other two collars fit into the slab at two separate places. The ring and collars are disposed in an annular space formed in the slab and dividing it into two parts, i.e., a central part and a peripheral part surrounding the central part of the slab

Completely automated nuclear reactors for long-term operation

International Nuclear Information System (INIS)

Teller, E.; Ishikawa, M.; Wood, L.

1996-01-01

The authors discuss new types of nuclear fission reactors optimized for the generation of high-temperature heat for exceedingly safe, economic, and long-duration electricity production in large, long-lived central power stations. These reactors are quite different in design, implementation and operation from conventional light-water-cooled and -moderated reactors (LWRs) currently in widespread use, which were scaled-up from submarine nuclear propulsion reactors. They feature an inexpensive initial fuel loading which lasts the entire 30-year design life of the power-plant. The reactor contains a core comprised of a nuclear ignitor and a nuclear burn-wave propagating region comprised of natural thorium or uranium, a pressure shell for coolant transport purposes, and automatic emergency heat-dumping means to obviate concerns regarding loss-of-coolant accidents during the plant's operational and post-operational life. These reactors are proposed to be situated in suitable environments at ∼100 meter depths underground, and their operation is completely automatic, with no moving parts and no human access during or after its operational lifetime, in order to avoid both error and misuse. The power plant's heat engine and electrical generator subsystems are located above-ground

Mirror Advanced Reactor Study (MARS) final report summary

International Nuclear Information System (INIS)

Henning, C.D.; Logan, B.G.; Carlson, G.A.

1983-01-01

The Mirror Advanced Reactor Study (MARS) has resulted in an overview of a first-generation tandem mirror reactor. The central cell fusion plasma is self-sustained by alpha heating (ignition), while electron-cyclotron resonance heating and negative ion beams maintain the electrostatic confining potentials in the end plugs. Plug injection power is reduced by the use of high-field choke coils and thermal barriers, concepts to be tested in the Tandem Mirror Experiment-Upgrade (TMX-U) and Mirror Fusion Test Facility (MFTF-B) at Lawrence Livermore National Laboratory

ENCAPAI SUMBER DAYA MANUSIA UNGGUL (ANALISIS KINERJA DAN KUALITAS PELAYANAN

Directory of Open Access Journals (Sweden)

Ketut Sudarma

2012-03-01

Full Text Available Penelitian ini  bertujuan untuk menganalisis pengaruh kemampuan individu, kepuasan kerja, komitmen organisasi terhadap kinerja dan kinerja terhadap kualitas pelayanan. Sampel penelitian berjumlah 76 orang. Teknik pengambilan sampel menggunakan proportional random sampling. Variabel penelitian terdiri dari kemampuan individu, kepuasan kerja, komitmen organisasi, dan kinerja serta kualitas pelayanan  Analisis data menggunakan regresi dua tahap. Hasil penelitian menunjukkan bahwa kemampuan individu, kepuasan kerja dan komitmen organisasi mempunyai pengaruh positif signifikan terhadap kinerja dan kinerja berpengaruh positif signifikan terhadap kualitas pelayanan. Ini berarti semakin meningkat kinerja, maka semakin meningkat juga kualitas pelayanan. Dari hasil analisis deskriptif persentase tampak secara rata-rata  semua variabel penelitian  menunjukkan kategori baik, namun pada aspek-aspek tertentu pada masing-masing variabel masih terdapat kekurangan. Hasil penelitian ini diharapkan dapat menjadi masukan bagi pimpinan dalam meningkatkan kinerja dan kualitas pelayanan. Upaya perbaikan dimulai dari peningkatan kemampuan melalui pendidikan dan latihan, monitoring pelaksanaan kerja secara rutin, menumbuhkan komitmen kerja dan perbaikan standar operasi prosedur.The aim of the study is toanalyze the influence of individual abilities, job satisfaction, organizational commitment to performanceand performance againstservice quality. This samplingmethod is using 76 samples by the proportionalrandom sampling techniques. Variables consisted of individual ability, job satisfaction, organizational commitment, and performance andservice qualitydata analysisusingtwo-stageregression. The results showedthat theability of individuals, job satisfaction and organizational commitment had asignificant positive effecton performance and the performance ofa significant positive effecton quality of service. It means the higher performance, the higher service

Utilization of nuclear research reactors

International Nuclear Information System (INIS)

1980-01-01

prior to the beginning of the course was of particular value. Interesting scientific visits and demonstrations at the Isotope Institute and at the Central Research Institute for Physics (IFKI), both of the Hungarian Academy of Sciences, were also arranged. During the Study Tour at the Central Institute for Nuclear Research in Rossendorf near Dresden, German Democratic Republic, the participants had the opportunity to observe the organization of a 10 MW nuclear reactor where radioisotopes and radiopharmaceuticals are produced on a commercial scale. Lectures were delivered by local scientists on some of their programmes in applied research in solid state physics and material sciences. At the Technical University of Dresden, the group visited the homogeneous solid-moderated zero-power training reactor (AKR), primarily dedicated to nuclear education and training. Studies on different theoretical and experimental aspects of radiation protection (solid state nuclear track and thermoluminescent detectors) are also being carried out. The last day of the Study Tour was devoted to a visit to the College for Advanced Technology at Zittau, where a training reactor with a power of a few watts has been recently installed. (author)

Failure analysis of pebble bed reactors during earthquake by discrete element method

International Nuclear Information System (INIS)

Keppler, Istvan

2013-01-01

Highlights: ► We evaluated the load acting on the central reflector beam of a pebble bed reactor. ► The load acting on the reflector beam highly depends on fuel element distribution. ► The contact force values do not show high dependence on fuel element distribution. ► Earthquake increases the load of the reflector, not the contact forces. -- Abstract: Pebble bed reactors (PBR) are graphite-moderated, gas-cooled nuclear reactors. PBR reactors use a large number of spherical fuel elements called pebbles. From mechanical point of view, the arrangement of “small” spherical fuel elements in a container poses the same problem, as the so-called silo problem in powder technology and agricultural engineering. To get more exact information about the contact forces arising between the fuel elements in static and dynamic case, we simulated the static case and the effects of an earthquake on a model reactor by using discrete element method. We determined the maximal contact forces acting between the individual fuel elements. We found that the value of the maximal bending moment in the central reflector beam has a high deviation from the average value even in static case, and it can significantly increase in case of an earthquake. Our results can help the engineers working on the design of such types of reactors to get information about the contact forces, to determine the dust production and the crush probability of fuel elements within the reactor, and to model different accident scenarios

Failure analysis of pebble bed reactors during earthquake by discrete element method

Energy Technology Data Exchange (ETDEWEB)

Keppler, Istvan, E-mail: keppler.istvan@gek.szie.hu [Department of Mechanics and Engineering Design, Szent István University, Páter K.u.1., Gödöllő H-2103 (Hungary)

2013-05-15

Highlights: ► We evaluated the load acting on the central reflector beam of a pebble bed reactor. ► The load acting on the reflector beam highly depends on fuel element distribution. ► The contact force values do not show high dependence on fuel element distribution. ► Earthquake increases the load of the reflector, not the contact forces. -- Abstract: Pebble bed reactors (PBR) are graphite-moderated, gas-cooled nuclear reactors. PBR reactors use a large number of spherical fuel elements called pebbles. From mechanical point of view, the arrangement of “small” spherical fuel elements in a container poses the same problem, as the so-called silo problem in powder technology and agricultural engineering. To get more exact information about the contact forces arising between the fuel elements in static and dynamic case, we simulated the static case and the effects of an earthquake on a model reactor by using discrete element method. We determined the maximal contact forces acting between the individual fuel elements. We found that the value of the maximal bending moment in the central reflector beam has a high deviation from the average value even in static case, and it can significantly increase in case of an earthquake. Our results can help the engineers working on the design of such types of reactors to get information about the contact forces, to determine the dust production and the crush probability of fuel elements within the reactor, and to model different accident scenarios.

Analisis Spektral Daya dan Koherensi EEG Pada Anak Penderita Autism Spectrum Disorders (ASD

Directory of Open Access Journals (Sweden)

Nita Handayani

2017-12-01

Full Text Available Autism Spectrum Disorders (ASD adalah kondisi neurodevelopmental yang berkaitan dengan defisit dalam fungsi eksekutif, emosi, bahasa, dan komunikasi sosial. Beberapa teknik neuroimaging dan neurofisiologi digunakan untuk memahami hubungan antara fungsionalitas otak dan perilaku autis. Quantitative Electroencephalography (QEEG adalah sebuah teknik non-invasif yang dapat digunakan untuk memberikan gambaran fungsionalitas otak melalui beberapa besaran fisis yang dikaji. Pada paper ini akan dibahas tentang karakteristik sinyal listrik otak pada penderita austis berdasarkan analisis QEEG. Perekaman sinyal otak menggunakan Emotiv Epoc 14 channel (AF3, F7, F3, FC5, T7, P7, O1, O2, P8, T7, FC6, F4, F8, AF4 dan 2 channel referensi (CMS dan DRL. Jumlah subjek uji dalam penelitian sebanyak 6 anak penderita autis dan 5 anak sehat sebagai kontrol dengan rentang usia antara 10-15 tahun. Perekaman otak dilakukan pada kondisi rileks dan mata terutup selama 15 menit. Metode analisis data meliputi pre-processing data EEG untuk menghilangkan noise dan artefak, perhitungan spektral daya menggunakan periodogram Welch, dan analisis konektivitas fungsional otak dengan menghitung besarnya koherensi intra-hemisphere dan inter-hemisphere. Dari hasil studi diperoleh bahwa pada anak autis terjadi peningkatan spektral daya pada pita delta dan penurunan spektral daya pada pita alpha dibandingkan dengan subjek kontrol. Analisis konektivitas fungsional otak pada anak autis menunjukkan nilai koherensi intra-hemisphere dan inter-hemisphere yang lebih rendah pada pita delta dan theta, khususnya pada area frontal. QEEG dapat digunakan untuk karakterisasi sinyal otak pada penderita autis dan membedakannya dari subjek normal. Autism Spectrum disorder (ASD is a neurodevelopmental disorder associated with deficits in executive function, emotions, language, and social communication. Several neuroimaging and neurophysiology techniques are used to understand the relationship between

Neutron Field Characterization of Irradiation Locations Applied to the Slovenian TRIGA Reactor

International Nuclear Information System (INIS)

Barbot, Loic; Domergue, Christophe; Breaud, Stephane; Destouches, Christophe; Villard, Jean-Francois; Snoj, Luka; Stancar, Ziga; Radulovic, Vladimir; Trkov, Andrej

2013-06-01

This work deals with several neutron flux measurement instruments and particle transport calculations combined in a method to assess the neutron field in experimental locations in nuclear reactor core or reflector. First test of this method in the TRIGA Mark II of Slovenia led to the assessment of three energy groups neutron fluxes in central irradiation locations within reactor core. (authors)

The evolution of Canadian research reactors: 1942 to 1992

International Nuclear Information System (INIS)

Lidstone, R.F.

1992-01-01

Research reactors have played a central role in the development of the Canadian nuclear program. Major benefits arising from the operation of Canada's research reactors include the development and demonstration of Canada deuterium uranium (CANDU) power reactors and the creation of an international business based on the production of medical and industrial radioisotopes. Insofar as practicable, nuclear engineers have based each design on the evolutionary development of appropriate technology for Canada. This approach has resulted in several generations of multipurpose reactors with a common heritage of neutronic efficiency. A focus on neutronic efficiency stemmed from the incentive for direct use of Canada's abundant uranium resources; the desired reliance on natural-uranium fuels promoted interest in efficient moderators, especially heavy water, and structural materials with a low affinity for absorbing neutrons, such as aluminum and zirconium alloys

ANALISIS RASIO ALTMAN MODIFIKASI PADA PREDIKSI KEBANGKRUTAN PERUSAHAAN PROPERTY DAN REAL ESTATE YANG TERDAFTAR DI BEI

OpenAIRE

Anita Tri Widiyawati; Supri Wahyudi Utomo; Nik Amah

2015-01-01

Penelitian ini bertujuan untuk mengetahui pengaruh rasio Altman Modifikasi terhadap prediksi kebangkrutan. Jenis penelitian ini termasuk penelitian kuantitatif. Populasi dalam penelitian ini adalah perusahaan property dan real estate yang terdaftar di BEI. Teknik pengambilan sampel menggunakan purposive sampling sehingga diperoleh sampel sejumlah 32 perusahaan property dan real estate yang menerbitkan laporan keuangannya selama tahun 2011-2013. Teknik analisis data menggunakan regresi logisti...

Mirror Advanced Reactor Study interim design report

Energy Technology Data Exchange (ETDEWEB)

1983-04-01

The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design.

Mirror Advanced Reactor Study interim design report

International Nuclear Information System (INIS)

1983-04-01

The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design

ANALISIS KINERJA COOLING TOWER 8330 CT01 PADA WATER TREATMENT PLANT-2 PT KRAKATAU STEEL (PERSERO. TBK

Directory of Open Access Journals (Sweden)

Hutriadi Pratama Siallagan

2017-11-01

Full Text Available Pada proses produksi baja sangat erat kaitannya dengan pendinginan baik untuk proses pendinginan baja maupun pendinginan mesin-mesin produksi supaya terhindar dari over heat sehingga dapat bekerja dengan optimal. Pada PT Krakatau Steel menggunakan beberapa sistem pendingin salah satunya adalah sistem pendingin cooling tower 8330 CT 01. Sistem pendingin tersebut digunakan untuk menunjang proses produksi dan juga pendinginanan mesin produksi khusunya pada Slab Steel Plant (SSP, dengan peran yang sangat besar maka cooling tower 8330 CT 01 harus diketahui bagaimana kinerjanya. Skripsi ini membahas tentang analisis kinerja Cooling tower 8330 CT 01 dengan membandingkan data teori dengan data aktual berdasarkan perhitungan-perhitungan sehingga dapat diketahui bagaimana kinerja dari Cooling tower 8330 CT 01 tersebut. Dari hasil analisis diperoleh penurunan efisiensi sebesar 22,353%, kapasitas pendinginan 7.033,35 Kj/s, Hal tersebut diakibatkan oleh temperatur air yang masuk Cooling tower 8330 CT 01 tidak terlalu tinggi, karena SSP sedang dalam pengerjaan revitatalisi, agar lebih efektif dan efisien Cooling tower 8330 CT 01 sebaiknya lebih dimamfaatkan lagi untuk pendingin objek lainnya sehingga temperatur air yang masuk tidak terlalu rendah.

ANALISIS GEN HAEMAGGLUTININ PADA VIRUS CAMPAK LIAR

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Subangkit Subangkit

2015-05-01

Full Text Available AbstrakPenyakit Campak disebabkan oleh virus campak yang termasuk genus Morbilivirus dan Family Paramyxoviridae. Penyakit campak masih menjadi masalah kesehatan karena masih ditemukan Kejadian Luar Biasa (KLB di Indonesia. Salah satu penyebab terjadinya KLB tersebut diduga sebagaiakibat perbedaan antigenesitas antara strain vaksin yang digunakan dengan strain virus campak liar yang beredar di Indonesia. Penelitian ini bertujuan mendapatkan gambaran tentang karakteristik genetik gen Haemagglutinin virus campak liar yang ada di Indonesia. Spesimen yang digunakan sebanyak 27 isolat virus penyebab KLB dari 17 propinsi selama periode tahun 2003-2010. Isolat virus dilakukan pemeriksaan secara RT-PCR dan sekuensing dengan metode Sanger. Hasil sekuensing dianalisis dengan menggunakan perangkat lunak Bioedit 7.0 dan MEGA 4.0. Hasil penelitian didapatkan perbedaan 10 asam amino antara virus campak strain vaksin CAM-70 dan virus campak liar pada posisi D416N; K424T; V451M; N455T; V466I; I473T; F476L; Y481S atau Y481N; H495N; G505D. Kesimpulan penelitian ini adalah terdapat perbedaan karakteristik genetik antara virus campak liar di Indonesia berbeda dengan strain virus vaksin CAM-70.Kata kunci : Campak, Analisis Molekuler, Hemagglutinin, CD46AbstractMeasles is caused by virus belonging to the genus Morbilivirus and Family Paramyxoviridae. Measles is still a public health problem because outbreak of measles still found in Indonesia. Outbreak is suspected as a result of differences in antigenicity between vaccine strains used with wild-type measles virus strains circulating in Indonesia. This study aims to get genetic characteristics of wild-type measles virus haemagglutinin gene in Indonesia. The specimens were used 27 viral isolates from 17 provinces period 2003-2010. Viral isolates examined by RT-PCR and sequencing with Sanger method. Sequencing analysis were conducted using Bioedit 7.0 and MEGA 4.0 software. The results showed 10 amino acid differences

Introducing small modular reactors into Canada

International Nuclear Information System (INIS)

Humphries, J.R.

