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Sample records for basf-industriekernkraftwerk reaktor 2

  1. Implementation of parallel processing in the basf2 framework for Belle II

    International Nuclear Information System (INIS)

    Itoh, Ryosuke; Lee, Soohyung; Katayama, N; Mineo, S; Moll, A; Kuhr, T; Heck, M

    2012-01-01

    Recent PC servers are equipped with multi-core CPUs and it is desired to utilize the full processing power of them for the data analysis in large scale HEP experiments. A software framework basf2 is being developed for the use in the Belle II experiment, a new generation B-factory experiment at KEK, and the parallel event processing to utilize the multi-core CPUs is in its design for the use in the massive data production. The details of the implementation of event parallel processing in the basf2 framework are discussed with the report of preliminary performance study in the realistic use on a 32 core PC server.

  2. BASF: the choice of chemistry

    International Nuclear Information System (INIS)

    Champion, E.

    2001-01-01

    Here are given the results of the firm BASF for the year 2000. The turnover has reached a historical record; these exceptional results are justified by the last sales and acquiring of the firm BASF and in particular by the cession of its pharmaceutical activities to the Abbott laboratories. (O.M.)

  3. Final Techno-Economic Analysis of 550 MWe Supercritical PC Power Plant CO2 Capture with Linde-BASF Advanced PCC Technology

    Energy Technology Data Exchange (ETDEWEB)

    Bostick, Devin [Linde LLC, Murray Hill, NJ (United States); Stoffregen, Torsten [Linde AG Linde Engineering Division, Dresden (Germany); Rigby, Sean [BASF Corporation, Houston, TX (United States)

    2017-01-09

    This topical report presents the techno-economic evaluation of a 550 MWe supercritical pulverized coal (PC) power plant utilizing Illinois No. 6 coal as fuel, integrated with 1) a previously presented (for a subcritical PC plant) Linde-BASF post-combustion CO2 capture (PCC) plant incorporating BASF’s OASE® blue aqueous amine-based solvent (LB1) [Ref. 6] and 2) a new Linde-BASF PCC plant incorporating the same BASF OASE® blue solvent that features an advanced stripper interstage heater design (SIH) to optimize heat recovery in the PCC process. The process simulation and modeling for this report is performed using Aspen Plus V8.8. Technical information from the PCC plant is determined using BASF’s proprietary thermodynamic and process simulation models. The simulations developed and resulting cost estimates are first validated by reproducing the results of DOE/NETL Case 12 representing a 550 MWe supercritical PC-fired power plant with PCC incorporating a monoethanolamine (MEA) solvent as used in the DOE/NETL Case 12 reference [Ref. 2]. The results of the techno-economic assessment are shown comparing two specific options utilizing the BASF OASE® blue solvent technology (LB1 and SIH) to the DOE/NETL Case 12 reference. The results are shown comparing the energy demand for PCC, the incremental fuel requirement, and the net higher heating value (HHV) efficiency of the PC power plant integrated with the PCC plant. A comparison of the capital costs for each PCC plant configuration corresponding to a net 550 MWe power generation is also presented. Lastly, a cost of electricity (COE) and cost of CO2 captured assessment is shown illustrating the substantial cost reductions achieved with the Linde-BASF PCC plant utilizing the advanced SIH configuration in combination with BASF’s OASE® blue solvent technology as compared to the DOE/NETL Case 12 reference. The key factors contributing to the reduction of COE and the cost of CO2 captured

  4. Awakening interest in the natural sciences - BASF's Kids' Labs.

    Science.gov (United States)

    Lang, Cinthia

    2012-01-01

    At BASF's Ludwigshafen headquarters, kids and young adults in grades 1-13 can learn about chemistry in the Kids' Labs. Different programs exist for different levels of knowledge. In the two 'Hands-on Lab H(2)O & Co.' Kids' Labs, students from grades 1-6 explore the secrets of chemistry. BASF Kids' Labs have now been set up in over 30 countries. In Switzerland alone, almost 2,000 students have taken part in the 'Water Loves Chemistry' Kids' Lab since it was started in 2011. In Alsace, 600 students have participated to date. In the Teens' Lab 'Xplore Middle School', middle school students explore five different programs with the themes 'substance labyrinth', 'nutrition', 'coffee, caffeine & co.', 'cosmetics' and 'energy'. Biotechnological methods are the focus of the Teens' Lab 'Xplore Biotech' for students taking basic and advanced biology courses. In the 'Xplore High School' Teens' Lab, chemistry teachers present their own experimental lab instruction for students in basic and advanced chemistry courses. The Virtual Lab has been expanding the offerings of the BASF Kids' Labs since 2011. The online lab was developed by the company for the International Year Of Chemistry and gives kids and young adults the opportunity to do interactive experiments outside of the lab.

  5. Opportunities and challenges at the interface between petrochemistry and refinery. The BASF perspective

    Energy Technology Data Exchange (ETDEWEB)

    Blankertz, H.J. [BASF AG, Ludwigshafen (Germany)

    2007-07-01

    The author of the contribution under consideration reports on the BASF perspective according to opportunities and challenges at the interface between petrochemistry and refinery. This contribution is divided into the following chapters: (a) Overview BASF-Group; (b) Overview BASF Petrochemicals; (c) The refinery-chemistry interface; (d) Main focus refineries; (e) Interface challenges and opportunities; (f) What can BASF do for refineries. BASF employs the Verbund concept, a system that combines production with energy needs in an intelligent way. The idea is to reduce of primary energy carriers both in terms of raw materials and for power and steam generation. The authors describes the petrochemicals of BASF AG (Ludwigshafen, Federal Republic of Germany), the raw material development, evolution of thermal steamcracking and crackerproducts. Major feedstock source of the European petrochemical industry are streams out of refineries which can't be used for transportation fuels. The gap between propylene demand and production out of steam crackers has to be closed by propylene out for FCC's. Demand for aromatics (xylenes and benzene, and to a lesser extent toluene) needs to be filled in by aromatics out of refineries. Market drivers for the refining industry are lowering crude costs, growing clean products, increasing capacity and enhancing E and P integration. BASF has various business with the oil und refining industry and provides solutions for oil field chemicals, process chemicals and performance additives. The author explains which kind of products and services BASF provides for refiners.

  6. DESAIN KONSEPTUAL TERAS REAKTOR RISET INOVATIF BERBAHAN BAKAR URANIUM MOLIBDENUM DARI ASPEK NEUTRONIK

    Directory of Open Access Journals (Sweden)

    Tukiran Surbakti

    2015-03-01

    Full Text Available Manfaat yang luas dari penggunaan reaktor riset membuat banyak negara membangun reaktor riset baru. Kecenderungan saat ini adalah reaktor tipe reaktor serbaguna (MPR dengan teras yang kompak untuk mendapatkan fluks neutron yang tinggi dengan daya yang relatif sedang atau rendah. Reaktor riset yang ada di Indonesia yang paling muda usianya sudah berumur 25 tahun. Oleh karena itu diperlukan desain reaktor riset baru sebagai alternatif, disebut reaktor riset inovatif (RRI, kelak pengganti reaktor riset yang sudah ada. Tujuan dari riset ini mendapatkan konfigurasi teras setimbang reaktor riset yang optimal dengan kriteria memiliki fluks neutron termal minimum sebesar 2,5x1014 n/cm2 s pada daya 20 MW (minimum, memiliki panjang operasi satu siklus lebih dari 40 hari dan penggunaan bahan bakar yang paling efisien. Desain neutronik dilakukan untuk bahan bakar baru U-9Mo-Al dengan kerapatan bervariasi dan jenis reflektor yang bervariasi. Desain dilakukan dengan paket program WIMSD-5B dan BATAN-FUEL. Hasil desain konseptual menyajikan 4 konfigurasi teras yaitu 5×5, 5×7, 6×5 dan 6×6. Hasil optimasi menunjukkan bahwa teras setimbang reaktor RRI dengan konfigurasi 5×5, tingkat muat 235U sebesar 450 g, reflektor berilium, fluks neutron termal maksimum di daerah reflektor sebesar 3,33×1014 neutron cm-2s-1 dan panjang siklus 57 hari merupakan desain teras reaktor riset inovatif yang paling optimal. Kata kunci: desain konseptual, bahan bakar uranium-molibdenum,berilium, D2O, WIMS, BATAN-FUEL   The multipurpose of research reactor utilization make many countries build the new research reactor. Trend of this reactor for this moment is multipurpose reactor type with a compact core to get high neutron flux at the low or medium level of power. The research newest reactor in Indonesia right now is already 25 year old. Therefore, it is needed to design a new research reactor, called innovative research reactor (IRR and then as an alternative to replace the old