2012-01-01

the reactor facility. Because of this the CNSC has stated publicly in a variety of presentations and meetings that it is prepared now to license small reactor projects and that they expect that SMRs can be licensed in Canada in less time than would be required in the U.S. They have urged SMR vendors to bring their designs to Canada and to engage with them in the rather unique pre-licensing Vendor Design Review process that is available in Canada. Notwithstanding the rather 'promotional' licensing stance being taken by the CNSC, there remains a significant level of uncertainty around the many other issues that need to be addressed to successfully introduce an SMR into Canada. These include, among other things and in no particular order: safety; risk (licensing, economic, schedule, public perception); economics (is economy of scale offset by modular fabrication, serial introduction); siting (remote or industrial complex); design and engineering (FOAK or prototype); manufacturing/construction (central fabrication facility, who gets 'construction' license); staffing (number, training); operations (who owns, who operates); maintenance and refuelling (on-site refuelling allowed or at central facility, what level of maintenance required); and decommissioning (on-site or centralized storage of waste, decommissioning funds). Addressing these and other infrastructure issues will need to be a key part of any considerations given to the possible introduction of Small Modular Reactors into Canada.

Connected analysis nuclear-thermo-hydraulic of parallel channels of a BWR reactor using distributed computation; Analisis acoplado nuclear-termohidraulico de canales paralelos de un reactor BWR empleando computacion distribuida

Energy Technology Data Exchange (ETDEWEB)

Campos Gonzalez, Rina Margarita

2007-07-15

This work consists of the integration of three models previously developed which are described widely in Literature: model of the thermo-hydraulic channel, model of the modal neutronic and the model of the recirculation bows. The tool used for this connection of models is the PVM system, Parallel Virtual Machine that allowed paralleling the model by means of the concept of distributed computation. The purpose of making this connection of models is the one of obtaining a more complete tool than better represents the real configuration and the phenomenology of the nucleus of a BWR reactor, thus obtaining better results. In addition to maintaining the flexibility to improve the resulting model at any time, since the very complex or sophisticated models are difficult to improve being impossible to modify the equations they use and can include variables that are not of primary importance in the tackled problem or that mask relations among variables due to the excess of results. Also maintaining the flexibility for adding component of models or systems of the BWR reactor, all of this following the modeling needs. The Swedish Ringhals power plant was chosen to characterize the resulting connected model for counting on a Stability Benchmark that offers the opportunity to count on real plant data. Besides that in case 9 of cycle 14 of this Benchamark oscillations outside phase appeared, which are from great interest because the detection systems that register the average of the power of the nucleus do not detect them. Additionally in this work the model of the recirculation bows as an independent module is obtained in an individual way, since this model belongs to another work and works connected to the reactor vessel. The model of the recirculation bows is able to model several transients of interest, as it is shown in the Appendix A of this work, among which are found the tripping of recirculation pumps or the transference at low or high velocity of them. The scope of the

Nuclear reactors

International Nuclear Information System (INIS)

Prescott, R.F.

1976-01-01

In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

Adaptation and implementation of the TRACE code for transient analysis in designs lead cooled fast reactors; Adaptacion y aplicacion del codigo TRACE para el analisis de transitorios en disenos de reactores rapidos refrigerados por plomo

Energy Technology Data Exchange (ETDEWEB)

Lazaro, A.; Ammirabile, L.; Martorell, S.

2015-07-01

Lead-Cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in the technology road map of the Generation IVC International Forum (GIF)as well as in the Deployment Strategy of the European Sustainable Nuclear Industrial Initiative (ESNII), both aiming at improved sustainability, enhanced safety, economic competitiveness, and proliferation resistance. This new nuclear reactor concept requires the development of computational tools to be applied in design and safety assessments to confirm improved inherent and passive safety features of this design. One approach to this issue is to modify the current computational codes developed for the simulation of Light Water Reactors towards their applicability for the new designs. This paper reports on the performed modifications of the TRACE system code to make it applicable to LFR safety assessments. The capabilities of the modified code are demonstrated on series of benchmark exercises performed versus other safety analysis codes. (Author)

Use of research reactors in multidisciplinary education at Cornell University

International Nuclear Information System (INIS)

Clark, D.D.

1992-01-01

Multidisciplinary aspects of nuclear science and technology form a large part of the research and teaching activities of the Nuclear Science and Engineering (NS and E) Program at Cornell, and the two reactors housed in Ward Laboratory - a 500-kW TRIGA and a 100-W critical facility [zero-power reactor (ZPR)]- play a central role in those activities. Several primarily educational and multidisciplinary features of the NS and E program are described in this paper

High power density reactors based on direct cooled particle beds

Science.gov (United States)

Powell, J. R.; Horn, F. L.

Reactors based on direct cooled High Temperature Gas Cooled Reactor (HTGR) type particle fuel are described. The small diameter particle fuel is packed between concentric porous cylinders to make annular fuel elements, with the inlet coolant gas flowing inwards. Hot exit gas flows out along the central channel of each element. Because of the very large heat transfer area in the packed beds, power densities in particle bed reactors (PBRs) are extremely high resulting in compact, lightweight systems. Coolant exit temperatures are high, because of the ceramic fuel temperature capabilities, and the reactors can be ramped to full power and temperature very rapidly. PBR systems can generate very high burst power levels using open cycle hydrogen coolant, or high continuous powers using closed cycle helium coolant. PBR technology is described and development requirements assessed.

Molten salt reactors and possible scenarios for future nuclear power deployment

International Nuclear Information System (INIS)

Merle-Lucotte, E.; Mathieu, L.; Heuer, D.; Loiseaux, J. M.; Billebaud, A.; Brissot, R.; David, S.; Garzenne, C.; Laulan, O.; Le Brun, C.; Lecarpentier, D.; Liatard, E.; Meplan, O.; Michel-Sendis, F.; Nuttin, A.; Perdu, F.

2004-01-01

An important fraction of the nature energy demand may be satisfied by nuclear power. In this context, the possibilities of worldwide nuclear deployment are studied. We are convinced that the Molten Salt Reactors may play a central role in this deployment. The Molten Salt Reactor needs to be coupled to a reprocessing unit in order to extract the Fission Products which poison the core. The efficiency of this reprocessing has a crucial influence on reactor behavior especially for the breeding ratio. The Molten Salt Breeder Reactor project was based on an intensive reprocessing for high breeding purposes. A new concept of Thorium Molten Salt Reactor is presented here. Including this new concept in the worldwide nuclear deployment, to satisfy these power needs, we consider three typical scenarios, based on three reactor types: Pressurized Water Reactor, Fast Neutron Reactor and Thorium Molten Salt Reactor. The aim of this paper is to demonstrate, in a first hand that a Thorium Molten Salt Reactor can be realistic, with correct temperature coefficients and at least iso-breeder with slow reprocessing and new geometry; on the other hand that such Molten Salt Reactors enable a successful nuclear deployment, while minimizing fuel and waste management problems. (authors)

ANALISIS PENGGUNAAN FILTER AKTIF SHUNT UNTUK MENANGGULANGI THD DI RSUP SANGLAH

Directory of Open Access Journals (Sweden)

I Wayan Rinas

2009-12-01

Full Text Available Rumah Sakit Umum Pusat Sanglah (RSUP memiliki tingkat THD (Total Harmonics Distortion  arus yang tidak sesuai dengan standar IEEE 159-1992. THD arus yang berlebih dapat menyebabkan berbagai kekurangan. Untuk mengatasi masalah ini digunakan filter aktif shunt berbasis inverter. Dalam penelitian ini dilakukan simulasi penggunaan filter aktif menggunakan sofware simulink MATLAB 7.0.4 Hasil analisis menunjukan pemasangan filter aktif menyebabkan terjadi penurunan kandungan THD arus dan THD tegangan pada feeder yang bermasalah. Kandungan THD arus dan THD tegangan telah sesuai dengan IEEE 152-1992. Daya distorsi harmonisa pada sistem mengalami penurunan dan terjadi peningkatan faktor daya mendekati unity power factor pada feeder.

Reactor IPEN/MB-01 dosimetry using TLDs

Energy Technology Data Exchange (ETDEWEB)

Cavalieri, Tássio A.; Siqueira, Paulo T.D.; Yoriyaz, Hélio, E-mail: tassio.cavalieri@usp.br [Instituto de Pesquisas Energética s e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

This paper is a preliminary study on the use of reactor IPEN/MB-01 as standard radiation source for mixed field dosimetry studies. As a first step on this attempt, simulations and experiments, evaluating the neutron and gamma field distributions, were performed and compared. TLDs are widely employed in dose measurements and the TLD 100 / TLD 700 pair conforms with ICRU recommendations for mixed field dosimetry. In this study, TLD irradiations were performed in the IPEN/MB-01 nuclear reactor. IPEN/MB-01 reactor is zero power reactor widely used to perform reactor physics experiments. Its neutron flux distribution is well known for a variety of reactor core configurations. However, the photon fluxes are unknown. A series of experiments with TLD 100 and TLD 700 were performed for two different core configurations (rectangular and cylindrical with a central flux trap). Simulations with MCNP5 for these two configurations were also done, and neutron and gamma fluxes distributions along the core were computed. The responses of TLD 100 and TLD 700 were compared with simulated fluxes and showing a good agreement between them. This paper presents the results of the experiments done so far given the status of the study under way in order to couple IPEN/MB-01 and TLD 100 / 700 pair into a mixed field calibration methodology. (author)

HIGH TEMPERATURE, HIGH POWER HETEROGENEOUS NUCLEAR REACTOR

Science.gov (United States)

Hammond, R.P.; Wykoff, W.R.; Busey, H.M.

1960-06-14

A heterogeneous nuclear reactor is designed comprising a stationary housing and a rotatable annular core being supported for rotation about a vertical axis in the housing, the core containing a plurality of radial fuel- element supporting channels, the cylindrical empty space along the axis of the core providing a central plenum for the disposal of spent fuel elements, the core cross section outer periphery being vertically gradated in radius one end from the other to provide a coolant duct between the core and the housing, and means for inserting fresh fuel elements in the supporting channels under pressure and while the reactor is in operation.

Nuclear reactor instrumentation power monitor

International Nuclear Information System (INIS)

Suzuki, Shigeru.

1989-01-01

The present invention concerns a nuclear reactor instrumentation power monitor that can be used in, for example, BWR type nuclear power plants. Signals from multi-channel detectors disposed on field units are converted respectively by LPRM signal circuits. Then, the converted signals are further converted by a multiplexer into digital signals and transmitted as serial data to a central monitor unit. The thus transmitted serial data are converted into parallel data in the signal processing section of the central monitor unit. Then, LPRM signals are taken out from each of channel detectors to conduct mathematical processing such as trip judgment or averaging. Accordingly, the field unit and the central monitor unit can be connected by way of only one data transmission cable thereby enabling to reduce the number of cables. Further, since the data are transmitted on digital form, it less undergoes effect of noises. (I.S.)

Digital computer control of a research nuclear reactor

International Nuclear Information System (INIS)

Crawford, Kevan

1986-01-01

Currently, the use of digital computers in energy producing systems has been limited to data acquisition functions. These computers have greatly reduced human involvement in the moment to moment decision process and the crisis decision process, thereby improving the safety of the dynamic energy producing systems. However, in addition to data acquisition, control of energy producing systems also includes data comparison, decision making, and control actions. The majority of the later functions are accomplished through the use of analog computers in a distributed configuration. The lack of cooperation and hence, inefficiency in distributed control, and the extent of human interaction in critical phases of control have provided the incentive to improve the later three functions of energy systems control. Properly applied, centralized control by digital computers can increase efficiency by making the system react as a single unit and by implementing efficient power changes to match demand. Additionally, safety will be improved by further limiting human involvement to action only in the case of a failure of the centralized control system. This paper presents a hardware and software design for the centralized control of a research nuclear reactor by a digital computer. Current nuclear reactor control philosophies which include redundancy, inherent safety in failure, and conservative yet operational scram initiation were used as the bases of the design. The control philosophies were applied to the power monitoring system, the fuel temperature monitoring system, the area radiation monitoring system, and the overall system interaction. Unlike the single function analog computers that are currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control rod movements to conform with operator requests, automatically log the required physical parameters during reactor

Capital cost: pressurized water reactor plant. Commercial electric power cost studies

Energy Technology Data Exchange (ETDEWEB)

1977-06-01

The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description.

Capital cost: pressurized water reactor plant. Commercial electric power cost studies

International Nuclear Information System (INIS)

1977-06-01

The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description

Comparison of control systems applied to the handling of radioactive reactor components

International Nuclear Information System (INIS)

Robinson, C.; Harris, E.G.; Dyer, P.C.; Williams, J.G.B.

1985-01-01

The first generation of nuclear power stations have individual reactors each incorporating complete facilities for servicing components and refuelling. In the later designs, each power station has two reactors which are connected by a central block. This central block contains one set of facilities to service both reactors, but to improve the station capability, some of these are to be replicated. The central block incorporates a hoist well which was used during construction for the accessing of complete components. On completion of this work, the physical size of the hoist well is such as to permit the incorporation of additional facilities if these are shown to be operationally and economically desirable. Since a number of years of power operation has elapsed, the advantages of back-fitting to existing fuel-handling facilities has been illustrated. Since the mechanical arrangements and operating procedures are substantially similar for both the original and new handling facilities, the paper will illustrate the control systems provided for each. The configuration of the system is arranged to have two channels of control which complies with the current standard requirements in the United Kingdom. These requirements are more stringent than when the existing facility was designed and constructed, as described in the relevant sections of the paper. The new system has been designed and is being manufactured to comply with the Central Electricity Generating Board standard for nuclear fuel route interlock and control systems. (author)

ANALISIS PENJUALAN LEMARI ES MEREK LG PADA PT. LG ELECTRONICS INDONESIA CABANG PEKANBARU

Directory of Open Access Journals (Sweden)

Hadiyati Hadiyati

2015-04-01

Full Text Available Abstrak: PT. LG Electronics Indonesia Cabang Pekanbaru merupakan salah satu perusahaan perdagangan yang menjual berbagai macam produk elektronik termasuk  Lemari Es. Penelitian ini bertujuan untuk: (1. Mengetahui penjualan yang dilakukan oleh manajemen PT. LG Electronics Indonesia Cabang Pekanbaru. (2. Mengetahui faktor-faktor yang menyebabkan tidak tercapainya target penjualan Lemari Es Merek LG Pada PT. LG Electronics Indonesia Cabang Pekanbaru. Populasi dalam penelitian ini adalah keseluruhan dari objek yaitu seluruh konsumen Lemari Es merek LG pada PT. LG Electronics Indonesia Cabang Pekanbaru pada tahun 2013 yaitu sebanyak 8.563 orang. Karena keterbatasan penulis, maka diambil sampel yang dianggap mewakili pelanggan yaitu sebanyak 100 orang dengan rumus slovin. Analisis data dilakukan dengan menggunakan metode Analisis Deskriptif. Variabel yang digunakan adalah produk, harga, dan promosi. Berdasarkan hasil penelitian diperoleh, tidak tercapainya target penjualan Lemari Es merek LG pada PT. LG Electronics Indonesia Cabang Pekanbaru karena produk yang ditawarkan belum sepenuhnya sesuai dengan keinginan dan harapan konsumen, harga yang ditawarkan belum sepenuhnya sesuai dengan kondisi ekonomi masyarakat secara umum, serta promosi yang belum maksimal. Abstract: PT. LG Electronics Indonesia Branch of Pekanbaru is one trading company that sells a wide range of electronic products including Refrigerator. This study aims to: (1. Knowing the sales made by the management of PT. LG Electronics Indonesia Branch of Pekanbaru. (2. Knowing the factors that leads failure to achieve sales targets Refrigerator Brand LG At PT. LG Electronics Indonesia Branch of Pekanbaru. The population in this study is the whole of the object that is the entire consumer Refrigerator LG brand in the PT. LG Electronics Indonesia Pekanbaru Branch in 2013 as many as 8563 people. Because of the limitations of the author, then a swab which is considered to represent the customer

Limits and conditions for permanent operation of the LVR-15 reactor

International Nuclear Information System (INIS)

1995-03-01

The ''Limits and Conditions'' have been set up to demonstrate compliance with all nuclear safety requirements specified by the Decree of the Czechoslovak Atomic Energy Commission No. 9/1985, and to serve as a guide for the reactor operators to respond adequately to deviations from the required values in normal operation conditions. The publications is divided into the following chapters: (1) Safety limits of the LVR-15 reactor; (2) Adjusting the reactor protection and control system parameters; (3) Limiting conditions for normal operation modes; (4) Control requirements; and (5) reactor operation management. A document by the Institute for Research, Production, and Application of Radioisotopes specifying conditions for the acceptance of radioactive wastes to the central repository is appended. (P.A.). 7 tabs

McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: Four years of operations

International Nuclear Information System (INIS)

Heidel, C.C.; Richards, W.J.