  7. ANALISIS PENGARUH DENSITAS BAHAN BAKAR SILISIDA TERHADAP PARAMETER KINETIK TERAS REAKTOR RSG-GAS

    Directory of Open Access Journals (Sweden)

    Tukiran s

    2016-11-01

    Full Text Available Saat ini RSG-GAS menggunakan elemen bakar silisida 2,96 g U/cc. Untuk meningkatkan waktu operasi reaktor maka akan direncanakan untuk mengganti elemen bakar silisida dengan kerapatan yang lebih tinggi. Keuntungan reaktor dengan bahan bakar kerapatan tinggi adalah dapat lebih efektif dan efisien. Maka perlu dilakukan perhitungan parameter kinetik teras silisida kerapatan tinggi mengingat pengaruhnya sangat penting untuk keselamatan operasi reaktor. Parameter kinetik yang dihitung yaitu fraksi neutron kasip efektif, konstanta peluruhan neutron kasip, umur neutron serempak yang merupakan faktor utama dalam kontrol dan keselamatan. Bahan bakar silisida tipe pelat dengan densitas 2,96 - 4,8 gU/cm3 digunakan pada teras RSG-GAS untuk menganalisis perhitungan parameter kinetik. Perhitungan sel dilakukan dengan paket program WIMSD-5B dan paket program Batan-2DIFF digunakan untuk perhitungan teras. Hasil perhitungan menunjukkan bahwa harga fraksi neutron kasip turun dengan naiknya densitas bahan bakar. Turunnya nilai parameter kinetik ini tidak mengganggu pergantian bahan bakar ke densitas yang lebih tinggi. Turunnya nilai parameter kinetik rata-rata dari densitas 2,96 gU/cm3 ke 3,55 gU/cm3 adalah 1,3 % sedangkan dari densitas 2,96 gU/cm3 ke 4,8 gU/cm3 adalah 2,2 % . Sehingga jika dilakukan pergantian bahan bakar maka ditinjau dari segi neutronik dan parameter kinetiknya tidak akan mengalami perubahan dalam pola operasi reaktor atau manajemen bahan bakar dan tidak akan berpengaruh terhadap keselamatan operasi reaktor.

  8. 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

  9. ANALISIS POLA MANAJEMEN BAHAN BAKAR DESAIN TERAS REAKTOR RISET TIPE MTR

    Directory of Open Access Journals (Sweden)

    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

  10. 76 FR 32332 - BASF Corp.; Filing of Food Additive Petition (Animal Use); Methyl Esters of Conjugated Linoleic...

    Science.gov (United States)

    2011-06-06

    .... FDA-2011-F-0365] BASF Corp.; Filing of Food Additive Petition (Animal Use); Methyl Esters of... petition proposing that the food additive regulations be amended to provide for the safe use of methyl... is given that a food additive petition (FAP 2269) has been filed by BASF Corp. (BASF), 100 Campus Dr...

  11. REAKTOR INNOVATIVE MOLTEN SALT (IMSR DENGAN SISTEM KESELAMATAN PASIF MENYELURUH

    Directory of Open Access Journals (Sweden)

    Andang Widiharto

    2015-04-01

    Full Text Available Pengembangan Teknologi Reaktor Nuklir pada masa mendatang mengarah pada peningkatan aspek keselamatan, peningkatan pendayagunaan bahan bakar, reduksi limbah radioaktif, ketahanan terhadap proliferasi bahan-bakar nuklir dan peningkatan aspek ekonomi. reaktor Innovative Molten Salt (IMSR adalah reaktor nuklir yang menggunakan bahan bakar cair berupa garam lebur fluoride (7LiF-ThF4-UF4-MaFx. Reaktor IMSR didesain sebagai reaktor pembiak termal, yaitu membiakkan U-233 dari Th-232. Hal ini untuk menjawab permasalahan sustainabilitas ketersedian sumber daya bahan bakar nuklir dan reduksi limbah radioaktif. Dalam aspek keselamatan, desain reaktor IMSR memiliki sifat inherent safe, yaitu koefisien umpan balik daya yang negatif serta memiliki fitur-fitur keselamatan pasif. Fitur-fitur keselamatan pasif terdiri dari sistem shutdown pasif, sistem pendinginan pasif pasca shutdown serta sistem pendinginan pasif untuk produk fisi. Kecelakaan yang berpotensi terjadi pada IMSR, yaitu kecelakaan kehilangan aliran bahan bakar, kecelakaan kehilangan aliran pendingin, kecelakaan kehilangan kemampuan pengambilan kalor serta kecelakaan kerusakan integritas sistem reaktor, dapat ditangani sepenuhnya secara pasif hingga mencapai kondisi shutdown selamat. Kata kunci: keselamatan pasif, inherent safe, IMSR   The next Nuclear Reactor Technology developments are directed to the increasing of the aspects of safety, fuel utility, radioactive waste reduction, proliferation retention and economy. Innovative Molten Salt Reactor (IMSR is a nuclear reactor design that uses fluoride molten salt (7LiF-ThF4-UF4-MaFx. IMSR is designed as a thermal breeder reactor, i.e. to produce U-233 from Th-232. This is the answer of natural nuclear fuel sustainability and radioactive waste problems. In term of safety aspect, IMSR design has inherent safe characteristics, i.e. negative power feedback coefficient, and passive safety features. The passive safety features are passive shutdown

  12. ANALISIS DESAIN PROSES SISTEM PENDINGIN PADA REAKTOR RISET INOVATIF 50 MW

    Directory of Open Access Journals (Sweden)

    Sukmanto Dibyo

    2015-03-01

    Full Text Available Reaktor Riset Inovatif (RRI merupakan jenis MTR (Material Testing Reactor yang dipersiapkan ke depan sebagai desain reaktor baru. Daya RRI telah ditetapkan dari perhitungan neutronik dan termohidrolika teras yaitu 50 MW termal. Reaktor bertekanan 8 kgf/cm2 dan laju aliran massa pendingin primer 900 kg/s. Tantangan yang penting dalam menindak lanjuti desain reaktor ini adalah analisis desain pada sistem pendingin. Makalah ini bertujuan untuk menganalisis desain proses sistem pendingin utama reaktor RRI daya 50 MW (RRI-50 dengan menggunakan program Chemcad 6.1.4. Dalam analisis ini dilakukan perhitungan neraca massa dan energi (mass/energy balances pada sistem pendingin primer dan sekunder sebagai pendingin utama. Masing-masing sistem pendingin tersebut terdiri dari 2 jalur beroperasi secara paralel dan 1 jalur redundansi. Disamping itu untuk desain termal unit komponen telah dianalisis dengan program RELAP5, frenchcreek dan Metoda Analitik. Hasil analisis yang diperoleh adalah desain diagram sistem pendingin yang mencakup data parameter entalpi, temperatur, tekanan dan laju aliran massa pendingin untuk masing-masing jalur. Adapun hasil desain unit komponen utama pada RRI-50 adalah tangki tunda dengan volume 51,5 m3, 2 unit pompa sentrifugal dan 1 unit pompa cadangan pada pendingin primer daya 141 kW/pompa dan pendingin sekunder daya 206 kW/pompa, 2 unit penukar panas tipe shell-tube dengan koefisien termal overall 1377 W/m2.oC dan 4 unit menara pendingin yang mampu melepaskan panas ke udara dengan desain temperatur approach 5,0 oC dan temperatur range 9,0 oC. Desain sistem pendingin reaktor RRI-50 ini telah menetapkan parameter operasi sistem pendingin yaitu temperatur, tekanan dan laju aliran massa pendingin dengan mempertimbangkan tuntutan aspek keselamatan teras reaktor sehingga desain temperatur maksimum pendingin masuk ke teras 44,5 oC. Kata kunci : RRI 50 MW, desain sistem pendingin, program Chemcad 6.1.4   Innovative Research Reactor RRI

  13. UJI COBA TEKNOLOGI BIOFILM KONSORSIUM BAKTERI PADA REAKTOR SEMIANAEROB-AEROB UNTUK PENGOLAHAN AIR LIMBAH DI INDUSTRI PENCELUPAN TEKSTIL SKALA RUMAH TANGGA

    Directory of Open Access Journals (Sweden)

    Dewa Ketut Sastrawidana

    2013-04-01

    Full Text Available Penelitian ini bertujuan untuk menganalisis efektifitas teknologi biofilm konsorsium bakteri pada  reaktor semianaerob-aerob ntuk mengolah air limbah pencelupan tekstil. Bakteri pada reaktor semianaerob terdiri dari  Aeromonas sp. Pseudomonas sp, dan Flavobacterium sp. sedangkan pada reaktor aerob terdiri dari Vibrio sp. Plesiomonas sp. dan Enterobacter sp. Perombakan proses pertumbuhan terlekat diawali dengan menumbuhkan konsorsium bakteri pada masing-masing reaktor selama 10  hari menggunakan pada batu vulkanik merah sebagai media pelekatan bakteri. Setelah terbentuk biofilm,selanjutnya digunakan untuk merombak limbah denagn waktu tinggal limbah 2 hari. Hasil penelitian menunjukkan teknologi biofilm cukup efektif diaplikasikan pada skala lapang menghasilkan efisiensi perombakan TSS, BOD dan COD secara berturut-turut sebesar 84,7%; 80,56% dan 90,40%. Uji toksisitas air limbah tekstil menggunakan ikan nila dengan waktu paparan 3 hari menunjukkan bahwa air limbah tekstil sebelum diolah berkatagori toksik ringan dengan nilai EC50 adalah 88,80% sedangkan setelah diolah dalam reaktor biofilm konsorsium bakteri sistem anaerob-aerob selama 2 hari menjadi katagori tidak toksik dengan nilai EC50 sebesar 101,64%. Dengan demikian, pengolahan limbah tektil dengan sistem kombinasi anaerob-aerob menghasilkan kualitas limbah dengan kriteria sudah memenuhi baku mutu untuk dibuang ke lingkungan.

  14. ANALISIS SEBARAN RADIONUKLIDA PADA KONDISI NORMAL UNTUK REAKTOR AEC 1000 MW

    Directory of Open Access Journals (Sweden)

    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

  15. PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS

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    A. G. Abdullah

    2014-07-01

    Full Text Available Kelengkapan sistem keselamatan pasif dan inheren pada reaktor lanjut merupakan prasyarat utama. Makalah ini mengeksplorasi hasil desain konseptual sistem pembuang sisa panas pada pusat listrik tenaga nuklir berjenis Very High-Temperature Reactor. Tujuan riset ini untuk merancang sistem pembuang sisa panas pusat listrik tenaga nuklir yang terdapat pada dinding reaktor. Studi kinerja Reactor Vessel Auxliary Cooling System (RVACS dilakukan pada dua jenis pendingin yaitu Timbal-Bismut dan Liquid Salt. Panas dari dinding reaktor dihapus melalui sirkulasi alamiah pada keadaan tunak. Analisis melibatkan sistem perpindahan panas secara radiasi, konduksi dan konveksi alami. Perhitungan perpindahan panas dilakukan pada elemen reaktor vessel, dinding luar guard vessel, dan pelat pemisah. Hasil analisis kecelakaan menunjukkan kedua jenis sistem pendingin reaktor dan sistem pasif sisa pembuangan panas cukup menghapus sisa panas hasil peluruhan dengan sirkulasi alami.ABSTRACTCompleteness of passive safety systems and inherent in advanced reactors is a major prerequisite. This paper explores the results of a conceptual design of the heat removal system at the nuclear power plant (NPP type Very High-Temperature Reactor. The purpose of this research was to design the reactor vessel auxiliary cooling system (RVACS of NPP located within the reactor walls. The RVACS performance study was conducted on two types of coolant: Lead-Bismuth and Liquid Salt. Heat was removed from the reactor vessel through the natural circulation in the steady state. Analyses of heat transfer systems involved radiation, conduction and natural convection. Heat transfer calculations were performed on the reactor vessel, guard vessel, and perforated plate. The results from the accident analysis showed that both types, the reactor coolant system and the passive residual heat removal system, adequately remove remaining heat of the decay by a natural circulation.

  16. Industrial applications using BASF eco-efficiency analysis: perspectives on green engineering principles.

    Science.gov (United States)

    Shonnard, David R; Kicherer, Andreas; Saling, Peter

    2003-12-01

    Life without chemicals would be inconceivable, but the potential risks and impacts to the environment associated with chemical production and chemical products are viewed critically. Eco-efficiency analysis considers the economic and life cycle environmental effects of a product or process, giving these equal weighting. The major elements of the environmental assessment include primary energy use, raw materials utilization, emissions to all media, toxicity, safety risk, and land use. The relevance of each environmental category and also for the economic versus the environmental impacts is evaluated using national emissions and economic data. The eco-efficiency analysis method of BASF is briefly presented, and results from three applications to chemical processes and products are summarized. Through these applications, the eco-efficiency analyses mostly confirm the 12 Principles listed in Anastas and Zimmerman (Environ. Sci. Technol. 2003, 37(5), 94A), with the exception that, in one application, production systems based on bio-based feedstocks were not the most eco-efficient as compared to those based on fossil resources. Over 180 eco-efficiency analyses have been conducted at BASF, and their results have been used to support strategic decision-making, marketing, research and development, and communication with external parties. Eco-efficiency analysis, as one important strategy and success factor in sustainable development, will continue to be a very strong operational tool at BASF.

  17. PEMODELAN TERAS UNTUK ANALISIS PERHITUNGAN KONSTANTA MULTIPLIKASI REAKTOR HTR-PROTEUS

    Directory of Open Access Journals (Sweden)

    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

  18. RA Research reactor, Annual report 1986; Istrazivacki nuklearni reaktor RA - Izvestaj za 1986. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1986-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1986 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  19. Fire modeling of the Heiss Dampf Reaktor containment

    International Nuclear Information System (INIS)

    Nicolette, V.F.; Yang, K.T.

    1995-09-01

    This report summarizes Sandia National Laboratories' participation in the fire modeling activities for the German Heiss Dampf Reaktor (HDR) containment building, under the sponsorship of the United States Nuclear Regulatory Commission. The purpose of this report is twofold: (1) to summarize Sandia's participation in the HDR fire modeling efforts and (2) to summarize the results of the international fire modeling community involved in modeling the HDR fire tests. Additional comments, on the state of fire modeling and trends in the international fire modeling community are also included. It is noted that, although the trend internationally in fire modeling is toward the development of the more complex fire field models, each type of fire model has something to contribute to the understanding of fires in nuclear power plants

  20. RA research nuclear reactor - Annual report 1985; Istrazivacki nuklearni reaktor RA - Izvestaj za 1985. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1985 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  1. PENGARUH KONSENTRASI ZrO2 TERHADAP KORELASI PERPINDAHAN PANAS NANOFLUIDA AIR-ZrO2 UNTUK PENDINGIN REAKTOR

    Directory of Open Access Journals (Sweden)