1994-01-01

McClellan Air Force Base, at Sacramento, California, is headquarters for the Sacramento Air Force Logistics Center (SM-ALC). McClellan Air Force Base provides extensive inspection and maintenance capabilities for the F-111, F-1 5, and other military aircraft. Criticality of the MNRC TRIGA reactor was obtained on January 20, 1990 with 63 standard TRIGA fuel elements, three fuel-followed control rods and one air-followed control rod. Presently there are 93 fuel elements in the reactor core. The reactor can be operated at 1 MW steady state power, producing pulses up to three dollars worth of reactivity addition, and can be square waved up to 1 MW. The reactor core contains a circular grid plate and a graphite reflector assembly surrounding the core. Four tangential beam ports installed in the reflector assembly provide a thermal neutron flux to four radiography bays. The reactor tank is twenty-four (24) feet deep, seven and one-half (7.5) feet in diameter, and has a protrusion in the upper portion of the reactor tank. This protrusion is scheduled for use as a neutron thermal collimator in the future. Besides the neutron radiography capabilities, the reactor contains a pneumatic rabbit system, a central thimble, an in-core irradiation facility, and three additional cutouts that provide locations for additional irradiation facilities. The central thimble can be removed along with the B-ring locations of the upper portion of the grid plate to provide an additional and larger in-core irradiation facility. A new upper grid plate has been manufactured to expand one triangular cutout so that larger experiments can be inserted directly into the reactor core. Some operational problems experienced during the first four years of operations are the timeout of the CSC and DAC watchdogs, deterioration of the heat exchanger gaskets, and loss of thermocouples in the instrumented fuel elements. (author)

Nonlinear analysis of thermal stresses of a of first stage nozzle of a gas turbine at full load from the results of an analysis of conjugated heat transference; Analisis no lineal de esfuerzos termicos de una tobera de primera etapa de turbina de gas a plena carga a partir de resultados de un analisis de transferencia de calor conjugado

Energy Technology Data Exchange (ETDEWEB)

Perez Hernandez, Efrain [Centro Nacional de Investigacion y Desarrollo Tecnologico (Cenidet), Cuernavaca, Morelos (Mexico); Mazur C, Zdzislaw; Garcia Illescas, R; Hernandez Rossette, Alejandro [Instituto de Investigaciones Electricas, Cuernavaca, Morelos (Mexico)

2007-11-15

The gas turbines operate at extremely high temperatures, at high thermal and mechanical stresses, causing that the useful life of the involved components be reduced. In the present article the results realized by previous investigations of temperatures obtained from analysis of heat transfer and flow of fluids of the nozzle by means of the Star-CD program based on finite volumes is presented. Later, the NISA program of finite elements was used to realize the analysis of thermal stresses considering the material plasticity. The methodology employed to determine the material properties variable with the temperature of the super-alloy FSX-414 and the plasticity model used in the structural analysis in the finite element program. The result will be later used in the fatigue analysis for the useful life assessment. [Spanish] Las turbinas de gas operan a temperatura extremadamente altas, a elevados esfuerzos termicos y mecanicos, ocasionando que la vida de los componentes involucrados se reduzca. En el presente articulo se presentan los resultados realizados por previas investigaciones de temperaturas obtenidas a partir de analisis de transferencia de calor y flujo de fluidos de la tobera mediante el programa Star-CD basado en volumenes finitos. Posteriormente, se utilizo el programa NISA de elementos finitos para realizar el analisis de esfuerzos termicos considerando plasticidad del material. Se muestra la metodologia empleada para determinar las propiedades del material variables con la temperatura de la superaleacion FSX-414 y el modelo de plasticidad utilizado en el analisis estructural en el programa de elemento finito. Los resultados seran empleados posteriormente en el analisis de fatiga para la estimacion de vida util.

DESAIN KONSEP TANGKI PENAMPUNG BAHAN BAKAR PASSIVE COMPACT MOLTEN SALT REACTOR

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A. Hadiwinata

2015-04-01

Full Text Available Passive Compact Molten Salt Reactor (PCMSR merupakan pengembangan dari reaktor MSR. Desain reaktor PCMSR membutuhkan tempat khusus penampung sementara bahan bakar pada saat terjadi insiden, misalnya kecelakaan yang menyebabkan peningkatan suhu bahan bakar. Tangki penampung bahan bakar tersusun dari 3 bagian yang saling terhubung yaitu bagian penampung cairan bahan bakar, cerobong (chimney, dan penukar kalor. Dalam penelitian ini, tangki dimodelkan secara lump dan dilakukan variasi daya awal reaktor dan ketinggian cerobong. Syarat batas model ditetapkan suhu bahan bakar maksimum 1400 °C, yang didasarkan pada titik didih larutan garam LiF-BeF2-ThF4-UF4. Analisis dilakukan dengan cara menghitung rugi tekanan total dan transfer kalor untuk variasi daya awal antara 1800-3000 MWth dan ketinggian cerobong antara 1-10 m. Hasil penelitian menunjukan semakin besar daya reaktor, maka tinggi tangki penampung bahan bakar dan tinggi alat penukar kalor yang dibutuhkan akan semakin besar, tejadi kenaikan suhu fluida pendingin dan suhu udara pendingin, dan menyebabkan kenaikan laju aliran masa fluida pendingin, sedangkan laju aliran masa udara menurun. Peningkatan ketinggian cerobong menyebabkan ketinggian tangki penampung bahan bakar dan ketinggian alat penukar kalor semakin menurun, penurunan suhu fluida pendingin, tetapi suhu udara meningkat, dan menyebabkan peningkatan laju aliran masa fluida pendingin, tetapi laju aliran masa udara akan semakin menurun. Kata kunci: PCMSR, cerobong, alat penukar kalor, variasi daya.   The Passsive Compact Molten Salat Reactor (PCMSR reactor is developed from MSR reactor. The PCMSR reactor design requires special place to temporarily storage for reactor fuel when incident occurs, such as when there is an accident which caused the temperature of the fuel increases. The tank consist of three interconnected parts, the reservoir liquid fuel, chimney, and the heat exchanger. In this research, the tank system is modeled based on

Studies on the properties of hard-spectrum, actinide fissioning reactors. Final report

International Nuclear Information System (INIS)

Nelson, J.B.; Prichard, A.W.; Schofield, P.E.; Robinson, A.H.; Spinrad, B.I.

1980-01-01

It is technically feasible to construct an operable (e.g., safe and stable) reactor to burn waste actinides rapidly. The heart of the concept is a driver core of EBR-II type, with a central radial target zone in which fuel elements, made entirely of waste actinides are exposed. This target fuel undergoes fission, as a result of which actinides are rapidly destroyed. Although the same result could be achieved in more conventionally designed LWR or LMFBR systems, the fast spectrum reactor does a much more efficient job, by virtue of the fact that in both LWR and LMFBR reactors, actinide fission is preceded by several captures before a fissile nuclide is formed. In the fast spectrum reactor that is called ABR (actinide burning reactor), these neutron captures are short-circuited

High aspect ratio catalytic reactor and catalyst inserts therefor

Science.gov (United States)

Lin, Jiefeng; Kelly, Sean M.

2018-04-10

The present invention relates to high efficient tubular catalytic steam reforming reactor configured from about 0.2 inch to about 2 inch inside diameter high temperature metal alloy tube or pipe and loaded with a plurality of rolled catalyst inserts comprising metallic monoliths. The catalyst insert substrate is formed from a single metal foil without a central supporting structure in the form of a spiral monolith. The single metal foil is treated to have 3-dimensional surface features that provide mechanical support and establish open gas channels between each of the rolled layers. This unique geometry accelerates gas mixing and heat transfer and provides a high catalytic active surface area. The small diameter, high aspect ratio tubular catalytic steam reforming reactors loaded with rolled catalyst inserts can be arranged in a multi-pass non-vertical parallel configuration thermally coupled with a heat source to carry out steam reforming of hydrocarbon-containing feeds. The rolled catalyst inserts are self-supported on the reactor wall and enable efficient heat transfer from the reactor wall to the reactor interior, and lower pressure drop than known particulate catalysts. The heat source can be oxygen transport membrane reactors.

Conceptual design of the SlimCS fusion DEMO reactor

International Nuclear Information System (INIS)

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Utoh, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; Sakurai, Shinji; Kurita, Genichi; Hayashi, Takao; Oyama, Naoyuki; Liu Changle; Hamamatsu, Kiyotaka; Inoue, Takashi; Ozeki, Takahisa; Sato, Masayasu; Suzuki, Satoshi; Kawashima, Hisato; Ezato, Koichiro; Tsuru, Daigo; Koizumi, Norikiyo; Sakamoto, Keiji; Ando, Masami; Sakamoto, Yoshiteru; Shibama, Yusuke; Suzuki, Takahiro; Takechi, Manabu; Takahashi, Koji; Hirose, Takanori; Sato, Satoru; Nozawa, Takashi; Tanigawa, Hisashi; Kakudate, Satoshi; Kawamura, Yoshinori; Yamanishi, Toshihiko; Hoshino, Tsuyoshi; Ochiai, Kentaro; Ide, Shunsuke; Aiba, Nobuyuki; Shimizu, Katsuhiro; Honda, Mitsuru; Nakamichi, Masaru; Nishi, Hiroshi; Seki, Yoji; Nakamura, Yukiharu; Tsuchiya, Kunihiko; Yoshida, Tohru; Song Yuntao

2010-08-01

This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). Owing to low aspect ratio, the reactor will be capable of having comparatively high beta limit and high elongation (which can elevate the Greenwald density limit), having potential for high power density. The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m 2 . This report covers various aspects of design study including systematic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept. (author)

Research projects at the TRIGA-reactor Vienna

International Nuclear Information System (INIS)

Boeck, H.; Buchberger, T.; Buchtela, K.; Hammer, J.; Miksovsky, A.; Veider, A.; Weber, H.W.; Zugarek, G.

1986-01-01

In 1985 the thermalizing column was modified to a beam tube with a conical collimator for neutron radiography. A highly sophisticated sample and cassette changer will be constructed in the next months. The central channel of the thermal column is also used for neutron radiography especially for small objects. The four beam tubes of the TRIGA-reactor are intensively used for neutron spectroscopy, small angle scattering, neutron interferometry and investigations of magnetic structures with polarized neutrons. The neutron activation installation in the piecing beam tube is permanently used for various sample analysis using a ultrafast pneumatic transfer system. In addition to these experiments directly related to the TRIGA-reactor other research projects are carried out, some of them under an IAEA research contract which are mostly focused towards nuclear safeguards such as the magnetic scanning of power reactor fuel assemblies or the laser surveillance system of spent fuel pools. (author)

Kajian Eksperimental Parameter Modal Bangunan Dua Lantai dengan Metode Modal Analisis

Directory of Open Access Journals (Sweden)

Islahuddin Islahuddin

2016-12-01

Full Text Available Abstrak: Pengukuran getaran merupakan kegiatan yang umum dilakukan dalam perawatan prediktif. Perawatan prediktifbiasanya menggunakan pengukuran sinyal getaran untuk mendeteksi kerusakan yang terjadi pada mesin. Sinyalgetaran yang terukur tersebut, kemudian ditransformasikan dalam bentuk grafik fungsi respon frekuensi (FRF.Selanjutnya FRF diolah sedemikian rupasehingga diperoleh modus getar struktur. Dari modus getar yang diperoleh,maka dapat dianalisa kemungkinan kerusakan yang terjadi pada mesin dengan melihat besarnya amplitudo getarannya.Penelitian ini bertujuan untuk menganalisa karakteristik dinamik dari sistem getaran yang terjadi pada model strukturbangunan dua lantai. Pengujian dilakukan denganmemberikan gaya eksitasi menggunakan impact hammer.Akselerometer digunakan mengukur sinyal getaran yang terjadi pada struktur. Posisi penempatan akselerometerdilakukan bervariasi untuk delapan titik pengujian yang berbeda. Sedangkan posisi pemberian gaya eksitasi tetap untuksemua titik pengujian. Pada penelitian ini menggunakan metode modal analisis eksperimen untuk mengetahuikarakteristik dinamik dari model struktur bangunan dua lantai. Teknik modal analisis ini digunakan untuk mendapatkanparameter modal seperti frekuensi, rasio redaman, dan modus getar. Hasil yang diperoleh dari penelitian inimenunjukkan bahwafrekuensi pribadipertama pada amplitudo maksimum mempunyai nilai yang sama, yaitu 2,313 Hz.Sedangkan untuk frekuensi pribadi kedua pada amplitudo maksimumnya terdapat perbedaan, yaitu pada titik pengujian3 dan 7. Hal ini dapat disebabkan oleh pemberian gaya eksitasi yang tidak sama dengan titik-titik pengujian yang lain.Kata kunci: Karakteristik dinamik, analisis modal eksperimen, frekuensi pribadi, FRF Abstract: Measuring vibration is an activity which is generally carried out in a predictive maintenance. In maintaining, vibratesignal measurement is usually used for machine damage detection. The signal measurement is then being

Penggunaan Kontrasepsi pada Remaja Perempuan Kawin di Indonesia (Analisis Riskesdas 2013

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Anissa Rizkianti

2017-12-01

Full Text Available AbstractAdolescent pregnancy has been highlighted in various parts of the world including access to contraceptive use among married teenagers. This is an advanced analysis of secondary data of Riskesdas 2013 that aims to identify contraceptive use among married adolescents in Indonesia. The data used in multilevel logistic regression analysis consist of demographic characteristics of adolescents, parity, availability of health services and the use of health insurance.. The results showed that 54.2% of married adolescents women or their partners used any method of contraception. Age, education level, socioeconomic status and the use of health insurance have significant relationships to contraceptive use after adjusted by the type of residence, parity and availability of health services. Adolescent aged above 17 years (OR=1.49, 95% CI 1.25 to 1.79 and had higher socio-economic status (OR kuintil 5=1.62, 95% CI 1,19- 2.22 were more likely to use contraception, while young women with higher school education (OR= 0.73; 95% CI .58-.91 as well as used health insurance (OR=0.72; 95 % CI 0.60 to 0.86 had smaller probability in contraceptive use. Fulfillment of adolescent access to contraception is expected to focus not only on increasing of knowledge but also purchasing power, which is through the utilisation of health insurance.Key words: contraception, married adolescents, RiskesdasAbstrakKehamilan remaja telah menjadi sorotan di berbagai belahan dunia, termasuk akses terhadap penggunaan kontrasepsi pada remaja kawin. Studi ini merupakan analisis lanjut Riskesdas 2013 untuk mengetahui penggunaan kontrasepsi pada remaja kawin di Indonesia. Data yang digunakan dalam analisis regresi logistik multi level terdiri atas karakteristik demografi remaja, paritas, ketersediaan pelayanan kesehatan serta penggunaan jaminan kesehatan. Subjek adalah seluruh remaja perempuan berusia 15-19 tahun yang berstatus kawin dan aktif secara seksual. Hasil menunjukkan bahwa

KERAGAAN WARNA IKAN CLOWN BIAK (Amphiprion percula) POPULASI ALAM DAN BUDIDAYA BERDASARKAN ANALISIS GAMBAR DIGITAL

OpenAIRE

Ruby Vidia Kusumah; Sawung Cindelaras; Anjang Bangun Prasetio

2015-01-01

Penelitian ini bertujuan untuk mengkaji keragaan warna ikan clown Biak (Amphiprion percula) populasi alam dan budidaya berdasarkan analisis gambar digital sebagai dasar upaya pemuliaannya. Gambar digital diambil dari koleksi ikan clown Biak Balai Besar Perikanan Budidaya Laut Lampung, Balai Besar Penelitian dan Pengembangan Budidaya Laut Gondol, Bali; serta pengumpul ikan hias di Denpasar, Bali menggunakan kamera digital Canon EOS 600D. Pola warna dikarakterisasi secara visual terhadap varias...

Genusa Bepu methodologies for the safety analysis of BWRs; Metodologias Bepu de Genusa para el analisis de seguridad de reactores BWR

Energy Technology Data Exchange (ETDEWEB)

Trueba, M.; Garcia, J.; Goodson, C.; Ibarra, L.

2016-08-01

This article describes the BEPU methodologies developed by General Electric-Hitachi (GEH) for the evaluation of the BWR reactor safety analysis based on the TRACG best-estimate code. These methodologies are applicable to a wide range of events, operational transients (AOO), anticipated transients without scram (ATWS), loss of coolant accidents (LOCA) and instability events; to different BWR types operating commercially. General Electric (GE( designs and other vendors, including Generation III+ESBWR; to the new operation strategies, and to all types of BWR fuel. Their application achieves, among other benefits, a better understanding of the overall plant response and an improvement in margins to the operating limits; thus, the increase of flexibility in reactor operation and reduction in generation costs. (Author)

Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

Energy Technology Data Exchange (ETDEWEB)

Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

2009-07-01

The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

A novel method for in-situ estimation of time constant for core temperature monitoring thermocouples of operating reactors

International Nuclear Information System (INIS)

Sylvia, J.I.; Chandar, S. Clement Ravi; Velusamy, K.