    K.A. Sudjatmi

    2015-03-01

    Full Text Available Sejalan dengan perkembangan konsep keselamatan pasif pada sistem keselamatan PLTN, maka sistem perpindahan panas konveksi alam memegang peranan penting. Pemakaian nanofluid sebagai fluida pendingin pada sistem keselamatan nuklir dapat digunakan pada Sistem Pendingin Teras Darurat dan Sistem Pendingin Pengungkung Luar Reaktor. Beberapa peneliti telah melakukan studi desain konseptual aplikasi nanofluid untuk meningkatkan keselamatan AP1000 dan sistem pendingin teras darurat pada reaktor daya eksperimen. Penerapan nanofluida juga mulai dikembangkan melalui hasil penelitian perpindahan panas konveksi alamiah pada sub-buluh dengan nanofluida sebagai fluida kerjanya sangat dibutuhkan. Penelitian ini bertujuan untuk menentukan pengaruh perubahan konsentrasi ZrO2 terhadap korelasi perpindahan panas konveksi alamiah dengan pendekatan eksperimental. Data eksperimental yang diperoleh digunakan untuk mengembangkan korelasi umum empirik perpindahan panas konveksi alamiah. Metode penelitian dengan menggunakan alat uji sub-buluh vertikal dengan geometri segitiga dan segiempat menggunakan air dan nanofluida air-ZrO2 sebagai fluida kerjanya. Konsentrasi nanopartikel dalam larutan yang digunakan sebesar 0,05 %, 0,10% dan 0,15 % dalam persen berat. Hasil penelitian menunjukan bahwa untuk bilangan Rayleigh yang sama, kemampuan pemindahan kalor oleh nanofluida air-ZrO2 lebih baik dari pada pemindahan kalor oleh air. Namun peningkatan konsentrasi nanofluida tidak selalu mendapatkan kemampuan pemindahan kalor yang lebih baik. Kata kunci: nanofluida air-ZrO2, konveksi alamiah, sub-buluh segitiga, sub-buluh segi segiempat   In line with the development of the passive safety concept for the safety systems of nuclear power plants, the natural convection heat transfer system plays an important role. The nanofluid as coolant fluid on nuclear safety system can be used in Emergency core cooling system and in reactor coolant system confinement. Several researchers have

  2. ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA

    Directory of Open Access Journals (Sweden)

    Andi Sofrany Ekariansyah

    2015-06-01

    Full Text Available ABSTRAK ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA. Kecelakaan yang diakibatkan oleh kehilangan pendingin (loss of coolant accident / LOCA dari sistem reaktor merupakan kejadian dasar desain yang tetap diantisipasi dalam desain reaktor daya yang mengadopsi teknologi Generasi II hingga IV. LOCA ukuran kecil (small break LOCA memiliki dampak yang lebih signifikan terhadap keselamatan dibandingkan LOCA ukuran besar (large break LOCA seperti terlihat pada kejadian Three-Mile Island (TMI. Fokus makalah adalah pada analisis small break LOCA pada reaktor daya maju Generasi III+ yaitu AP1000 dengan mensimulasikan tiga kejadian pemicu yaitu membukanya katup Automatic Depressurization System (ADS secara tak disengaja, putusnya salah satu pipa Direct Vessel Injection (DVI secara double-ended, dan putusnya pipa lengan dingin dengan diameter bocoran 10 inci. Metode yang digunakan adalah simulasi kejadian pada model AP1000 yang dikembangkan secara mandiri menggunakan program perhitungan RELAP5/SCDAP/Mod3.4. Dampak yang ingin dilihat adalah kondisi teras selama terjadinya small break LOCA yang terdiri dari pembentukan mixture level dan transien temperatur kelongsong bahan bakar. Hasil simulasi menunjukkan bahwa mixture level untuk semua kejadian small break LOCA berada di atas tinggi teras aktif yang menunjukkan tidak terjadinya core uncovery. Adanya mixture level berpengaruh pada transien temperatur kelongsong yang menurun dan menunjukkan pendinginan bahan bakar yang efektif. Hasil di atas juga identik dengan hasil perhitungan program lain yaitu NOTRUMP. Keefektifan pendinginan teras juga disebabkan oleh berfungsinya injeksi pendingin melalui fitur keselamatan pasif yang menjadi ciri reaktor daya AP1000. Secara keseluruhan, hasil analisis menunjukkan model AP1000 yang telah dikembangkan dengan RELAP5 dapat digunakan untuk keperluan analisis kecelakaan dasar desain pada reaktor daya maju AP1000. Kata kunci: analisis

  3. 78 FR 66892 - BASF Plant Science LP; Availability of Plant Pest Risk Assessment and Environmental Assessment...

    Science.gov (United States)

    2013-11-07

    .... Kevin Shea, Administrator, Animal and Plant Health Inspection Service. [FR Doc. 2013-26701 Filed 11-6-13... DEPARTMENT OF AGRICULTURE Animal and Plant Health Inspection Service [Docket No. APHIS-2012-0028] BASF Plant Science LP; Availability of Plant Pest Risk Assessment and Environmental Assessment for...

  4. ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI

    Directory of Open Access Journals (Sweden)

    Azizul Khakim

    2015-10-01

    Full Text Available ABSTRAK ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI. Bulk shielding merupakan fasilitas yang terintegrasi dengan reaktor Kartini yang berfungsi sebagai penyimpanan sementara bahan bakar bekas. Fasilitas ini merupakan fasilitas yang termasuk dalam struktur, sistem dan komponen (SSK yang penting bagi keselamatan. Salah satu fungsi keselamatan dari sistem penanganan dan penyimpanan bahan bakar adalah mencegah kecelakaan kekritisan yang tak terkendali dan membatasi naiknya temperatur bahan bakar. Analisis keselamatan paling kurang harus mencakup analisis keselamatan dari sisi neutronik dan termo hidrolik Bulk shielding. Analisis termo hidrolik ditujukan untuk memastikan perpindahan panas dan proses pendinginan bahan bakar bekas berjalan baik dan tidak terjadi akumulasi panas yang mengancam integritas bahan bakar. Code tervalidasi PARET/ANL digunakan untuk analisis pendinginan dengan mode konveksi alam. Hasil perhitungan menunjukkan bahwa mode pendinginan konvekasi alam cukup memadai dalam mendinginkan panas sisa tanpa mengakibatkan kenaikan temperatur bahan bakar yang signifikan. Kata kunci: Bulk shielding, bahan bakar bekas, konveksi alam, PARET.   ABSTRACT THERMAL HYDRAULIC SAFETY ANALYSIS OF BULK SHIELDING KARTINI REACTOR. Bulk shielding is an integrated facility to Kartini reactor which is used for temporary spent fuels storage. The facility is one of the structures, systems and components (SSCs important to safety. Among the safety functions of fuel handling and storage are to prevent any uncontrolable criticality accidents and to limit the fuel temperature increase. Safety analyses should, at least, cover neutronic and thermal hydraulic calculations of the bulk shielding. Thermal hydraulic analyses were intended to ensure that heat removal and the process of the spent fuels cooling takes place adequately and no heat accumulation that challenges the fuel integrity. Validated code, PARET/ANL was used for analysing the

  5. 77 FR 41363 - BASF Plant Science, LP; Availability of Petition for Determination of Nonregulated Status of...

    Science.gov (United States)

    2012-07-13

    ... Engineering Which Are Plant Pests or Which There Is Reason to Believe Are Plant Pests,'' regulate, among other... and products altered or produced through genetic engineering that are plant pests or that there is... field tests were conducted by BASF in Brazil, which allowed for evaluation in a natural agricultural...

  6. Isotopic composition of precipitation at the station Ljubljana (Reaktor, Slovenia – period 2007–2010

    Directory of Open Access Journals (Sweden)

    Polona Vreča

    2014-12-01

    Full Text Available The stable isotopic composition of hydrogen and oxygen (δ2H and δ18O and the tritium activity (A were monitored in monthly collected precipitation at Ljubljana (Reaktor during the period 2007–2010. Monthly and yearly isotope variations are discussed and compared with those observed over the period 1981–2006 and with the basic meteorological parameters for Ljubljana (Bežigrad and Ljubljana (Hrastje stations for the period 2007−2010. The mean values for δ2H and δ18O, weighted by precipitation amount at Ljubljana (Reaktor, are –59.4 ‰ and –8.71 ‰. The reduced major axis local meteoric water line (LMWLRMA is δ2H = (8.19 ± 0.22×δ18O + (11.52 ± 1.97, while the precipitation weighted least square regression results in LMWLPWLSR-Re δ2H = (7.94 ± 0.21×δ18O + (9.76 ± 1.93. The lack of significant difference in the LMWL slopes indicates a relatively homogeneous distribution of monthly precipitation as well as the small number of low-amount monthly precipitation events with low deuterium excess. The deuterium excess weighted mean value is 10.3 ‰ which indicates the prevailing influence of the Atlantic air masses. The temperature coefficient of δ18O is 0.30 ‰/°C. Tritium activity in monthly precipitation shows typical seasonal variations, with a weighted mean tritium activity in this period of 8.5 TU. No decrease of mean annual activity is observed.

  7. Developing a registry of workers involved in nanotechnology: BASF experiences.

    Science.gov (United States)

    David, Raymond M; Nasterlack, Michael; Engel, Stefan; Conner, Patrick R

    2011-06-01

    To assist BASF in the establishment of a registry of workers involved in nanotechnology. The initial step was a complete inventory of nanomaterials and sites of use. Guidance was developed to clarify which particulate nanomaterials were to be included in the survey. Site management was then contacted by the medical department to obtain a list of workers. The time line for collecting data ranged from several months to a year, depending on the information needed, and presented challenges based on the lack of global definition and labeling of nanomaterials. Less than 50 nanomaterials are used as raw materials in less than 10% of the sites globally. In North America, less than 5% of sites and 5% workers use nanomaterials. Further work is required to integrate the inventory, registry, and exposure assessments.

  8. Large Pilot Scale Testing of Linde/BASF Post-Combustion CO2 Capture Technology at the Abbott Coal-Fired Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, Kevin C. [University of Illinois, Champaign, IL (United States)

    2017-08-18

    The work summarized in this report is the first step towards a project that will re-train and create jobs for personnel in the coal industry and continue regional economic development to benefit regions impacted by previous downturns. The larger project is aimed at capturing ~300 tons/day (272 metric tonnes/day) CO2 at a 90% capture rate from existing coal- fired boilers at the Abbott Power Plant on the campus of University of Illinois (UI). It will employ the Linde-BASF novel amine-based advanced CO2 capture technology, which has already shown the potential to be cost-effective, energy efficient and compact at the 0.5-1.5 MWe pilot scales. The overall objective of the project is to design and install a scaled-up system of nominal 15 MWe size, integrate it with the Abbott Power Plant flue gas, steam and other utility systems, and demonstrate the viability of continuous operation under realistic conditions with high efficiency and capacity. The project will also begin to build a workforce that understands how to operate and maintain the capture plants by including students from regional community colleges and universities in the operation and evaluation of the capture system. This project will also lay the groundwork for follow-on projects that pilot utilization of the captured CO2 from coal-fired power plants. The net impact will be to demonstrate a replicable means to (1) use a standardized procedure to evaluate power plants for their ability to be retrofitted with a pilot capture unit; (2) design and construct reliable capture systems based on the Linde-BASF technology; (3) operate and maintain these systems; (4) implement training programs with local community colleges and universities to establish a workforce to operate and maintain the systems; and (5) prepare to evaluate at the large pilot scale level various methods to utilize the resulting captured CO2. Towards the larger project goal, the UI-led team, together

  9. RA Research reactor, Annual report 1970 - Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1970. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1970-12-15

    the pool. Refuelling was done three times by 'mixing' the irradiated fuel slugs with 5 to 6 fresh ones. Total exposure of the staff was increased due to activities during the shut-down period. Individual maximum exposure dose was not higher than 3.5 R. Cooperation with the French partner, concerned with the possibility of using 93% enriched fuel instead of the present low enriched, was continued. This would enable achievement of higher neutron flux, order of magnitude of 10{sup 14} n/cm{sup 2} sec. It is mentioned that there is doubt whether the plan for 1971 could be fulfilled for financial difficulties. [Serbo-Croat] Reaktor RA je u 1970. godini radio na nominalnoj snazi 160 dana i 40 dana na manjim snagama. Ukupni rad iznosio je 25968 MWh odnosno 3.87% vise od planiranog. Plan rada razlikovao se od prethodnih godina zbog slanja teske vode na rekoncentraciju u Francusku. Izotopski sastav teske vode je opao na 99.05% a posle rekoncentracije iznosi 99,96%. Odstupanje od plana rada u septembru mesecu bilo je izazvano kasnjenjem prispeca teske vode usled administrativnih teskoca i transporta. Pocetak kampanje odlozen je i zbog posledica ostecenja kosuljice jednog gorivnog elementa, sto se dogodilo odmah po pocetku rada pa je reaktor bio zaustavljen. U oktobru i novembru reaktor je radio 28 odnosno 25 dana respektivno sto je omogucilo da se nadoknadi izgubljeno vreme. Reaktor je koriscen za ozracivanja i eksperimente za 390 korisnika od cega 340 iz Instituta i 50 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Zakljucuje se da je reaktor radio uspesno prema planu rada. Kracih zastoja u radu bilo je samo zbog teskoca sa cevovodima tehnicke vode kao posledica klizanja zemljista. Reaktor je samo dva puta sigurnosno zaustavljan zbog neispravnosti opreme odnosno laznog signala elektronske aparature sistema upravljanja. Vreme dok reaktor nije radio iskorisceno je za inspekciju unutrasnjosti reaktorskog suda. Pomocu

  10. Pengaruh Laju Alir Inlet Reaktor MSL terhadap Reduksi BOD, COD, TSS, dan Minyak/Lemak Limbah Cair Industri Minyak Goreng

    Directory of Open Access Journals (Sweden)

    Salmariza Sy

    2017-06-01

    Full Text Available This research was conducted by treating edible oil industry wastewater used Multi Soil Layering (MSL method. The MSL reactor was built from a 200x120x200 cm concrete basin. Andisol soil was mixed with sawdust and fine charcoal at each ratio 5:1:1 based on dry weight as an impermeable layer. The flow rate variations were 250, 500, 1000, and 1500 L/m2.day. The observed pollutant parameters were BOD, COD, TSS, oil/fat, and pH. The results showed that MSL reactor was effective to decrease the pollutant content of edible oil industry wastewater. The reactor could reduce concentration of effluent parameters below standard except for oil/fat parameters at high flow rates. In the effluent was found BOD 0.66-14.22 mg/L, COD 5-69 mg/L, TSS 9-26 mg/L, and oil/fat 2-9 mg/L. The flow rate had an effect on reduction efficiency of BOD, COD, TSS, and oil/fat but did not effect pH as all flow rate could raise pH 6.37-6.95 became pH 6.99-7.24. The lower the flow rate the higher the reduction efficiency. The reduction efficiency at flow rates 250 and 1500 L/m2 days for BOD were 99% and 86%, COD were 96% and 71%, TSS were 88% and 77%, and oil/fat were 80% and 60%.ABSTRAK  Penelitian ini dilakukan dengan mengolah air limbah industri minyak goreng menggunakan metoda Multi Soil Layering (MSL. Reaktor MSL dibuat dari beton berbentuk bak ukuran 200x120x200 cm. Tanah andisol dicampur dengan serbuk gergaji dan arang halus pada rasio masing-masing 5:1:1 berdasarkan berat kering sebagai penyusun lapisan impermeable. Variasi laju alir yaitu 250, 500, 1000, dan 1500 L/m2.hari. Parameter pencemar yang dianalisis meliputi BOD, COD, TSS, minyak/lemak, dan pH. Hasil penelitian menunjukkan bahwa reaktor MSL sangat efektif untuk menurunkan kandungan zat pencemar limbah cair industri minyak goreng. Reaktor dapat mereduksi konsentrasi parameter outlet sampai dibawah baku mutu yang distandarkan kecuali untuk parameter miyak/lemak pada perlakuan laju alir tinggi. Pada effluen

  11. PEMBUATAN SERBUK U-6Zr DENGAN PENGKAYAAN URANIUM 19,75 % UNTUK BAHAN BAKAR REAKTOR RISET

    Directory of Open Access Journals (Sweden)