2014-01-01

Highlights: • Core temperature sensor was mathematically modeled. • Ramp signal generated during reactor operating condition is used. • Procedure and methodology has been demonstrated by applying it to FBTR. • Same technique will be implemented for all fast reactors. - Abstract: Core temperature monitoring system is an important component of reactor protection system in the current generation fast reactors. In this system, multiple thermocouples are housed inside a thermowell of fuel subassemblies. Response time of the thermocouple assembly forms an important input for safety analysis of fast reactor and hence frequent calibration/time constant estimation is essential. In fast reactors the central fuel subassembly is provided with bare fast response thermocouples to detect under cooling events in reactor and take proper safety action. On the other hand, thermocouples in thermowell are mainly used for blockage detection in individual fuel subassemblies. The time constant of thermocouples in thermowell can drift due to creep, vibration and thermal fatigue of the thermowell assembly. A novel method for in-situ estimation of time constant is proposed. This method uses the Safety Control Rod Accelerated Mechanism (SCRAM) or lowering of control Rod (LOR) signals of the reactor along with response of the central subassembly thermocouples as reference data. Validation of the procedure has been demonstrated by applying it to FBTR

ANALISIS FAKTOR-FAKTOR YANG MEMPENGARUHI LOYALITAS PELANGGAN DAN DAMPAKNYA TERHADAP KEUNGGULAN BERSAING (STUDI PADA BMT AMANAH UMMAH SUKOHARJO

Directory of Open Access Journals (Sweden)

meyta pritandhari

2015-05-01

Full Text Available Abstrak   Baitul Maal Wat Tamwil merupakan salah satu model lembaga keuangan syariah yang saat ini banyak muncul di Indonesia. BMT Amanah Ummah memiliki 9.142 anggota dan 45 % anggotanya tidak loyal kepada BMT. Penelitian ini bertujuan untuk mengetahui faktor-faktor yang mempengaruhi loyalitas pelanggan dan dampaknya terhadap keunggulan bersaing. Penelitian ini menggunakan metode penelitian deskriptif dengan pendekatan analisis kualitatif dengan model analisis interaktif. Teknik sampling yang digunakan adalan insidental sampling untuk anggota BMT dan purposive sampling  untuk  pimpinan, manajer dan  marketing.  Teknik  pengumpulan  data yang digunakan yaitu wawancara, observasi dan dokumentasi. Hasil penelitian ini menunjukkan bahwa dari beberapa faktor yang mempengaruhi loyalitas pelanggan yaitu reputasi merek, kepuasan angggota, kualitas pelayanan, kualitas pelayanan berpengaruh positif terhadap kepuasan anggota, dan kualitas pelayanan. Dari beberapa faktor tersebut faktor kualitas pelayanan yang paling dominan dalam mempengaruhi loyalitas anggota.Dampak loyalitas terhadap keunggulan bersaing dapat dilihat dari seberapa banyak anggota BMT yang tidak pindah ke lembaga keuangan lain. Semakin bagus kualitas pelayanan maka semakin tinggi tingkat loyalitas dan keunggulan bersaing antar lembaga keuangan juga semakin tinggi.

RELAP5 SIMULATION FOR SEVERE ACCIDENT ANALYSIS OF RSG-GAS REACTOR

Directory of Open Access Journals (Sweden)

Andi Sofrany Ekariansyah

2018-01-01

SIMULASI RELAP5 UNTUK ANALISIS KECELAKAAN PARAH PADA REAKTOR RSG-GAS. Reaktor riset di dunia diketahui lebih aman dari pada reaktor daya karena desainnya yang lebih sederhana pada teras dan karakteristika operasinya. Namun demikian, potensi bahaya reaktor riset terhadap publik dan lingkungan tidak bisa diabaikan karena beberapa fitur tertentu. Oleh karena itu, level keselamatan reaktor riset harus jelas ditunjukkan dalam Laporan Analisis Keselamatan (LAK dalam bentuk analisis keselamatan yang dilakukan dengan berbagai macam pendekatan dan metode dan didukung dengan alat komputasi. Tujuan penelitian ini adalah untuk mensimulasikan beberapa kecelakaan parah pada reaktor RSG-GAS yang dapat menyebabkan kerusakan bahan bakar untuk memperkuat hasil analisis kecelakaan parah yang sudah ada dalam LAK. Simulation dilakukan dengan program perhitungan RELAP5/SCDAP/Mod3.4 yang memiliki kemampuan untuk memodelkan elemen bahan bakar tipe pelat di RSG-GAS. Tiga kejadian telah disimulasikan yaitu hilangnya aliran primer dan sekunder dengan kegagalan reaktor untuk dipadamkan, tersumbatnya beberapa kanal pendingin bahan bakar pada daya penuh, dan hilangnya aliran primer dan sekunder yang diikuti dengan tersumbatnya beberapa kanal pendingin bahan bakar setelah reaktor padam. Kejadian pertama akan membahayakan pelat bahan bakar dengan naiknya temperatur kelongsong hingga titik lelehnya yaitu 590 °C. Tersumbatnya satu atau beberapa kanal pada satu elemen bahan bakar menyebabkan konsekuensi yang berbeda pada pelat bahan bakar, dimana paling sedikit tersumbatnya 2 kanal akan merusak satu pelat bahan bakar, apalagi tersumbatnya satu elemen bahan bakar. Kombinasi antara hilangnya aliran pendingin primer dan sekunder yang diikuti dengan tersumbatnya satu kanal bahan bakar setelah reaktor dipadamkan menyebabkan naiknya temperatur kelongsong di bawah titik lelehnya yang berarti sirkulasi alam yang terbentuk dan daya yang terus turun cukup untuk mendinginkan elemen bahan bakar. Kata kunci

Out of operation in simultaneous way of the two reactors of nucleoelectric central of Laguna Verde(Mexico)

International Nuclear Information System (INIS)

Mar, Bernardo Salas

2013-01-01

The two nuclear reactors that Mexico has in the Laguna Verde Nuclear Power Plant, were out of operation simultaneously in September 2012. First it was reported that one of the reactors had problems with the diesel generator, while the other had problems with the nuclear fuel reloading. The day after it was reported a problem related to sediment in the Obra de Toma, place the plant feeds seawater to cool the condenser the depth to which it must operate is 6 meters, with the current level of 1.5 meters, causing a lack of cooling water. Finally it was reported the cause of the suspension of operations, the cracks in jet pumps in both reactors. It is described a brief analysis of these opinions. The reactors are of cooling water of General Electric (BWR-5) and generate 1640 MWe each one

Improvements in streaking nuclear reactors

International Nuclear Information System (INIS)

Pedrick, A.P.

1976-01-01

In this type of reactor atomic nuclei are stripped of their electron shells by heating to form a very high temperature plasma which is passed at high speed through a chamber in which they are forced into contact with a 'wall' formed by a unidirectional stream of photons from continuous laser beams. In this way it should be possible to brush off from the surface of the nuclei protons and neutrons, with release of their binding energy. The energy thus produced can be subjected to much more gentle control than with a fission or fusion reactor. Furthermore, if this concept can be successfully applied to elements of high atomic number which are normally regarded as stable and unfissionable, a vast new source of nuclear energy release will have been made available. It also seems possible that an atomic nucleus might be spun sufficiently in such a reactor to disintegrate it completely into nucleons by simple centrifugal action, with great release of binding energy. The reactor described has a central body with radial ducts through which the nuclei are passed, and a number of lasers are provided whose beams are arranged so that the nuclei are discharged at the cross-over point of two or more laser beams which form a corner at the junction of two or more photon walls. (U.K.)

Pressurized water reactor inspection procedures

International Nuclear Information System (INIS)

Heinrich, D.; Mueller, G.; Otte, H.J.; Roth, W.

1998-01-01

Inspections of the reactor pressure vessels of pressurized water reactors (PWR) so far used to be carried out with different central mast manipulators. For technical reasons, parallel inspections of two manipulators alongside work on the refueling cavity, so as to reduce the time spent on the critical path in a revision outage, are not possible. Efforts made to minimize the inspection time required with one manipulator have been successful, but their effects are limited. Major reductions in inspection time can be achieved only if inspections are run with two manipulators in parallel. The decentralized manipulator built by GEC Alsthom Energie and so far emmployed in boiling water reactors in the USA, Spain, Switzerland and Japan allows two systems to be used in parallel, thus reducing the time required for standard inspection of a pressure vessel from some six days to three days. These savings of approximately three days are made possible without any compromises in terms of positioning by rail-bound systems. During inspection, the reactor refueling cavity is available for other revision work without any restrictions. The manipulator can be used equally well for inspecting standard PWR, PWR with a thermal shield, for inspecting the land between in-core instrumentation nozzles, BWR with and without jet pumps (complementary inspection), and for inspecting core support shrouds. (orig.) [de

Summary of the progress of reactor physics in Japan reviewing the activities related to NEA Committee on Reactor Physics

International Nuclear Information System (INIS)

Hirota, Jitsuya

1984-09-01

The progress of fast and thermal reactor physics, fusion neutronics and shielding researches in these twenty years can be clearly recognized in the reviews of reactor physics activities in Japan which had been perpared by the Special Committee on Reactor Physics: the joint committee under Atomic Energy Society of Japan and JAERI. Many topics of those discussed at the NEACRP meetings concerned fast reactor physics. Information exchange on the topics such as adjustment of group cross sections by integral data, central worth discrepancy, sodium void effect and heterogeneous core stimulated the researches in Japan. And achievements in Japan including those in the JAERI Fast Critical Facility FCA were reported and contributed largely to the international co-operation. In addition, the contribution from Japan was also made concerning a study of fusion blanket. Among various specialists' meetings recommended by NEACRP, those on nuclear data and benchmarks for reactor shielding were often held since 1973 and helpful to the progress of shielding researches in Japan. The Third Specialists' Meeting on Reactor Noise (SMORN-III) was held in Tokyo in 1981, indicating the recent progress in safety-related applications of reactor noise analysis. The NEACRP benchmark tests were quite useful to the progress of reactor physics in Japan, which included the benchmark calculations of BWR lattice cell, key parameters and burn-up characteristics of a large LMFBR, FBR and PWR shielding, and so on. It may be noted that the benchmark test on reactor noise analysis methods was successfully conducted by Japan in connection with SMORN-III. In addition, the co-operation was positively made to the compilation of light water lattice data, and the preparation of reviews on actinide production and burn-up, and blanket physics. (J.P.N.)

A complete fuel development facility utilizing a dual core TRIGA reactor system

Energy Technology Data Exchange (ETDEWEB)

Middleton, A; Law, G C [General Atomic Co., San Diego, CA (United States)

1974-07-01

A TRIGA Dual Core Reactor System has been chosen by the Romanian Government as the heart of a new fuel development facility which will be operated by the Romanian Institute for Nuclear Technologies. The Facility, which will be operational in 1976, is an integral part of the Romanian National Program for Power Reactor Development, with particular emphasis being placed on fuel development. The unique combination of a new 14 MW steady state TRIGA reactor, and the well-proven TRIGA Annular Core Pulsing Reactor (ACPR) in one below-ground reactor pool resulted in a substantial construction cost savings and gives the facility remarkable experimental flexibility. The inherent safety of the TRIGA fuel elements in both reactor cores means that a secondary containment building is not necessary, resulting in further construction cost savings. The 14 MW steady state reactor gives acceptably high neutron fluxes for long- term testing of various prototype fuel-cladding-coolant combinations; and the TRIGA ACPR high pulse capability allows transient testing of fuel specimens, which is so important for accurate prediction of the performance of power reactor fuel elements under postulated failure conditions. The 14 MW steady state reactor has one large and three small in-core irradiation loop positions, two large irradiation loop positions adjacent to the core face, and twenty small holes in the beryllium reflector for small capsule irradiation. The power level of 14 MW will yield peak unperturbed thermal neutron fluxes in the central experiment position approaching 3.0 x 10{sup 14} n/cm{sup 2}-sec. The ACPR has one large dry central experimental cavity which can be loaded at pool level through a shielded offset loading tube; a small diameter in-core flux trap; and an in-core pneumatically-operated capsule irradiation position. A peak pulse of 15,000 MW will yield a peak fast neutron flux in the central experimental cavity of about 1.5 x 10{sup 17} n/cm{sup 2}-sec. The pulse width at

ANALISIS PENERAPAN PRINSIP MENGENAL NASABAH PADA BANK ACEH SYARIAH BANDA ACEH

Directory of Open Access Journals (Sweden)

Husnawati Husnawati

2013-06-01

Full Text Available This study aims to identify the systems and procedures that is applied at Bank Aceh Syariah (BAS Banda Aceh in knowing of its customers. In specific, it aims to analyze the effectiveness of the implementation of Knowing Your Customer (KYC Principle at BAS. This study employs both primary and secondary data which was obtained through field and library research. The data was analyzed using descriptive analysis method. The results show that in knowing its customers, BAS Banda Aceh taken several steps of customer identification includes the identity check, occupation, source of funds, and the purpose of the use of funds. The implementation of the KYC principle in BAS Banda Aceh has effectively overcome and prevented the banking crimes such as money laundering. The implementation of the principle is intended to embolden the implementation of prudential principles in order to reduce business risks such as operational risk, legal risk, concentration risk, and reputational risk. =========================================== Penelitian ini bertujuan untuk mengidentifikasi sistem dan prosedur yang diterapkan Bank Aceh Syariah (BAS Banda Aceh dalam mengenal nasabah. Secara khusus, penelitian bertujuan untuk menganalisis efektifitas penerapan Prinsip Mengenal Nasabah pada BAS. Data untuk penelitian ini bersumber dari data primer melalui kajian lapangan, dan data sekunder melalui kajian kepustakaan. Analisis data menggunakan metode deskriptif analisis. Dari hasil penelitian dapat diketahui bahwa sistem dan prosedur yang diterapkan BAS Banda Aceh dalam mengenal nasabah yaitu identifikasi calon nasabah yang meliputi identitas, pekerjaan, sumber dana dan tujuan penggunaan dana yang dilengkapi dokumen pendukung. Penerapan Prinsip Mengenal Nasabah (Know Your Customer Principle pada BAS Banda Aceh efektif dalam mengatasi kejahatan-kejahatan dalam dunia perbankan seperti pencucian uang. Penerapan prinsip tersebut dimaksudkan agar mendorong terselenggaranya prinsip

Development of the Centralized Reliability Data Organization (CREDO)

International Nuclear Information System (INIS)

Haas, P.M.; Bott, T.F.; Knee, H.E.; Manning, J.J.; Hudson, S.D.; Greene, N.M.; Woodside, M.A.

1979-01-01

CREDO has been established to meet the needs of the US Breeder Reactor Program and the advanced reactor community for a centralized source of accurate reliability/maintainability data and data-related services. The center provides for a comprehensive program of collection, evaluation, and dissemination of data and for necessary user services. A steering committee of nationally recognized experts has been formed to guide CREDO development and operation. Historic data have been collected, analyzed, and published. Routine, continuous data collection and processing has been initiated at US sites. Interfaces with existing data bases have been established. Special user services are under development

PESAN MORAL DALAM FILM TO KILL A MOCKINGBIRD (ANALISIS SEMIOTIKA PADA FILM TO KILL A MOCKINGBIRD

OpenAIRE

RENYOET, JAQUILINE MELISSA

2014-01-01

2014 JAQUILINE MELISSA RENYOET. Pesan Moral Dalam Film To Kill A Mockingbird (Analisis Semiotika Pada Film To Kill A Mockingbird). (Dibimbing oleh Muh. Nadjib dan Alem Febri Sonni). Tujuan Penelitian ini adalah mengidentifikasi bentuk pesan moral dan memahami makna pesan moral dalam film To Kill A Mockingbird. Penelitian ini dilakukan selama kurang lebih 2 bulan yaitu Maret ??? Mei 2014. Metode yang digunakan untuk penelitian ini adalah metode penelitian kualitatif den...

Analisi Pengaruh Store Name, Brand Name, Dan Price Discounts Terhadap Purchase Intentions Konsumen Infinite Tunjungan Plaza

OpenAIRE

Gunawan, Andy

2013-01-01

Andy Gunawan:SkripsiAnalisis pengaruh store name, brand name dan price discounts terhadap purchase intention konsumen infnite tunjungan plaza Di era globalisasi ini, persaingan dagang antara Perusahaan – Perusahaan baik lokal maupun global menjadi semakin ketat, oleh karena itu Perusahaan selalu berusaha untuk meningkatkan ketertarikan minat beli konsumen. Beberapa variabel yang menjadi fokus Perusahaan adalah store name, brand name, dan price discount. Tujuan penelitian ini adalah untuk meng...

Modular Stellarator Fusion Reactor concept

International Nuclear Information System (INIS)

Miller, R.L.; Krakowski, R.A.

1981-08-01

A preliminary conceptual study is made of the Modular Stellarator Reactor (MSR). A steady-state ignited, DT-fueled, magnetic fusion reactor is proposed for use as a central electric-power station. The MSR concept combines the physics of the classic stellarator confinement topology with an innovative, modular-coil design. Parametric tradeoff calculations are described, leading to the selection of an interim design point for a 4-GWt plant based on Alcator transport scaling and an average beta value of 0.04 in an l = 2 system with a plasma aspect ratio of 11. The physics basis of the design point is described together with supporting magnetics, coil-force, and stress computations. The approach and results presented herein will be modified in the course of ongoing work to form a firmer basis for a detailed conceptual design of the MSR

Keefektifan Konseling Behavioral Teknik Modeling dan Konseling Analisis Transaksional Teknik Role Playing untuk Meminimalkan Kecenderungan Perilaku Agresif Siswa Sekolah Menengah Atas

Directory of Open Access Journals (Sweden)

I Ketut Gading

2017-11-01

Full Text Available Abstract: This study aims to determine the effectiveness of behavioral counseling using modeling technique and counseling transactional analysis using role playing technique to minimize student’s tendency of aggressive behavior. This experimental research with pretest-posttest control group design is taking samples using purposive sampling technique. The sample were 18 tenth grade students from Senior High School Laboratorium Universitas Pendidikan Ganesha who have high aggressive behavior. 18 sample were randomly assigned to three group, that is: (1 experimental group of behavioral counseling using modeling technique; (2 counseling transactional analysis using role playing technique group; and (3 control group. Data on aggressive behavior tendency before and after treatment were collected using questionnaire of aggressive behavior, then analyzed by t test. The results show: (1 behavioral counseling using modeling technique were effective to minimize the tendency of aggressive behavior; (2 counseling transactional analysis using role playing technique were effective to minimize the aggressive behavior; and (3 counseling transactional analysis using role playing technique were more effectively minimizes the tendency of aggressive behavior rather than behavioral counseling using modeling technique. Abstrak: Penelitian ini bertujuan untuk mengetahui keefektifan konseling behavioral teknik modeling dan konseling analisis transaksional teknik role playing untuk meminimalkan kecenderungan perilaku agresif siswa. Penelitian eksperimen dengan rancangan pretest-posttest control group design ini mengambil sampel dengan teknik purposive sampling. Sampel terdiri dari 18 orang siswa kelas X Sekolah Menengah Atas (SMA Laboratorium Universitas Pendidikan Ganesha yang memiliki perilaku agresif tinggi. 18 sampel dibagi secara acak dan merata pada tiga kelompok, yaitu: (1 kelompok eksperimen yang mendapatkan perlakuan konseling behavioral teknik modeling; (2

Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

Control device for start-up of reactor depressurization system

International Nuclear Information System (INIS)

Suzuki, Hiroshi; Saito, Minoru; Oda, Shingo; Miura, Satoshi; Hashimoto, Koji; Tate, Hitoshi; Fujii, Kazunobu

1998-01-01

The present invention concerns are emergency reactor core cooling system (ECCS) of a BWR type reactor and provides a control device for start-up of an automatic depressurization system. Namely, the device has an object of preventing erroneous opening of a main steam escape safety value when testing a start-up signal circuit of an automatic depressurization system for testing the automatic depressurization system. A start-up signal circuit receives both signals of a reactor container pressure high signal and a reactor pressure vessel water level low signal and outputs an automatic start-up signal for compulsorily opening a main steam escape safety valve automatically. A test switch having a self-holding circuit is disposed to a central control chamber. A test signal circuit is disposed for preventing transfer of an erroneous start-up signal to the main steam escape safety valve due to a simulation signal during output test signals by the test switch. (I.S.)

Preparations for the Integral Fast Reactor fuel cycle demonstration

International Nuclear Information System (INIS)

Lineberry, M.J.; Phipps, R.D.

1989-01-01

Modifications to the Hot Fuel Examination Facility-South (HFEF/S) have been in progress since mid-1988 to ready the facility for demonstration of the unique Integral Fast Reactor (IFR) pyroprocess fuel cycle. This paper updates the last report on this subject to the American Nuclear Society and describes the progress made in the modifications to the facility and in fabrication of the new process equipment. The IFR is a breeder reactor, which is central to the capability of any reactor concept to contribute to mitigation of environmental impacts of fossil fuel combustion. As a fast breeder, fuel of course must be recycled in order to have any chance of an economical fuel cycle. The pyroprocess fuel cycle, relying on a metal alloy reactor fuel rather than oxide, has the potential to be economical even at small-scale deployment. Establishing this quantitatively is one important goal of the IFR fuel cycle demonstration

Nuclear reactor safety: on the history of the regulatory process

International Nuclear Information System (INIS)

Okrent, D.

1981-01-01

This manuscript is derived from a long report which examines the history of the evolution of light water reactor safety. The central portion of the document provides a historical view of the development of siting policy and the major safety issues which interacted strongly with siting policy. A very incomplete selection of the very many important issues and developments in light water reactor safety is also included. Coverage of the loss-of-coolant accident (LOCA) has deliberately been abbreviated to include only a few selected aspects

The use of graphite for the reduction of void reactivity in CANDU reactors

International Nuclear Information System (INIS)

Min, B.J.; Kim, B.G.; Sim, K-S.

1995-01-01

Coolant void reactivity can be reduced by using burnable poison in CANDU reactors. The use of graphite in the fuel bundle is introduced to reduce coolant void reactivity by adding an appropriate amount of burnable poison in the central rod. This study shows that sufficiently low void reactivity which in controllable by Reactor Regulating System (RRS) can be achieved by using graphite used fuel with slightly enriched uranium. Zero void reactivity can be also obtained by using graphite used fuel with a large central rod. A new fuel bundle with graphite rods can substantially reduce the void reactivity with less burnup penalty compared to previously proposed low void reactivity fuel with depleted uranium. (author)

Analisis Migrasi Radio Trunking Analog ke Radio Trunking Digital di Indonesia

Directory of Open Access Journals (Sweden)

Riza Azmi

2013-09-01

Full Text Available Dalam Tabel Alokasi Spektrum Frekuensi di Indonesia pada catatan kaki INS9 dan INS13 disebutkan bahwa alokasi pada pita-pita frekuensi yang digunakan untuk teknologi trunking direncanakan dimigrasi ke sistem komunikasi trunking digital pada waktu yang akan ditentukan oleh pemerintah. Terkait dengan hal itu, studi ini bertujuan untuk mengkaji bagaimana kelayakan migrasi dari sistem trunking analog ke sistem trunking digital dan hal-hal yang terkait dengannya. Dengan menggunakan analisis biaya dan manfaat (Cost-Benefit Analysis studi ini melihat bahwa migrasi hanya dapat dilakukan jika umur masing-masing lisensi dari operator telah berakhir, atau dengan kata lain pemerintah dapat mendorong transisi ke digital dengan menerbitkan lisensi baru yaitu lisensi trunking digital.

Remote controlled ultrasonic pre-service and in-service inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Mueller, G.

1990-01-01

The first mechanised in-service inspection of the reactor pressure vessel on unit one of Eskom's Koeberg nuclear power station has been carried out. Since 1968 a whole range of manipulators to carry out remote controlled ultrasonic inspections of nuclear power station equipment has been developed. The inspection of a reactor pressure vessel using a central mast manipulator is described. 3 figs., 1 ill

GENERIC, COMPONENT FAILURE DATA BASE FOR LIGHT WATER AND LIQUID SODIUM REACTOR PRAs

Energy Technology Data Exchange (ETDEWEB)

S. A. Eide; S. V. Chmielewski; T. D. Swantz

1990-02-01

A comprehensive generic component failure data base has been developed for light water and liquid sodium reactor probabilistic risk assessments (PRAs) . The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) and the Centralized Reliability Data Organization (CREDO) data bases were used to generate component failure rates . Using this approach, most of the failure rates are based on actual plant data rather than existing estimates .

Safety analysis of sea transportation of solidified reactor wastes

International Nuclear Information System (INIS)

Devell, L.; Edlund, O.; Kjellbert, N.; Grundfelt, B.; Milchert, T.

1980-06-01

A central handling and storage facility (ALMA) for low- and medium-level reactor waste from Swedish nuclear power plants is being planned and the transportation to it will be by sea. A safety assessment devoted to the potential environmental impacts from the transportation is presented. (Auth.)

RASISME DALAM FILM 99 CAHAYA DI LANGIT EROPA PART 1 (ANALISIS SEMIOTIKA DALAM FILM 99 CAHAYA DI LANGIT EROPA PART 1

Directory of Open Access Journals (Sweden)

Vallen Nur Rita

2016-09-01

Full Text Available Stereotip merupakan pernyataan negatif dari prasangka. Prasangka inilah yang kemudian dijadikan alasan untuk melakukan diskriminasi terhadap kelompok rasial tertentu. Stereotip dan prasangka kemudian merujuk pada suatu paham yang mempercayai adanya superioritas yang menolak adanya kesetaraan manusia yaitu rasisme. Perilaku maupun tindakan rasisme tersebut banyak muncul dalam beberapa scene film 99 Cahaya Di Langit Eropa Part 1. Tujuan dari penelitian ini adalah untuk mengetahui bagaimana simbol-simbol digunakan untuk menggambarkan rasisme di dalam film 99 Cahaya Di Langit Eropa Part 1. Metode yang digunakan oleh peneliti adalah semiotika Roland Barthes. Model Roland Barthes terdiri dari tiga tahap analisis yaitu denotasi, konotasi, mitos. Peneliti melakukan analisis menggunakan tanda verbal dan nonverbal yang terdapat dalam film “99 Cahaya di Langit Eropa Part 1”. Dalam menganalisis film 99 Cahaya di Langit Eropa Part 1, dikelompokkan menjadi beberapa kategori yang berhubungan dengan perilaku rasisme, antara lain : stereotip, prasangka, diskriminasi

Development of an analytic outline for the aflatoxins analysis in grains and flours; Desarrollo de un esquema analitico para el analisis de aflatoxinas en granos y harinas

Energy Technology Data Exchange (ETDEWEB)

Sibaja Adams, Roxana

2000-07-01

The instrumental and analytic conditions were optimized for the aflatoxine determination B1, B2, 1 and G2 in corn and peanut byl iquid chromatography of high discharge following the analyzing method AOAC 994,08. Besides, it was defined a function for evaluating the dependence of the chromatographic discharge with the aflatoxine concentration. The analyzing method was validated, and four calibration curves were obtained for the aflatoxine B1, B2, G1 and G2, which turned to have a heterocedastico behavior. The applicability of this method was demonstrated, obtaining imagines of appropriate merit and comparable with those reported by the AOAC. Additionally, the applicability of the chromatographic method was demonstrated in fine layer for the presumptive analysis of aflatoxine, allowing both methods to propose an outline of reliable analysis of real samples. [Spanish] Se optimizaron las condiciones instrumentales y analiticas para la determinacion de aflatoxinas B1, B2, G1 y G2 en maiz y mani por Cromatografia liquida de alto desempeno siguiendo el metodo de analisis AOAC 994,08. Ademas, se definio una funcion para evaluar la dependencia del desempeno cromatografico con la concentracion de aflatoxinas.Se valido el metodo de analisis y se obtuvieron las cuatro curvas de calibracion para las aflatoxinas B1, B2, G1 y G2, las que resultaron tener un comportamiento heterocedastico. Se demostro la aplicabilidad del metodo, obteniendose figuras de merito adecuadas y comparables con las reportadas por el AOAC.Adicionalmente, se demostro la aplicabilidad del metodo de cromatografia en capa fina para el analisis presuntivo de aflatoxinas, permitiendo ambos metodos proponer un esquema de analisis confiable de muestras reales.

A review of fast reactor programme in Japan

International Nuclear Information System (INIS)

1998-01-01

This report describes the development and activities on fast reactor in Japan for the period of April 1996 - March 1997. During this period, the 30th duty cycle operation has been started in the Experimental Fast Reactor ''''Joyo''''. The cause investigation on the sodium leak incident has completed and the safety examination are being performed in the Prototype Fast Breeder Reactor ''''Monju''''. The three years design study since FY1994 on the plant optimization of the Demonstration FBR has been completed by the Japan Atomic Power Company (JAPC). Related research and development works are underway at several organizations under the discussion and coordination of the Japanese FBR R and D Steering Committee, which is composed of Power Reactor and Nuclear Fuel Development Corporation (PNC), JAPC, Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI). In November 1996, the Japan Atomic Energy Commission (JAEC) established a Social Gathering Meeting to discuss generally the significance of FBR development in Japan for the future. (author)

EL-2 reactor: Thermal neutron flux distribution

International Nuclear Information System (INIS)

Rousseau, A.; Genthon, J.P.

1958-01-01

The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)

Reactor core in FBR type reactor

International Nuclear Information System (INIS)

Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

1989-01-01

In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

Reactor physics tests of TRIGA Mark-II Reactor in Ljubljana

International Nuclear Information System (INIS)

Ravnik, M.; Mele, I.; Trkov, A.; Rant, J.; Glumac, B.; Dimic, V.

2008-01-01

TRIGA Mark-II Reactor in Ljubljana was recently reconstructed. The reconstruction consisted mainly of replacing the grid plates, the control rod mechanisms and the control unit. The standard type control rods were replaced by the fuelled follower type, the central grid location (A ring) was adapted for fuel element insertion, the triangular cutouts were introduced in the upper plate design. However, the main novelty in reactor physics and operational features of the reactor was the installation of a pulse rod. Having no previous operational experience in pulsing, a detailed and systematic sequence of tests was defined in order to check the predicted design parameters of the reactor with measurements. The following experiments are treated in this paper: initial criticality, excess reactivity measurements, control rod worth measurement, fuel temperature distribution, fuel temperature reactivity coefficient, pulse parameters measurement (peak power, prompt energy, peak temperature). Flux distributions in steady state and pulse mode were measured as well, however, they are treated only briefly due to the volume of the results. The experiments were performed with completely fresh fuel of 12 w% enriched Standard Stainless Steel type. The core configuration was uniform (one fuel element type, including fuelled followers) and compact (no irradiation channels or gaps), as such being particularly convenient for testing the computer codes for TRIGA reactor calculations. Comparison of analytical predictions, obtained with WIMS, SLXTUS, TRIGAP and PULSTRI codes to measured values showed agreement within the error of the measurement and calculation. The paper has the following contents: 1. Introduction; 2. Steady State Experiments; 2.1. Core loading and critical experiment; 2.2. Flux range determination for tests at zero power; 2.3. Digital reactivity meter checkout; 2.4. Control rod worth measurements; 2.5. Excess reactivity measurement; 2.6. Thermal power calibration; 2

Development of fast reactor metal fuels containing minor actinides

International Nuclear Information System (INIS)

Ohta, Hirokazu; Ogata, Takanari; Kurata, Masaki; Koyama, Tadafumi; Papaioannou, Dimitrios; Glatz, Jean-Paul; Rondinella, Vincenzo V.

2011-01-01

Fast reactor metal fuels containing minor actinides (MAs) Np, Am, and Cm and rare earths (REs) Y, Nd, Ce, and Gd are being developed by the Central Research Institute of Electric Power Industry (CRIEPI) in collaboration with the Institute for Transuranium Elements (ITU) in the METAPHIX project. The basic properties of U-Pu-Zr alloys containing MA (and RE) were characterized by performing ex-reactor experiments. On the basis of the results, test fuel pins including U-Pu-Zr-MA(-RE) alloy ingots in parts of the fuel stack were fabricated and irradiated up to a maximum burnup of ∼10 at% in the Phenix fast reactor (France). Nondestructive postirradiation tests confirmed that no significant damage to the fuel pins occurred. At present, detailed destructive postirradiation examinations are being carried out at ITU. (author)

Probabilistic safety analysis for the Triga reactor Vienna

International Nuclear Information System (INIS)

Boeck, H.; Kirchsteiger, C.