    Masrukan Masrukan

    2016-03-01

    Full Text Available ABSTRAK PEMBUATAN SERBUK PADUAN U-6Zr DENGAN PENGKAYAAN URANIUM 19,75 % UNTUK BAHAN BAKAR REAKTOR RISET. Telah dilakukan pembuatan serbuk paduan U-6Zr dengan pengkayaan 19,75 % untuk bahan bakar reaktor riset. Pembuatan bahan bakar U-6Zr ini dalam rangka mencari bahan bakar baru yang mempunyai densitas tinggi untuk mengganti bahan bakar yang sudah ada U3Si2-Al. Tujuan dari percobaan ini untuk mengetahui sifat-sifat serbuk paduan U- 6Zr yang diperoleh dari proses hydriding-dehydriding sebagai kandidat bahan bakar reaktor riset. Serbuk yang diperoleh dari proses hydriding-dehydriding dikenai pengujian, diantaranya pungujian komposisi kimia, densitas, kandungan hidrogen, fasa dan sifat termal. Hasil pengujian komposisi kimia menunjukkan beberapa unsur seperti Al, Ca, Cu, dan Ni melebihi batas yang diijinkan dimana masing-masing unsur terdapat sebesar 202,21 ppm; 214,05 ppm; 61,25 ppm dan 134,53 ppm. Pada pengujian diperolah densitas serbuk U-6Zr sebesar 13,58 g/cm3 dan pada pengujian kandungan hidrogen sisa diperoleh kandungan hidrogen sebesar 0,16 %. Untuk pengujian fasa, diperoleh fasa αU dan δU, sedangkan pada pengujian sifat termal yakni transformasi temperatur terdapat dua puncak yakni puncak pertama terjadi pada temperatur 274 hingga 311 oC dan puncak kedua terjadi pada temperatur 493 hingga 527oC. Puncak pertama terjadi reaksi endotermik dengan menyerap panas sebesar ∆H = 6,23 cal/g tetapi tidak terbentuk fasa baru, sedangkan puncak kedua terjadi reaksi eksotermik dengan mengeluarkan panas sebesar ∆H = -9.34 cal/g dan terbentuk fasa αZr. Sementara itu, dari pengujian kapasitas panas pada temperatur 34 hingga 75 oC, terjadinya penurunan nilai kapasitas panas yang disertai dengan penyerapan panas. Pada temperatur yang lebih tinggi hingga temperatur 437oC nilai kapasitas panas menjadi lebih kecil disertai pengeluaran panas. Reaksi termokimia antara Zr dengan hidrogen sisa menunjukkan terbentuknya fasa αZr yang diindikasikan oleh reaksi

  12. BASF and acetylene. 70 years of reppe chemistry - long-standing reliability and promising future - and now, the only natural gas based clean technology for acetylene production

    Energy Technology Data Exchange (ETDEWEB)

    Vicari, M. [BASF SE, Ludwigshafen (Germany)

    2013-11-01

    Acetylene is still an attractive intermediate synthesis component because carbon in methane from natural gas comes at a lower price than carbon in naphtha from crude oil or coal. Acetylene can be understood as a product of C-C coupling and functionalization. Beginning in the 1950s, BASF developed the partial oxidation (Pox) process, in addition to the electric arc process dating from the 1930s and the submerged flame process. The originally developed Pox process came along with severe emissions of hydrocarbons to the environment. Nowadays it is extremely important to have a clean, environmentally friendly technology. So in the 1990s a closed water-quench process was developed and built in the United States. The presentation focuses on the ways of making acetylene, the use of acetylene and BASF's closed water-quench process based on natural gas. This process will be presented including some important safety aspects. The process is available for licensing. (orig.)

  13. Disain Sistem Pemantauan Lingkungan Untuk Evaluasi Lepasan Radionuklida dari Subsistem pada Kecelakaan Reaktor Daya PWR

    Directory of Open Access Journals (Sweden)

    Sri Kuntjoro

    2013-03-01

    Full Text Available PLTN. (Pembangkit Listrik Tenaga Nuklir sebagai sumber energi baru dipilih sebagai alternatif, karena memiliki berbagai kelebihan yaitu ramah lingkungan, pasokan bahan bakar yang tidak bergantung musim, serta harganya yang dapat bersaing dengan pembangkit listrik yang lain. Namun demikian, adanya keraguan sebagian masyarakat tentang keselamatan radiasi PLTN, maka pemerintah harus bisa meyakinkan tentang operasi PLTN yang aman dan selamat. Penelitian tentang disain sistem pemantauan lingkungan untuk evaluasi lepasan radionuklida dari subsistem reaktor dan lingkungan akibat terjadinya kecelakaan pada reaktor daya telah dilakukan. Penelitian dilakukan dengan melakukan perhitungan sebaran radionuklida ke subsistem dan lingkungan serta membuat sistim monitoring radiasi di lingkungan. Sistem monitoring lingkungan terdiri dari system pencacah radiasi, sistem peringatan dini, sistem pengukuran meteorologi, sistem GPS dan system GIS. Sistem pencacah radiasi digunakan untuk mencatat data radiasi, sistem pengukuran meteorologi digunakan untuk mencatat data arah dan kecepatan angin, sedangkan sistem GPS digunakan untuk menentukan data posisi pengukuran. Data tersebut kemudian dikirimkan ke system akuisisi data untuk ditransmisikan ke pusat kendali. Pengumpulan dan pengiriman data dilakukan melalui SMS menggunakan perangkat modem yang ditempatkan di ruang kendali. Ruang kendali menerima data dari berbagai tempat pengukuran. Dalam hal ini ruang kendali memiliki fungsi sebagai SMS gateway. Sistem ini dapat memvisualisasi untuk lokasi pengukuran yang berbeda. Selanjutnya, data posisi dan data radiasi diintegrasikan dengan peta digital. Integrasi sistem tersebut kemudian divisualisasikan dalam personal komputer. Untuk posisi pengukuran terlihat langsung di peta dan untuk data radiasi ditampilkan di monitor dengan tanda lingkaran merah atau hijau yang digunakan sebagai pemonitor batas aman radiasi. Bila tanda lingkaran berwarna merah maka akan menyalakan alarm di

  14. Ford/BASF/UM Activities in Support of the Hydrogen Storage Engineering Center of Excellence

    Energy Technology Data Exchange (ETDEWEB)

    Veenstra, Mike [Ford Motor Company, Dearborn, MI (United States); Purewal, Justin [Ford Motor Company, Dearborn, MI (United States); Xu, Chunchuan [Ford Motor Company, Dearborn, MI (United States); Yang, Jun [Ford Motor Company, Dearborn, MI (United States); Blaser, Rachel [Ford Motor Company, Dearborn, MI (United States); Sudik, Andrea [Ford Motor Company, Dearborn, MI (United States); Siegel, Don [Univ. of Michigan, Ann Arbor, MI (United States); Ming, Yang [Univ. of Michigan, Ann Arbor, MI (United States); Liu, Dong' an [Univ. of Michigan, Ann Arbor, MI (United States); Chi, Hang [Univ. of Michigan, Ann Arbor, MI (United States); Gaab, Manuela [BASF SE, Ludwigshafen (Germany); Arnold, Lena [BASF SE, Ludwigshafen (Germany); Muller, Ulrich [BASF SE, Ludwigshafen (Germany)

    2015-06-30

    Widespread adoption of hydrogen as a vehicular fuel depends critically on the development of low-cost, on-board hydrogen storage technologies capable of achieving high energy densities and fast kinetics for hydrogen uptake and release. As present-day technologies -- which rely on physical storage methods such as compressed hydrogen -- are incapable of attaining established Department of Energy (DOE) targets, development of materials-based approaches for storing hydrogen have garnered increasing attention. Material-based storage technologies have potential to store hydrogen beyond twice the density of liquid hydrogen. To hasten development of these ‘hydride’ materials, the DOE previously established three centers of excellence for materials storage R&D associated with the key classes of materials: metal hydrides, chemical hydrogen, and adsorbents. While these centers made progress in identifying new storage materials, the challenges associated with the engineering of the system around a candidate storage material are in need of further advancement. In 2009 the DOE established the Hydrogen Storage Engineering Center of Excellence with the objective of developing innovative engineering concepts for materials-based hydrogen storage systems. As a partner in the Hydrogen Storage Engineering Center of Excellence, the Ford-UM-BASF team conducted a multi-faceted research program that addresses key engineering challenges associated with the development of materials-based hydrogen storage systems. First, we developed a novel framework that allowed for a material-based hydrogen storage system to be modeled and operated within a virtual fuel cell vehicle. This effort resulted in the ability to assess dynamic operating parameters and interactions between the storage system and fuel cell power plant, including the evaluation of performance throughout various drive cycles. Second, we engaged in cost modeling of various incarnations of the storage systems. This analysis