1988-07-01

Triga-type reactors are the most widely used low power research reactors with power levels up to 3 MW. Although Triga reactors are considered inherently safe, due to their unique features such as prompt negative temperature coefficient and low power density, the reactor core still contains a respectable amount of activity which could lead under very adverse circumstances to radiation exposure both of staff members and of public. Such circumstances could be external events, accidents during fuel element manipulation or a loss of coolant water with exposure of the core. Therefore, it was decided to look more closely to various accident pathways and to calculate their probability, if possible. A major drawback is the lack of statistical material because no centralized registration of failures is carried out. Therefore, in many cases values from other research reactor types or even from power reactor statistics had to be used, thus increasing the uncertainty of the results. As most undesired event or TOP-event in this analysis a radiation exposure of staff members, the public or both together was selected and the probabilities of different pathways leading to this exposure was calculated. In the present case 'radiation exposure' are dose rates or activity concentration above the international accepted limits for occupational staff or public. 20 refs., 10 figs. (Author)

Analisis Plagiat dalam Penulisan Laporan Ilmiah Kelas XI Smk Sakti Gemolong Kabupaten Sragen Tahun Ajaran 2015/2016

OpenAIRE

Sari, Dwi Ratna; Arfa, Mecca

2016-01-01

Penelitian ini berjudul “Analisis Plagiat dalam Penulisan Laporan Ilmiah Kelas XI SMK Sakti Gemolong Kabupaten Sragen Tahun Ajaran 2015/2016”. Tujuan dari penelitian ini adalah untuk mengetahui pemahaman siswa mengenai tindakan plagiat, serta menganalisis tipe-tipe plagiat dan faktor-faktor yang menyebabkan tindakan plagiat. Penelitian ini menggunakan desain penelitian kualitatif dengan jenis penelitian studi kasus. Teknik pengambilan sampel pada penelitian ini menggunakan purposive sampling....

ANALISIS PENERAPAN STRATEGI PEMASARAN DALAM PENINGKATAN PANGSA PASAR PADA PT. HADJI KALLA (TOYOTA) CABANG COKROAMINOTO DI MAKASSAR

OpenAIRE

ASTRINI, PRATANTI AYU

2007-01-01

Analisis Penerapan Strategi Pemasaran Dalam Peningkatan Pangsa Pasar Pada PT. Hadji Kalla (Toyota) Cabang Cokroaminoto di Makassar Implementation of marketing strategy analyze on increasing market share study case PT.Hadji Kalla (Toyota) Cabang Cokroaminoto in Makassar Pratanti Ayu Astrini Mursalim Nohong Wardhani Hakim Tujuan dari penelitian ini adalah untuk mengetahui penerapan strategi pemasaran mobil Toyota pada PT. Hadji Kalla (Toyota) Cabang Cokroaminoto di Makassar me...

Long-lived sodium activity from a fast reactor

Energy Technology Data Exchange (ETDEWEB)

Martini, M; Moioli, P; Romanelli, C M

1973-06-05

The /sup 23/Na(n,2n)/sup 22/Na cross section was measured in two different ways; the first in the TRIGA reactor, with the sodium sample surrounded by a natural boron shield, the second in the central channel of the TAPIRO reactor. Irradiated samples were investigated either to measure the /sup 23/ Na(n,2n)/sup 22/Na cross section or to determine the impurities present and their activation cross sections. Unsatisfactory results for the second problem suggested evaluation of the impurity activations by calculation; therefore, a set of group constants for reactions of interest was prepared. (3 figures, 3 tables) (auth)

Fast reactor operating experience gained in Russia: Analysis of anomalies and abnormal operation cases

International Nuclear Information System (INIS)

Ashurko, Y.M.; Baklushin, R.P.; Zagorulko, Y.I.; Ivanenko, V.N.; Matveyev, V.P.; Vasilyev, B.A.

2000-01-01

Review of various anomalous events and abnormal operation experience gained in the process of Russian fast reactors operation is given in the paper. The main information refers to the BN-600 demonstration reactor operation. Statistical data on sodium leaks and steam generator failures are presented, and sources of these events and countermeasures taken to avoid their appearance on the operating reactors as well as related changes made in the BN-800 reactor design are considered. In the paper, some features of impurities behaviour are considered in various modes of the BN-600 reactor operation. Information is given on the impurities ingress into the circuits, on abnormal situation emerged in the process of the BN-600 reactor operation and its probable cause. Information is presented on the event related to the increased torque of the BN-600 reactor central rotating column and repair works performed. (author)

Issues affecting advanced passive light-water reactor safety analysis

International Nuclear Information System (INIS)

Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

1992-01-01

Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented

On possibility of vibrational stabilization in nuclear instable stationary regimes in nuclear reactors

International Nuclear Information System (INIS)

Trakhtenberg, A.M.

1987-01-01

A principle possibility of applying the vibrational stabilization method to nuclear reactors is studied. The problem of securing the stability of nuclear reactor operation steady-state regimes is one of the central ones in dynamics theory and nuclear reaction operation experience. In particular, the problem of xenon oscillation suppressing in a reactor, occuring as a result of steady-state regime instability is urgent. Investigation is conducted using the simpliest reactor model, repesenting it as a non-linear object with concentrated parameters. It is proved that vibrational stabilization is achieved by periodic fluctuations of the control rod positions in the reactor core and boric acid concentration in the coolant with period 1s 4 s. In practice stabilization is effective, when the steady-state regime is located near the stability boundary, which appears to be dangerous, i.e. self-oscillations with inadmissibly high amplitude occure in the reactor

ANALISIS POSISI RECLOSER TERHADAP KEANDALAN KINERJA PENYULANG SEMPIDI BERBASISKAN SOFTWARE ETAP POWERSTATION

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I Nengah Sunaya

2017-11-01

Full Text Available Penelitian ini menganalisis koordinasi recloser yang terdapat pada penyulang Sempidi untuk meningkatkan keandalan kinerja dari penyulang tersebut. Keandalan yang diharapkan adalah keandalan dalam penyediaan dan penyaluran dayanya. Untuk mengetahui keandalan dalam penyaluran tenaga listrik kepada konsumen perlu diperhitungkan indeks keandalannya. Indeks keandalan menjadi indikator dinyatakan dalam suatu besaran probabilitas yang bertujuan meminimalkan nilai SAIDI dan SAIFI, yaitu 1,8805505 jam/pelanggan tahun dan 5,8200455 kegagalan/pelanggan tahun, serta nilai fitness sebesar 0,091366843 untuk recloser pada posisi 10. Teknik yang digunakan dalam evaluasi keandalan sistem distribusi yaitu metode analisis dengan formula SAIDI dan SAIFI serta metode simulasi dengan memanfaatkan software ETAP powerstation

ANALISIS BAHASA GAUL ANTAR TOKOH DALAM FILM REMAJA INDONESIA “RADIO GALAU FM”

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St. Victor Maruli tua Lumbantobing , S.Pd., M.Pd

2016-03-01

Full Text Available ABSTRAKGajala bahasa ialah segala peristiwa yang berkaitan dengan bentuk-bentukkata beserta proses pembentuknya. Gejala-gejala bahasa seringkali digunakanoleh penutur bahasa baik di dalam film dan masyarakat. Bahasa gaul salah satu gaya bahasa yang sering digunakan anak remaja jaman sekarang. Film Remaja Indonesia yang berjudul “Radio Galau FM” merupakan sebuah karya yangditulis oleh Haqi Achmad. Dalam film ini banyak proses pembentukan kata bahasagaul. Mengingat pentingnya bahasa gaul sebagai wujud produk remaja, makapeneliti tertarik untuk meneliti pembentukan bahasa gaul ini. Sesuai denganrumusan masalah maka penelitian ini dimaksudkan untuk mendeskripsikanproses pembentukan bahasa gaul, yang meliputi: 1 proses afiksasi; 2; gejalagejalabahasa dan 3, serta penggunaan jenis-jenis makna dalam bahasagaul. Untuk membahas masalah tersebut, maka dalam menganalisis, penelitimenggunakan teori pembentukan kata ( kajian Morfologi . Penelitian inimenggunakan jenis penelitian kualitatif. Sedangkan metode yang digunakanadalah metode dan ekstralingual dan teknik analisis data dalam penelitian iniberupa urai unsure langsung dan teknik ubah ujud. Data penelitian ini adalahdialog dalam film “Radio Galau FM” ( berbentuk proses afiksasi, gejala-gejalabahasa, dan jenis-jenis makna. Sumber data berupa rekaman dialog film yangterjadi dalam film “Radio Galau FM”. Secara garis besar hasil analisis datadalam penelitian bahasa gaul sangat berbeda dengan penggunaannya dalam bahasa baku bahasa Indonesia. Hasil yang diperoleh dalam penelitian ini menunjukkan bahwa, bahasa gaul merupakan produk dari remaja, maksudnyaadalah remaja dalam berkomunikasi sehari-hari menggunakan bahasa ini disetiap situasi tanpa memperhatikan keadaan dan situasi, jika dibiarkan makasikap kesopanan akan terabaikan.Kata-Kata Kunci: Pembentukan Kata, Bahasa Gaul, Film Remaja Indonesia.Key words : Formation of words , language Gaul , Youth Film Indonesia

ANALISIS POSTUR KERJA PADA PT. XYZ MENGGUNAKAN METODE ROSA (RAPID OFFICE STRAIN ASSESSMENT

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Rosma Hani Damayanti

2014-06-01

Full Text Available Penggunaan teknologi informasi, dimana komputer sebagai medianya kini semakin meningkat. Frekuensi yang tinggi akan penggunaan komputer yang tidak memperhatikan sisi ergonomi dalam bekerja mengakibatkan adanya resiko yang dirasakan oleh pengguna. PT. XYZ merupakan salah satu perusahaan yang menggunakan komputer sebagai salah satu alat utama dalam bekerja. Pada penggunaannya karyawan pada Departemen Publishing merasakan keluhan pada punggung, pinggang, nyeri bahu, leher dan tangan. Keluhan yang dirasakan oleh pekerja pada Departemen publishing dapat diminimalkan dengan cara mengetahui dan mengidentifikasi postur kerja pada pekerja dalam menggunakan komputer. Identifikasi tersebut digunakan untuk mengetahui kondisi pekerja dan mengetahui penyebab keluhan yang dirasakan oleh pekerja untuk dilakukan perbaikan. Pada penelitian ini dilakukan analisis dengan menggunakan metode ROSA untuk mengurangi adanya keluhan yang dirasakan oleh pekerja pada Departemen publishing. ROSA merupakan salah satu metode pada office ergonomics, dimana penilaiannnya dirancang untuk mengukur resiko yang terkait dengan penggunaan komputer serta untuk menetapkan tingkat tindakan perubahan berdasarkan laporan dari ketidaknyamanan pekerja. Dengan menggunakan metode ROSA, dapat diketahui apakah postur kerja karyawan pada Departemen Publishing pada saat bekerja aman atau berbahaya. Hasil analisis postur kerja menggunakan metode ROSA pada Departemen Publishing menunjukkan bahwa seluruh pekerja yang menjadi sampel memiliki level resiko yang tinggi dan perlu dilakukan perbaikan segera. Perbaikan yang dapat dilakukan untuk mengurangi tingkat resiko yang dirasakan oleh pekerja yaitu dengan perbaikan fasilitas yang digunakan oleh pekerja yang sesuai dengan standar ergonomi, melakukan sosialisasi kepada pekerja tentang pentingnya ergonomi pada dunia kerja, dan sebaiknya pekerja melakukan istirahat atau peregangan otot minimal setiap tiga jam sekali.

ANALISIS POSTUR KERJA PADA PT. XYZ MENGGUNAKAN METODE ROSA (RAPID OFFICE STRAIN ASSESSMENT

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Rosma Hani Damayanti

2014-06-01

Full Text Available Penggunaan teknologi informasi, dimana komputer sebagai medianya kini semakin meningkat. Frekuensi yang tinggi akan penggunaan komputer yang tidak memperhatikan sisi ergonomi dalam bekerja mengakibatkan adanya resiko yang dirasakan oleh pengguna. PT. XYZ merupakan salah satu perusahaan yang menggunakan komputer sebagai salah satu alat utama dalam bekerja. Pada penggunaannya karyawan pada Departemen Publishing merasakan keluhan pada punggung, pinggang, nyeri bahu, leher dan tangan. Keluhan yang dirasakan oleh pekerja pada Departemen publishing dapat diminimalkan dengan cara mengetahui dan mengidentifikasi postur kerja pada pekerja dalam menggunakan komputer. Identifikasi tersebut digunakan untuk mengetahui kondisi pekerja dan mengetahui penyebab keluhan yang dirasakan oleh pekerja untuk dilakukan perbaikan. Pada penelitian ini dilakukan analisis dengan menggunakan metode ROSA untuk mengurangi adanya keluhan yang dirasakan oleh pekerja pada Departemen publishing. ROSA merupakan salah satu metode pada office ergonomics, dimana penilaiannnya dirancang untuk mengukur resiko yang terkait dengan penggunaan komputer serta untuk menetapkan tingkat tindakan perubahan berdasarkan laporan dari ketidaknyamanan pekerja. Dengan menggunakan metode ROSA, dapat diketahui apakah postur kerja karyawan pada Departemen Publishing pada saat bekerja aman atau berbahaya. Hasil analisis postur kerja menggunakan metode ROSA pada Departemen Publishing menunjukkan bahwa seluruh pekerja yang menjadi sampel memiliki level resiko yang tinggi dan perlu dilakukan perbaikan segera.  Perbaikan yang dapat dilakukan untuk mengurangi tingkat resiko yang dirasakan oleh pekerja yaitu dengan perbaikan fasilitas yang digunakan oleh pekerja yang sesuai dengan standar ergonomi, melakukan sosialisasi kepada pekerja tentang pentingnya ergonomi pada dunia kerja, dan sebaiknya pekerja melakukan istirahat atau peregangan otot minimal setiap tiga jam sekali.

Teori Pecking Order dan Trade-Off dalam Analisis Struktur Modal di Bursa Efek Indonesia

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D Agus Harjito

2014-06-01

Full Text Available AbstractThis study aims to test the pecking order theory and trade-off theory of capital structure in the analysis of the Indonesia Stock Exchange. Pecking order theory is represented by the variable profitability and growth, while the variables volatility of earnings, tangibility of assets and the size represents a trade-off theory. The company's goal is prosperity of shareholder value. To achieve these objectives the company needs funds from internal sources and external sources. Internal sources in the form of retained earnings, while the external sources of debt and shareholders' approval in the pecking order theory. This study uses the data of financial ratios of the firms during the period 2000-2010. To analyze the data, this study uses a multiple regression with the dependent variable is the debt ratio, while profitability, growth, volatility of earnings, tangibility of assets and size as independent variables. The results show that asset structure and company size has a positive and significant impact on capital structure, while profitability has a negative effect on debt ratios. But company's growth rate has not relationship with the debt ratio or capital structure. Simultaneously, the all independent variables affect capital structure significantly.Keywords: pecking order, trade-off, capital structure, debt rasioAbstrakPenelitian ini bertujuan untuk menguji teori pecking order dan teori trade-off dalam analisis struktur modal di Bursa Efek Indonesia. Teori pecking order diwakili oleh variabel profitability dan growth, sementara variabel-variabel volatility of earnings, tangibility of assets dan size mewakili teori trade-off. Tujuan perusahaan adalah memakmurkan nilai pemegang saham. Untuk mencapai tujuan tersebut perusahaan membutuhkan dana yang diperoleh dari sumber internal dan sumber eksternal. Sumber internal berupa laba ditahan, sedangkan sumber eksternal berupa hutang dan saham sebagaimana dijelaskan dalam teori pecking order

Development of the radiation models of a BWR type reactor and it facility in the SUN-RAH; Desarrollo de modelos de radiacion de un reactor tipo BWR y su instalacion en el SUN-RAH

Energy Technology Data Exchange (ETDEWEB)

Barron A, I. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. e-mail: isbarron@yahoo.com.mx

2005-07-01

This work about generation models, transport in processes and radioactive contamination of areas of a BWR central, is an amplification to the project developed in the UNAM to have a support tool in subjects or electric generation courses. It is planned about the implementation of models of radiation generation in a BWR type reactor for complement the functions developed in the University Simulator of Nucleo electric- Boiling water reactor (SUN-RAH) which it has been implemented in Simulink of MatLab and it has a model for the dynamics of one nucleo electric central that presents the main characteristics of the reactor vessel, the recirculation system, steam lines, turbines, generator, condensers and feeding water, defined by the main processes that intervene in the generation of energy of these plants. By this way the radiation monitoring systems for area and process, operate simultaneously with the processes of energy generation, with that is possible to observe the changes that present with respect to the operation conditions of the plant, and likewise to appreciate the radiation transport process through the components of the reactor, steam lines and turbines, for different operation conditions and possible faults that they could be presented during the reactor operation. (Author)

USULAN STRATEGI UNTUK MENINGKATKAN DAYA SAING PRODUK MEBEL ROTAN SINGLE CHAIR DENGAN ANALISIS RANTAI NILAI (Studi Kasus : Klaster Mebel Rotan Kab. Cirebon