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

    Directory of Open Access Journals (Sweden)

    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

  16. VERIFIKASI PAKET PROGRAM MVP-II DAN SRAC2006 PADA KASUS TERAS REAKTOR VERA BENCHMARK.

    Directory of Open Access Journals (Sweden)

    Jati Susilo

    2015-03-01

    Full Text Available Dalam penelitian ini dilakukan verifikasi perhitungan benchmark VERA pada kasus Zero Power Physical Test (ZPPT teras reaktor Watts Bar 1. Reaktor tersebut merupakan jenis PWR kelas 1000 MWe yang didesain oleh Westinghouse, tersusun dari 193 perangkat bahan bakar 17×17 dengan 3 jenis pengkayaan UO2 yaitu 2,1wt%, 2,619wt% dan 3,1wt%. Perhitungan nilai k-eff dan distribusi faktor daya dilakukan pada siklus operasi pertama teras dengan kondisi beginning of cycle (BOC dan hot zero power (HZP. Posisi batang kendali dibedakan menjadi uncontrolled (semua batang kendali berada di luar teras, dan controlled (batang kendali Bank D didalam teras. Paket program komputer yang digunakan dalam perhitungan adalah MVP-II dan SRAC2006 modul CITATION dengan data pustaka tampang lintang ENDF/B-VII.0. Hasil perhitungan menunjukkan bahwa perbedaan nilai k-eff teras pada kondisi controlled dan uncontrolled antara referensi dengan MVP-II (-0,07% dan -0,014% dan SRAC2006 (0,92% dan 0,99% sangat kecil atau masih dibawah 1%. Perbedaan faktor daya maksimum teras pada kondisi controlled dan uncontrolled dengan referensi dengan MVP-II adalah 0,38% dan 1,53%, sedangkan dengan SRAC2006 adalah 1,13% dan -2,45%. Dapat dikatakan bahwa kedua paket program komputer menunjukkan hasil perhitungan yang sesuai dengan nilai referensi. Dalam hal penentuan kekritisan teras, maka hasil perhitungan MVP-II lebih konservatif dibandingkan dengan SRAC2006. Kata kunci : MVP-II, SRAC2006, PWR, VERA   In this research, verification calculation for VERA core physics benchmark on the Zero Power Physical Test (ZPPT of the nuclear reactor Watts Bar 1. The reactor is a 1000 MWe class of PWR designed by Westinghouse, arranged from 193 unit of 17×17 fuel assembly consisting 3 type enrichment of UO2 that are 2.1wt%, 2.619wt% and 3.1wt%. Core power factor distribution and k-eff calculation has been done for the first cycle operation of the core at beginning of cycle (BOC and hot zero power (HZP. In this

  17. RA Research reactor, Annual report 1971; Istrazivacki nuklearni reaktor RA - Izvestaj za 1971. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1971-12-15

    effects. In the introduction of this report it has been emphasised that the decision makers should have in mind the negative effects of low budget on the reactor safe and reliable operation. For the sake of reactor, decision about the future operation and financing should be done as soon as possible, either to cease operation or continue with adequate financial support. [Serbo-Croat] Reaktor RA je u 1971. godini radio na nominalnoj snazi 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31606 MWh odnosno 5,3% vise od planiranog, sto je najvisa vrednost od kako je reaktor pusten u rad. Reaktor je koriscen za ozracivanja i eksperimente za 425 korisnika od cega 370 iz Instituta i 55 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Odstupanja od plana, odnosno veceg ostvarenog rada bilo je u junu i decembru usled posebnih zahteva korisnika. Ukupni broj prekida rada bio je manji od svih prethodnih godina, uglavnom zbog manjeg broja nestanka napona u vreme rada reaktora. U toku godine bilo je samo jedno sigurnosno zaustavljanje, ciji je uzrok bila pojava laznog signala opreme za zastitu reaktora. Nijednog duzeg prekida rada nije bilo zbog neispravnosti opreme. Kracih prekida bilo je usled kidanja spojki na potisnom cevovodu tehnicke vode, sto je bilo izazvano klizanjem zemljista u podrucju crpne stanice na Dunavu. Ukupna doza ozracivanja ljudstva bila je manja nego prethodnih godina. Nije bilo ni jednog akcidenta niti slucaja koji bi se mogao nazvati akcidentom. Dekontaminirano je znatno manje povrsina nego ranijih godina. Zakljuceno je da je uspesan rad reaktora u 1971. godini rezultat valjanog rada u prethodnim godinama. Medjutim usled jos nedefinisane politike u pogledu buduceg rada, odnosno neizvesnosti u vezi finansiranja, neki poslovi su obustavljeni. Tu spada proucavanje mogucnosti prelaska na koriscenje visokoobogacenog goriva sto bi povecalo korisni neutronski fluks i ucinilo reakor konkurentnim za

  18. RA Research reactor, Annual report 1969; Istrazivacki nuklearni reaktor RA - Izvestaj za 1969. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1969-12-15

    years of operation as well as purification of heavy water. [Serbo-Croat] Reaktor RA je u 1969. godini radio na nominalnoj snazi 200 dana i 15 dana na manjim snagama. Ukupni rad iznosio je 31131 MWh odnosno 3.77% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimenta prema zahtevima 463 korisnika iz Instituta i 63 izvan Instituta. Ovaj izvestak sadrzi detaljne podatke o snazi na kojoj je reaktor radio tokom 1969. godine i o uradjenim eksperimentima. Zakljuceno je da je reaktor RA uspesno radio prema planu rada. Da nije bilo problema sa napajanjem elektricnom energijom tokom poslednja tri meseca i niskog vodostaja Dunava u septembru i oktobru protekle godine bila bi to najuspesnija godina od pustanja reaktora u pogon. Broj sigurnosnih zaustavljanja nije bio veci u odnosu na prethodne dve godine i pored poteskoca u poslednjem kvartalu. Osoblje je bilo izlozeno povecanim dozama zracenja usled tri incidenta. Jedan je bio raspadanje kenera sa srebrom (zbog duzeg stajanja u aktivnoj zoni), sto je uzrokovalo kontaminaciju radne platforme, tako da je fon porastao za 10 do 100 puta od normalnohg Druga dva slucaja su bila otkazivanje uredjaja za mesanje goriva u tehnoloskim kanalima. Zamena goriva je radjena cetiri puta u toku godine, utroseno je 499 svezih gorivnih elemenata. Primenjena je metoda mesanja svezih gorivnih elemenata sa koriscenim gorivnim elementima u gorivnom kanalu. Dekontaminacija povrsina bila je na nivou prethodnih godina i pored problema sa srebrom. Kako su sa reaktora tokom godine otisla dva saradnika sa visokom spremom broj ljudi je opao na neophodan minimum za pogon i odrzavanje reaktora. Navrsavajuci u ovoj godini deset godina rada moze se reci da su rad i stanje opreme na tehnicki solidnom nivou. Kako bi se posle deset godina rada izvrsila kontrola vaznih komponenti reaktora i obavila rekoncentracija teske vode, za 1970. godinu je planirano da se proizvodnja smanji na 25000 MWh, a baziran je na istim principima kao i planovi za prethodne

  19. PERFORMA OKSIDASI METAN PADA REAKTOR KONTINYU DENGAN PENINGKATAN KETEBALAN LAPISAN BIOCOVER LANDFILL

    Directory of Open Access Journals (Sweden)