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Ary Arvianto

2013-06-01

Full Text Available Industri mebel rotan merupakan salah satu andalan sektor industri di Indonesia dimana sentra pengolahan rotan terbesar adalah di Kabupaten Cirebon, Jawa Barat. Namun, terdapat beberapa kendala dalam industri mebel rotan di Cirebon ini diantaranya semakin ketatnya persaingan antar produsen dunia dan kebijakan pemerintah memperbolehkan ekspor rotan yang menyebabkan keuntungan di pihak negara pesaing Oleh karena itu, dibutuhkan suatu strategi untuk meningkatkan daya saing  produk rotan di pasar dunia. Strategi ini dapat diperoleh dengan melakukan analisis value chain. Tujuan dari penelitian ini adalah untuk menganalisis rantai nilai produk mebel rotan dan mendapatkan strategi kompetitif yang tepat untuk diterapkan oleh setiap pelaku rantai nilai. Metode yang dilakukan adalah analisis finansial, analisis SWOT, analisis Competitiveness Diamond, dan analisis Critical Success Factor (CSF. Objek penelitian adalah perusahaan-perusahaan yang merupakan anggota dari Asosiasi Pengusaha Mebel Indonesia (ASMINDO Cirebon yang memproduksi mebel rotan single chair. Dari hasil pengolahan data dan analisis diperoleh hasil bahwa strategi yang dapat diterapkan di pihak supplier dalam hal ini pengumpul adalah mendirikan anak perusahaan di tempat tersedia bahan baku dan melakukan merger dengan perusahaan. Strategi yang dapat diterapkan di pihak perusahaan adalah menerapkan upah tenaga kerja per unit produk yang dihasilkan, pengalokasian dana untuk promosi, memprioritaskan buyer langganan, sharing informasi dan inovasi dengan buyer, memiliki fleksibilitas yang tinggi dalam hal kualitas dan harga, bekerjasama dengan asosiasi dan pemerintah dalam kegiatan pameran, dan melakukan merger dengan perusahaan lain ataupun dengan supplier. Sedangkan strategi yang dapat diterapkan di pihak buyer dalam hal ini wholeseller adalah menurunkan harga produk, memaksimalkan promosi dan menjaga hubungan baik dengan perusahaan yang sudah menjadi kepercayaan. Kata Kunci: mebel rotan, value

A Design of Alarm System in a Research Reactor Facility

International Nuclear Information System (INIS)

Park, Jaekwan; Jang, Gwisook; Seo, Sangmun; Suh, Yongsuk

2013-01-01

The digital alarm system has become an indispensable design to process a large amount of alarms of power plants. Korean research reactor operated for decades maintains a hybrid alarm system with both an analog annunciator and a digital alarm display. In this design, several alarms are indicated on an analog panel and digital display, respectively, and it requires more attention and effort of the operators. As proven in power plants, a centralized alarm system design is necessary for a new research reactor. However, the number of alarms and operators in a research reactor is significantly lesser than power plants. Thus, simplification should be considered as an important factor for the operation efficiency. This paper introduces a simplified alarm system. As advances in information technology, fully digitalized alarm systems have been applied to power plants. In a new research reactor, it will be more useful than an analog or hybrid configuration installed in research reactors decades ago. However, the simplification feature should be considered as an important factor because the number of alarms and number of operators in a research reactor is significantly lesser than in power plants

Analisis Potensi Ledakan dan Kebakaran Primary Reformer sebagai Unit Proses Produksi Amonia di PT. X

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Resti Ayu Lestari

2016-12-01

Full Text Available Peningkatan industri pupuk di dunia berimplikasi pada peningkatan jumlah industri amonia. Amonia memegang peranan penting pada proses produksi pupuk dalam hal penyediaan nitrogen. Proses pembuatan amonia melibatkan bahan baku berupa gas alam yang bersifat flammable dengan temperatur dan tekanan yang tinggi dalam setiap tahapan prosesnya. Primary reformer merupakan salah satu peralatan proses dalam produksi amonia dengan temperatur dan tekanan paling tinggi serta paling berisiko mengalami kegagalan yang dapat mengakibatkan terjadinya kebakaran/ledakan. Primary reformer berperan sebagai salah satu tahapan pemurnian gas alam dengan hasil berupa karbon monoksida. Identifikasi bahaya pada unit primary reformer dilakukan dengan menggunakan metode Fault Tree Analysis (FTA. Hasil analisis FTA menghasilkan bahwa sumber bahaya dari ledakan primary reformer dapat ditinjau dari faktor teknis dan faktor non teknis. Faktor non teknis menyumbang 74% dari penyebab terjadinya ledakan/kebakaran pada primary reformer. Hasil analisis risiko ledakan/kebakaran pada primary reformer dilakukan dengan menggunakan Dow’s Fire & Explosion Index  dengan hasil radius area dampak adalah 51 meter. Nilai kerugian finansial mencapai US$ 23.640.285 dengan kerugian hari kerja minimal adalah 138 hari. Perangkat lunak Arial Location of Hazardous Atmospheres menghasilkan radius ledakan dengan dampak terkecil yaitu dapat memecahkan kaca jendela/pintu (0,5 psi adalah 73 m dari primary reformer. Radius ledakan dengan kekuatan ledakan 1 psi (meruntuhkan rumah/perkantoran adalah 48 m dari primary reformer.

BAHASA DAN IDEOLOGI: MENGUNGKAP IDEOLOGI DAN KEKUASAAN SIMBOLIK DI BALIK PENGGUNAAN BAHASA (KAJIAN TEKS MEDIA MELALUI ANALISIS WACANA KRITIS

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Su haryo

2014-11-01

Full Text Available Abstrak   Tulisan ini didasari sebuah anggapan bahwa bahasa tidak berada di ruang hampa sosial.Maka, bahasa pada dasarnya bukan hanya untaian kata yang hanya bersifat linguistik, tetapi bersifat sosial. Karenanya, bahasa dipahami sebagai tindakan sosial.Implikasinya, bahasa bukan hanya bermatra linguistik, tetapi juga bermatra sosial. Van Dijk menjadi salah satu model yang dapat digunakan sebagai alat untuk menganalisis wacana secara kritis. Penelitian analisis wacana kritis model van Dijk mempertimbangkan teks, konteks, kognisi sosial, dan analisis/konteks sosial. Untuk mengungkap hal itu, langkah yang dapat dilakukan adalah: mengungkap struktur makro (tematik, suprstruktur (skematik, dan struktur mikro yang terdiri atas semantik, sintaksis, stilitistik, dan retorika. Untuk mengungkap hal itu, di sini digunakan metode simak dan catat dengan menjadikan Suara Merdeka dan Kompassebagai sumber datanya. Hasilnya pertama,SM cenderung berideologi kasar, provokatif, dan konotatif/figuratif. Hal itu, tampak pada pilihan kata/kalimat  kata yang cenderung kasar, seperti mengancam,menyerang, memanggil paksa, menyeret, menembak.Sementara, harian K cenderung berideologi idealisme pers yang objektif, netral, dan berimbang. Kedua, dari dimensi kekuasaan (simbolik, harian SM cenderung menjadi “oposisi”  dan “oposan”sebagai pihak yang di-dominan-kan, sedang pihak pemerintah sebagai pihak yang “dimarginalkan”. Sementara, harian K menempatkan pihak yang dominan/marginal lebih didasarkan pada kondisi objektif di lapangan yang  berbasis data dan keterangan yang dari narasumber yang cenderung netral, seperti pengamat, warga, dan akademisi; tidak didasarkan pada keterangan yang cenderung subjektif, seperti dari para politisi.Ketiga, dari sisi analisis sosial dan kognisi sosial; SM lebih tampak sebagai cerminan tagline-nya yaitu lokal (yaitu “perekat komunitas Jawa Tengah”, sedangkan harian K lebih “mengabdi” pada rakyat seperti tampak pada

ANALISIS MANFAAT BIAYA LINGKUNGAN USAHA TERNAK BABI: STUDI KASUS DI DESA AMBARKETAWANG KECAMATAN GAMPING KABUPATEN SLEMAN (Benefit Cost Analysis of Pig Farming Environment: Case Study at Ambarketawang Village, Gamping District, Sleman Regency, Indonesia

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Tri Anggraeni Kusumastuti

2001-12-01

Full Text Available ABSTRAK Penelitian ini bertujuan untuk mengetahui pendapatan peternak dan kelayakan pengembangan usaha ternak babi secara finansial maupun ekonomi. Penelitian dilakukan di Kecamatan Gamping. Data yang digunakan adalah data primer dari responden peternak dan data sekunder dari instansi terkait. Analisis yang digunakan adalah analisis pendapatan metode R/C Ratio, NPV (Net Present Value, dan IRR (Internal Rate of Return dengan umur ekonomis kandang selama 3 tahun. Hasil penelitian menunjukkan bahwa analisis pendapatan secara finansial menghasilkan nilai lebih tinggi dibandingkan penilaian secara ekonomi. Jenis penggemukan memberikanpendapatan tertinggi secara finansial, sedangkan secaraekonomi, dengan memperhitungkan lingkungan, jenis kombinasi memberikan pendapatan tertinggi. Analisis sensitivitas menunjukkan bahwa penurunan harga babi berpengaruh terhadap penurunan pendapatan peternak dibandingkan peningkatan harga pakan dan peningkatan biaya lingkungan. Jenis pembibitan paling peka terhadap analisis sensitivitas, sedangkan jenis kombinasi penggemukan dan pembibitan tidak begitu terpengaruhi.   ABSTRACT The objectives of this research were to assess the farmer’s income and the feasibility of pig farming, financially as well as economically. The data used in this research were primary data from pig farmers and secondary data from relevant institution. Financial and economic analysis of income and feasibility study with NPV (Net Present Value, B/C ratio, IRR (Internal Rate of Return with economic barn value of 3 years, were applied in this research. The results showed that financially the fattening system gave the highest income, but the combination system was more efficient because it provided the highest income, but the combination system was more efficient because it provided the highest income, inspite of taking into consideration the environment effect. Sensitivity analysis showed that the pig price’s decline influenced the farmer�

Project and characteristics of a 5MW experimental fast reactor

International Nuclear Information System (INIS)

Ishiguro, Y.; Nascimento, J.A. do.

1986-05-01

Characteristics of a 5 MW experimental fast reactor are reported. The reactor is designed with emphasis on fuel and materials irradiation and uses fuel assemblies of a standard structure. The reference core consist of 37 fuel assemblies, each of which contains 19 pins of metallic Pu/Zr fuel. With a core height of 17.6 cm the core volume is 11.4 liter and the central fast (E >=100 KeV) flux is 0.9 x 10 15 n/cm 2 sec. In addition to twelve control rod assemblies with a total reactivity worth of 5.5% Δk, 42 assemblies for reactivity compensation are placed in the two rings outside the core. Replacing these assemblies with driver, blanket, or refletor-shield assemblies, large reactivities can be added to make the central assembly position available for test irradiations and to assure high levels of burnup of driver assemblies. (Author) [pt

1980 nuclear plant survey: no reactors sold; more cancellations

International Nuclear Information System (INIS)

Friedlander, G.D.

1980-01-01

No sales were reported in 1979 by any of the big four reactor suppliers. Three cancellations were reported and construction was suspended on the Jersey Central Power and Light Co.'s Forked River unit. Since last year's survey, the commercial operation dates of about 80 units have been postponed from one year to indefinitely, and nuclear commitments are down from last year's 195 units to 193 units. Presently, there are 72 plants on line, with a capacity of more than 53,000 MW. A resumption of new reactor orders is expected in either late 1980 or early 1981

Visual examination program of the TRIGA Mark II reactor Vienna with the nuclear underwater telescope

International Nuclear Information System (INIS)

Boeck, H.; Hammer, J.; Varga, K.

1985-12-01

The visual inspection programm carried out during a three month shut-period at the TRIGA Mark II reactor Vienna is described. Optical inspection of all welds inside the reactor tank was carried out with an underwater telescope developed by the Central Research Institute of Physics, Budapest, Hungary. It is shown that even after 23 years of reactor operation all tank internals were found to be in good condition and minor defects can be easily repaired by remote handling tools. (Author)

Paired replacement fuel assemblies for BWR-type reactor

International Nuclear Information System (INIS)

Oguchi, Kazushige.

1997-01-01

There are disposed a large-diameter water rod constituting a non-boiling region at a central portion and paired replacement fuel assemblies for two streams having the same average enrichment degree and different amount of burnable poisons. The paired replacement fuel assemblies comprise a first fuel assembly having a less amount of burnable poisons and a second fuel assembly having a larger amount of burnable poisons. A number of burnable poison-containing fuel rods in adjacent with the large diameter water rod is increased in the second fuel assembly than the first fuel assembly. Then, the poison of the paired replacement fuel assemblies for the BWR type reactor can be annihilated simultaneously at the final stage of the cycle. Accordingly, fuels for a BWR type reactor excellent in economical property and safety and facilitating the design of the replacement reactor core can be obtained. (N.H.)

An assessment of econometric models applied to fossil fuel power generation; Un'analisi critica dell'applicazione dei modelli econometrici alla generazione termoelettrica

Energy Technology Data Exchange (ETDEWEB)

Gracceva, F.; Quercioli, R. [ENEA, Funzione Centrale Studi, Centro Ricerche Casaccia, Rome (Italy)

2001-07-01

The main purpose of this report is to provide a general view of those studies, in which the econometric approach is applied to the selection of fuel in fossil fired power generation, focusing the attention to the key role played by the fuel prices. The report consists of a methodological analysis and a survey of the studies available in literature. The methodological analysis allows to assess the adequateness of the econometric approach, in the electrical power utilities policy. With this purpose, the fundamentals of microeconomics, which are the basis of the econometric models, are pointed out and discussed, and then the hypotheses, which are needed to be assumed for complying the economic theory, are verified in their actual implementation in the power generation sector. The survey of the available studies provides a detailed description of the Translog and Logit models, and the results achieved with their application. From these results, the estimated models show to fit the data with good approximation, a certain degree of interfuel substitution and a meaningful reaction to prices on demand side. [Italian] In questo rapporto viene tracciato un quadro generale degli studi che utilizzano modelli econometrici per analizzare la scelta dei combustibili nella termogenerazione, con particoalre attenzione al ruolo svolto dal prezzo dei combustibili. La trattazione si compone di un'analisi di tipo metodologico e di una rassegna della letteratura. L'analisi metodologica consente di valutare l'adeguatezza dell'approccio econometrico nell'analisi del comportamento delle imprese di generazione elettrica. A tal fine vengono esplicitati e discussi i fondamenti microeconomici su cui poggiano i modelli econometrici, e viene verificata la sussistenza, nel settore termoelettrico, delle ipotesi che e' necessario assumere per soddisfare la teoria economica. La rassegna fornisce invece una descrizione dei modelli translog e logit lineare, ed un'analisi

Thermal and fast reactor benchmark testing of ENDF/B-6.4

International Nuclear Information System (INIS)

Liu Guisheng

1999-01-01

The benchmark testing for B-6.4 was done with the same benchmark experiments and calculating method as for B-6.2. The effective multiplication factors k eff , central reaction rate ratios of fast assemblies and lattice cell reaction rate ratios of thermal lattice cell assemblies were calculated and compared with testing results of B-6.2 and CENDL-2. It is obvious that 238 U data files are most important for the calculations of large fast reactors and lattice thermal reactors. However, 238 U data in the new version of ENDF/B-6 have not been renewed. Only data of 235 U, 27 Al, 14 N and 2 D have been renewed in ENDF/B-6.4. Therefor, it will be shown that the thermal reactor benchmark testing results are remarkably improved and the fast reactor benchmark testing results are not improved

Ambiente sonoro e percezione di alcune caratteristiche dei parchi urbani: analisi e modelli - Sonic environment and perception of some features of urban parks: analysis and models

Directory of Open Access Journals (Sweden)

Giovanni Brambilla

2016-07-01

Full Text Available Sui dati raccolti in otto parchi urbani, comprendenti alcuni parametri acustici e le valutazioni dei fruitori sulla qualità complessiva del parco percepita e di alcune sue caratteristiche, si è proceduto a diverse analisi statistiche. L’analisi delle componenti principali e quella cluster gerarchica sui dati acustici ha fornito una classificazione in tre gruppi risultata poco sovrapponibile a quella ottenuta con l’analisi cluster e delle corrispondenze multiple condotta sui responsi soggettivi. La discrepanza, confermata anche da alcuni modelli di regressione logistica multinomiale, evidenzia l’influenza di altri fattori non acustici sulla percezione dell’ambiente dei parchi urbani. ------ Different statistical analyses have been carried out on data collected in eight urban parks, including some acoustical parameters and the appraisals of park visitors on the perceived overall quality of the park and some of its features. Principal component analysis and hierarchical cluster one on the acoustic data have identified three groups. This classification poorly overlaps that obtained by hierarchical cluster analysis and multiple correspondence one performed on subjective appraisals data. The difference, confirmed also by models developed by multinomial logistic regression, points out the influence of other non-acoustic factors on the perception of the urban parks environment.

Capital cost: pressurized water reactor plant. Commerical electric power cost studies

International Nuclear Information System (INIS)

1977-06-01

The investment cost study for the 1139-MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume includes in addition to the foreword and summary, the plant description and the detailed cost estimate

Diagnosis of feed water, condensate and circulation pumps in electric power plants; Diagnostico de bombas de agua de alimentacion, condensado y circulacion en centrales termoelectricas

Energy Technology Data Exchange (ETDEWEB)

Colin Castellanos, Carlos [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1991-12-31

This article encompasses the analysis and the diagnosis of the pump`s performance that belong to the feed water, condensate and circulation systems of a fossil fuel power plant (FFPP). For this analysis pressure, temperature and flow data were collected by means of field installed instrumentation, as well as these pumps` motors current consumption and voltage values. Later on, the capacity and the pump efficiency are calculated and compared with the design values, to obtain the actual performance of the equipment with the aid of their characteristic curves (Q vs {Delta}H, Q vs {pi}, etc.). [Espanol] Este articulo comprende el analisis y el diagnostico de comportamiento de las bombas, las cuales forman parte de los sistemas de agua de alimentacion, condensado y circulacion de una central termoelectrica (CT). Para el analisis se recopilan datos de presion, temperatura y flujo de la instrumentacion instalada en campo, asi como de los valores de consumo de corriente y de voltaje en los motores de dichas bombas. Posteriormente, se calcula la capacidad y la eficiencia de las bombas en operacion real y se comparan con los valores de diseno, para obtener el comportamiento real del equipo con ayuda de las curvas caracteristicas (Q vs {Delta}H, Q vs {pi}, etcetera).

Diagnosis of feed water, condensate and circulation pumps in electric power plants; Diagnostico de bombas de agua de alimentacion, condensado y circulacion en centrales termoelectricas

Energy Technology Data Exchange (ETDEWEB)

Colin Castellanos, Carlos [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1992-12-31

This article encompasses the analysis and the diagnosis of the pump`s performance that belong to the feed water, condensate and circulation systems of a fossil fuel power plant (FFPP). For this analysis pressure, temperature and flow data were collected by means of field installed instrumentation, as well as these pumps` motors current consumption and voltage values. Later on, the capacity and the pump efficiency are calculated and compared with the design values, to obtain the actual performance of the equipment with the aid of their characteristic curves (Q vs {Delta}H, Q vs {pi}, etc.). [Espanol] Este articulo comprende el analisis y el diagnostico de comportamiento de las bombas, las cuales forman parte de los sistemas de agua de alimentacion, condensado y circulacion de una central termoelectrica (CT). Para el analisis se recopilan datos de presion, temperatura y flujo de la instrumentacion instalada en campo, asi como de los valores de consumo de corriente y de voltaje en los motores de dichas bombas. Posteriormente, se calcula la capacidad y la eficiencia de las bombas en operacion real y se comparan con los valores de diseno, para obtener el comportamiento real del equipo con ayuda de las curvas caracteristicas (Q vs {Delta}H, Q vs {pi}, etcetera).

Some Examples of Accident Analyses for RB Reactor

International Nuclear Information System (INIS)

Pesic, M.

2002-01-01

The RB reactor is heavy water critical assembly operated in the Vinca Institute of Nuclear Sciences, Belgrade, Yugoslavia, since April 1959. The first Safety Analysis Report of the RB critical assembly was prepared in 1961/62. But, the first accidental analysis was done in late 1958 in aim the examine power transient and total equivalent doses received by the staff during the reactivity accident occurred on October 15, 1958. Since 1960, the RB reactor is modified few times. Beside initial natural uranium metal fuel rods, new fuel (TVR-S types) from 2% enriched metal uranium and 80% enriched UO 2 were available since 1962 and 1976, respectively. Also, modifications in control and safety systems of the reactor were done occasionally. Special reactor cores were created using all three types of fuel elements, among them, the coupled fast-thermal ones. Nuclear Safety Committee of the Vinca Institute, an independent regulatory body approved for usage all these modifications of the RB reactor. For those decisions of the Committee, the Preliminary Safety Analysis Reports were prepared that, beside proposed technical modifications and new regulation rules had included analyses of various possible accidents. Special attention is given and new methodology was proposed for thoroughly analyses of design based accidents related to coupled fast-thermal cores, that include reactor central zones filled by fuel elements without moderator. In these accidents, during assumed flooding of the fast zone by moderator, a very high reactivity could be inserted in the system with very high reactivity rate. It was necessary to provide that the safety system of the reactor had fast response to that accident and had enough high (negative) reactivity to shut down the reactor timely. In this paper, a brief overview of some accidents, methodology and computation tools used for the accident analyses at RB reactor are given. (author)

Nuclear power in eastern and central Europe. Background paper

International Nuclear Information System (INIS)

Myers, L.C.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

Nuclear power in eastern and central Europe. Background paper

Energy Technology Data Exchange (ETDEWEB)

Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab.

Analisis Six Sigma pada Produk Casing Pompa sebagai Metode Perbaikan Kualitas (Studi Kasus: PT. Zenith Allmart Precisindo)

OpenAIRE

Haryono, Haryono; Rakasiwi, Hafiedza Pradana

2014-01-01

Pada Februari 2014, produk baja terbanyak yang diproduksi PT. Zenith Allmart Precisindo (ZAP) adalah casing pompa dengan reject sebesar 3,35%, padahal target maksimal reject 2% per bulan, ada gap sebesar 1,35%. Analisis DMAIC Six Sigma dilaksanakan untuk mengurangi persentase reject. Pada define, ditentukan project charter, peta proses produksi, dan SIPOC diagram. Dari SIPOC diagram ditentukan 10 CTQ. Pada fase measure dilakukan attribute agreement analysis untuk QC, hasilnya adalah repeabili...

Analisis Niat Penggunaan E-filing Di PT “X” Dan Pt”y” Surabaya Dengan Structural Equation Modeling

OpenAIRE

Jimantoro, Christina; Tjondro, Elisa

2014-01-01

Penelitian ini dilakukan untuk mengetahui pengaruh persepsi kegunaan, persepsi kemudahan, sikap penggunaan, norma subjektif dan persepsi kemampuan mengontrol terhadap niat penggunaan e-filing oleh wajib pajak orang pribadi. Sampel penelitian ini adalah 64 karyawan PT “X” dan PT “Y” di Surabaya. Teknik analisis data yang digunakan adalah Structural Equation Modelling berbasis Variance (Partial Least Square).Hasil penelitian ini menunjukkan adanya pengaruh persepsi kegunaan dan kemudahan terhad...

ANALISIS PENERAPAN STRATEGI PEMASARAN DALAM PENINGKATAN PANGSA PASAR PADA PT. HADJI KALLA (TOYOTA) CABANG URIP DI MAKASSAR

OpenAIRE

MAULADI RAHMAN, EKI

2012-01-01

- EKI MAULADI RAHMAN, A211 076 644. Analisis Penerapan Strategi Pemasaran Dalam Peningkatan Pangsa Pasar Pada PT. Hadji Kalla (Toyota) Cabang Urip di Makassar. (dibimbing oleh Muhammad Ismail dan Mukhtar) Tujuan dari penelitian ini adalah untuk mengetahui penerapan strategi pemasaran mobil Toyota pada PT. Hadji Kalla (Toyota) Cabang Urip di Makassar melalui penerapan (produk, harga, promosi dan saluran distribusi) dalam peningkatan pangsa pasar, untuk menganlisis sejauh mana penerapan ...

Physical Characteristics of the Dalat Nuclear Research Reactor; Cac dac trung vat ly lo cua lo phan ung hat nhan Da Lat

Energy Technology Data Exchange (ETDEWEB)

Huy, Ngo Quang [ed.; Nuclear Research Inst., Da Lat (Viet Nam)

1994-10-01

The operation of the TRIGA MARK II reactor of nominal power 250 KW has been stopped as all the fuel elements have been dismounted and taken away in 1968. The reconstruction of the reactor was accomplished with Russian technological assistance after 1975. The nominal power of the reconstructed reactor is of 500 KW. The recent Dalat reactor is unique of its kind in the world: Russian-designed core combined with left-over infrastructure of the American-made TRIGA II. The reactor was loaded in November 1983. It has reached physical criticality on 1/11/1983 (without central neutron trap) and on 18/12/1983 (with central neutron trap). The power start up occurred in February 1984 and from 20/3/1984 the reactor began to be operated at the nominal power 500 KW. The selected reports included in the proceedings reflect the start up procedures and numerous results obtained in the Dalat Nuclear Research Institute and the Centre of Nuclear Techniques on the determination of different physical characteristics of the reactor. These characteristics are of the first importance for the safe operation of the Dalat reactor.

Two design aspects connected with the safety of the PIK reactor presently under construction

International Nuclear Information System (INIS)

Gostev, V.V.; Zakharov, A.S.; Konoplev, K.A.; Levandovskii, N.V.; Ploshchanskii, L.M.; Smolsky, S.L.

1993-01-01

The PIK reactor is designed for physical research with neutron beams and sample irradiation. In the central trap the thermal neutrons flux is 4x10 15 n/cm 2 s. The reactor power is 100 MW, the thermal neutron flux in the reflector at the maximum of distribution is 1x10 15 n/cm 2 s. The core with a high uranium concentration of 600 g/l is light water-cooled, heavy water being used in the reflector. The Chernobyl disaster happened at the time of equipment installation at the PIK. The code revision, a change of the authors ideas about the safety, and a change of public attitude towards nuclear installations resulted in a stopping of construction and project revision. Reconstruction project has led to a change of all safety systems and involved in various degrees all essential reactor systems. The construction is presently resumed in spite of economic difficulties in Russia. The reactor was inspected by experts from a number of European countries, USA, and European Commission delegated by their governments to prepare a report on whether supporting the construction to its completion would be reasonable. In the course of inspection the experts from USA and EU expressed doubts concerning two systems, namely, the containment and scram. These two points are discussed in the present paper. Three type of containments are proposed and an analysis of their efficiency is presented. The PIK reactor is controlled by eight rods in the heavy-water reflector -and an absorbing cylinder at the boundary between the core and the central light-water neutron trap. The rods are used for emergency protection and reactor start-up. The central control cylinder called here the shutter serves several functions, namely, as scram, automatic control, and burnup compensation. The delay time before the onset of negative reactivity is 1.05 sec for rods and 0.25 sec for the shutter

Paracoccidioidomycosis of the central nervous system: CT findings

Energy Technology Data Exchange (ETDEWEB)

Rodacki, M.A. [Section of Neuroradiology, Service of Radiology, Sta Isabel Hospital, Sta Catarina (Brazil); Toni, G. de [University Hospital, Medical School of Curitiba, Parana (Brazil); Borba, L.A. [Division of Neurosurgery, Sta Isabel Hospital, Blumenau, Sta Catarina (Brazil); Oliveira, G.G. [Division of Pathology, Sta Isabel Hospital, Blumenau, Sta Catarina (Brazil)

1995-11-01

A retrospective analisis of six cases of central nervous system paracoccidioidomycosis, all but one proven by biopsy and surgery, was carried out to study the CT and clinical data and pathological correlation. Most of the patients were from the country. Headache, vomiting, seizures and hemiparesis were the most frequent symptoms. Papilloedema was present in four patients with raised intracranial pressure. Five patients had chronic lung disease and two with advanced systemic disease, skin and mucous membrane lesions were also observed. The neurological disturbance was sometimes the presenting features and the diagnosis was discovered incidentally after surgery. Both solitary and multiple parenchymal lesions were observed and the cerebral hemispheres were more commonly involved in four patients. Local meningeal involvement was observed in one with a single cortical granuloma. We enphasise the usefulness of CT, showing a rounded or lobulated mass with an isodense or radiolucent centre after contrast enhancement, surrounded by an irregular wall of varying thickness. There was always moderate oedema, extending peripherally. Other infections or neoplastic diseases may present similar findings. Preoperative diagnosis should rest on integration of clinical data, chest films, laboratory and neuroimaging studies. (orig.). With 4 figs., 2 tabs.

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

Reactor core of FBR type reactor

International Nuclear Information System (INIS)

Hayashi, Hideyuki; Ichimiya, Masakazu.

1994-01-01

A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

Refurbishment programme for the BR2-reactor

Energy Technology Data Exchange (ETDEWEB)

Koonen, E [Centre d' Etude de l' Energie Nucleaire, Studiecentrum voor Kernenergie, BR2 Department, Boeretang, Mol (Belgium)

1992-07-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

Refurbishment programme for the BR2-reactor

International Nuclear Information System (INIS)

Koonen, E.

1992-01-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

Recovery of a broken inspection lance from the reactor vessel of the German sodium cooled fast breeder reactor SNR 300

International Nuclear Information System (INIS)

Menck, J.W.; Hoeft, E.; Kirchner, G.

1988-01-01

An inspection lance for flow and vibration measurements was installed into the SNR-300 rotating plug. Centering and guiding of the lower end of the lance was effected in the central grid plate insert. The lance was torn off due to handling problems. The task consisted in recovering all defective parts from the reactor vessel and re-establishing the intact initial state. (author)

Analisi dell’anisotropia microstrutturale in materiali compositi rinforzati con fibre corte

Directory of Open Access Journals (Sweden)

D. Dreossi

2008-01-01

Full Text Available La microtomografia con luce di sincrotrone si è rivelata una tecnica particolarmente efficace per l’analisi della struttura risultante dalla distribuzione degli orientamenti assunti dalle fibre di rinforzo di compositi rinforzati con fibre di vetro. La ricostruzione dell'immagine tridimensionale ha consentito la visualizzazionedella distribuzione spaziale delle fibre all'interno della matrice polimerica anche nel caso di fibre di piccole dimensioni (diametro medio di 10 micrometri. E' stato quindi possibile misurare le differenze nell'orientamento delle fibre nei differenti strati di un campione utilizzando metodi basati sulla valutazione del Mean Intercept Length (MIL e del fabric tensor. La tecnica descritta è stata applicata a un campione di poliammide 6 rinforzato con il 30% di fibre corte di vetro ricavato da lastra.

ANALISIS NERACA PERDAGANGAN MIGAS DAN NON MIGAS INDONESIA TERHADAP VOLATILITAS CADANGAN DEVISA 2003-2013

Directory of Open Access Journals (Sweden)

Haniyah Safitri

2014-10-01

Full Text Available Abstrak ___________________________________________________________________ Cadangan devisa adalah asset ataupun aktiva dari bank sentral. Cadangan devisa tersimpan dalam mata uang asing seperti dolar, euro, yen dan digunakan untuk perdagangan internasional dan membiayai perekonomian sebuah negara. Cadangan ini tersimpan dalam neraca pembayaran. Krisis Asia 1997 dulu, membuat Indonesia mengalami krisis moneter yang berkepanjangan. Hal ini berdampak terhadap perdagangan internasional (Ekspor Impor dan mengalami krisi nilai tukar. Mempengaruhi perekonomian kita dan mengakibatkan kita kehilangan kepercayaan negara lain terkhususnya Negara Dunia Pertama. Judul jurnal ini adalah “ Analisis Neraca Perdagangan Migas dan Nonmigas Indonesia Terhadap Volatilitas Cadangan Devisa “. Neraca perdagangan migas dan nonmigas Indonesia mengakibatkan volatilitas yang berdampak tergerusnya cadangan devisa dan melemahnya nilai tukar rupiah. Abstract ___________________________________________________________________ Foreign exchange reserves is an asset of central Bank. It has saved by reserve currency like dolar, euro, yen and uses for beganing international trade and covered the economic of the country. It saved in a Balance Payment (BOP Prior to the 1997 Asia economic crisis, make Indonesia got a long time crisis monetary. It effected to the international trade (Export and Import and got the exchange rate crisis. The influence our economy and we lost trust from another country especially’ The First Country’ and causes decrease our Balance Of Payment. The title of this journal is "Analysis of Oil and Non-oil Trade Balance Indonesia Against Volatility Reserves". Oil and non-oil trade balance volatility impacting Indonesia resulted in erosion of foreign reserves and a weakening of the exchange rate. © 2014 Universitas Negeri Semarang

Synfuels from fusion: producing hydrogen with the tandem mirror reactor and thermochemical cycles

International Nuclear Information System (INIS)

Ribe, F.L.; Werner, R.W.

1981-01-01

This report examines, for technical merit, the combination of a fusion reactor driver and a thermochemical plant as a means for producing synthetic fuel in the basic form of hydrogen. We studied: (1) one reactor type - the Tandem Mirror Reactor - wishing to use to advantage its simple central cell geometry and its direct electrical output; (2) two reactor blanket module types - a liquid metal cauldron design and a flowing Li 2 O solid microsphere pellet design so as to compare the technology, the thermal-hydraulics, neutronics and tritium control in a high-temperature operating mode (approx. 1200 K); (3) three thermochemical cycles - processes in which water is used as a feedstock along with a high-temperature heat source to produce H 2 and O 2