    Opy Kurniasari

    2013-11-01

    methane through the form of methanol metabolite. ABSTRAKPenanganan sampah kota di Indonesia pada umumnya dilakukan pada tempat pemrosesan akhir sampah (TPA, yang sebagian besar dilakukan dengan cara pengurugan (landfilling yang cenderung bersifat anaerob (tidak ada oksigen. Cara pengurugan ini biasanya dioperasikan lapis perlapis sehingga memungkinkan terjadinya proses anaerob. Pada kondisi ini dipastikan biogas, yaitu gas metana (CH4 dan CO2, akan muncul. Metana adalah gas rumah kaca dengan potensi pemanasan global lebih besar dari CO2, dan dapat mengabsorpsi radiasi infra merah 23 kali lebih efisien dari CO2 pada periode lebih dari 100 tahun. Salah satu cara yang dapat dilakukan untuk mengurangi gas metana dari landfill yang lepas ke alam adalah dengan mengoksidasinya dengan memanfaatkan material penutup landfill (biocover sebagai media mikroorganisma pengoksidasi metana. Aplikasi kompos sebagai material penutup landfill merupakan pendekatan dengan biaya rendah untuk mereduksi emisi gas dari landfill sehingga cocok untuk negara berkembang. Biocover yang digunakan pada penelitian ini adalah kompos landfill mining, yaitu kompos yang terdegradasi secara alami di landfill. Tujuan penelitian ini adalah mengevaluasi kemampuan biocover kompos landfill mining dalam mengoksidasi metana pada ketebalan lapisan tertentu dengan kondisi aliran kontinyu. Tiga buah reaktor kolom yang digunakan terbuat dari flexy glass berukuran tinggi 70 cm dan diameter 15 cm. Gas metana dialirkan dari bawah reaktor secara kontinyu dengan laju alir 5 ml/menit. Kolom diisi dengan biocover kompos landfill mining dengan ketebalan lapisan 5, 25, 35 dan 60 cm. Hasil percobaan menunjukkan bahwa semakin tebal lapisan biocover, semakin tinggi efisiensi oksidasi metana. Efisiensi oksidasi yang diperoleh pada setiap ketebalan lapisan 15, 25, 35 dan 60 cm adalah masing-masing 56,43%, 63,69%, 74,58% dan 80,03%, dengan laju oksidasi 0,287 mol m-2 d-1 dan fraksi oksidasi 97%. Hasil oksidasi yang diperoleh tersebut

  20. PENGEMBANGAN MODEL UNTUK SIMULASI KESELAMATAN REAKTOR PWR 1000 MWe GENERASI III+ MENGGUNAKAN PROGRAM KOMPUTER RELAP5

    Directory of Open Access Journals (Sweden)

    Andi Sofrany Ekariansyah

    2015-04-01

    Full Text Available Reaktor daya PWR AP1000 yang didesain oleh Westinghouse adalah reaktor Generasi III+ pertama yang telah menerima persetujuan desain dari U.S. Nuclear Regulatory Commission (NRC. Saat ini utilitas China telah memulai pembangunan beberapa unit AP1000 di dua tapak terpilih untuk rencana operasi pada 2013-2015. AP1000 sebagai desain PWR berdasarkan teknologi teruji dari desain PWR lainnya yang dibuat oleh Westinghouse dengan penguatan pada sistem keselamatan pasif dengan demikian dapat dipertimbangkan untuk dibangun di Indonesia bila mengacu pada persyaratan pada PP 43/2006 mengenai Perijinan Reaktor Nuklir. Namun demikian, desain tersebut perlu diverifikasi oleh Technical Support Organization (TSO independen sebelum dapat dibangun di Indonesia. Verifikasi dapat dilakukan menggunakan paket program RELAP5 dalam bentuk analisis kecelakaan. Selama ini analisis kecelakaan PLTN dilakukan untuk tipe PWR 1000 MWe dari generasi II atau tipe konvensional. Mengingat saat ini referensi yang menggambarkan teknologi AP1000 yang menyertakan teknologi keselamatan pasif sudah tersedia maka dilakukan kegiatan pemodelan yang nantinya dapat digunakan untuk melakukan analisis kecelakaan. Metode pengembangan model mengacu pada pedoman IAEA yang terdiri dari pengumpulan data instalasi, pengembangan engineering data dan penyusunan input deck, verifikasi dan validasi data input. Model yang berhasil dikembangkan secara umum telah mewakili sistem AP1000 secara keseluruhan dan dianggap sebagai model dasar. Model tersebut telah diverifikasi dan divalidasi dengan data desain yang terdapat pada referensi dimana respon parameter termohidraulika menunjukkan perbedaan hasil ± 3% selain untuk parameter penurunan tekanan teras yang lebih rendah 13%. Sebagai model dasar, input deck yang diperoleh dapat dikembangkan lebih lanjut dengan mengintegrasikan pemodelan sistem keselamatan, sistem proteksi, dan sistem kendali yang spesifik AP1000 untuk keperluan simulasi keselamatan yang lebih

  1. RA Research reactor, Annual report 1968 - Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1968. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-12-15

    During 1968, the RA Reactor was operated at nominal power of 6.5 MW for 190 days, and during 50 days at lower power levels. Total production amounted to 31051 MWh which is 3.5% higher than planned. reactor was used for irradiation and experiments according to the demand of 600 users, of which 517 from the Institute and 83 externals users. This report contains detailed data about reactor power and experiments performed in 1968. It is concluded that the reactor operation was more successful than during previous years. There was only one longer interruption which lasted 27 hours because of the power cut on the cable for the pump station on Danube. Number of safety shutdowns were at the same level as during last year. The only significant incident in 1968 was air contamination with the radioactive argon in the reactor hall. The reactor operation was not interrupted although the hall was evacuated for two hours. The was no significant exposure of the staff. In April and September the integral dosed were higher than during other months because of the accident during refueling (mixing the slugs with irradiated and fresh fuel). There was no significant surface contamination, i.e. the decontaminated surface were negligible. Due to 'mixing' refueling scheme. [Serbo-Croat] Reaktor RA je u 1968. godini radio na nominalnoj snazi od 6,5 MW 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31051 MWh odnosno 3,5% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 600 korisnika od cega 517 iz Instituta i 83 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Zakljucuje se da je reaktor radio uspesnije nego prethodnih godina. U toku 1968. godine samo je jedan duzi prekid u radu od 27 casova izazvan zbog proboja kablovske glave na odvodu za pumpnu stanicu na Dunavu. Sigurnosna zaustavljanja bila su na proslogodisnjem nivou. Jedini znacajniji incident u 1968. godini, bio je kontaminacija vazduha

  2. Research nuclear reactor RA - Annual Report 1996; Istrazivacki nuklearni reaktor RA - Izvestaj za 1996. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U toku 1996. godine nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-12-15

    dozvoljava probni rad reaktora uz ogranicenje snage do 2 MW dok se ne izvrsi rekonstrukcija ventilacionog sistema i ne izgradi sistem za prinudno hladjenje jezgra u slucaju udesa. Realizacija programa probnog rada zapoceta je 15. septembra 1981. godine uz postupno povecanje snage tako da je u novembru i decembru reaktor radio na snazi od 2 MW u trajanju od 15 dana. Na reaktoru je u toku 1981. godine ostvaren rad od ukupno 1698 MWh. To je omogucilo da se reaktor u poslednja dva meseca koristi i za proizvodnju radioizotopa. Kontrola i odrzavanje celokupne opreme, kao i remontni radovi izvrsavani su redovno i efikasno u granicama koje su diktirane raspolozivoscu repromaterijalom i rezervnim delovima. Najvecu poteskocu pricinjava odrzavanje instrumentacije. Reaktor je u toku 1981. godine radio potpuno bezbedno i sigurno kako po osoblje tako i po ostalo ljudstvo u zgradi reaktora i van nje. Nije se dogodio ni jedan akcident vezan za rad reaktora. Probni rad ce biti nastavljen i u 1982. godini a dosadasnji rezultati pokazuju da ce ceo program biti uspesno realizovan.

  4. Operational report, Advantages of gradual introducing of highly enriched fuel into the RA reactor core from economic aspect and users needs; Radni izvestaj, Prednost postupka parcijalnog uvodjenja visokoobogacenog goriva u reaktor RA sa aspekta ekonomicnosti i potreba korisnika

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-10-14

    The possibility of increasing the neutron flux in the RA reactor was considered for a number of years. The possibilities of reactor reconstruction are not realistic and they should be disregarded. The possibility that remains is to achieve higher neutron flux by improving the fueling scheme and above all by introducing highly enriched fuel into the reactor core. Decision to purchase highly enriched fuel was quicker due to the fact that the 2% enriched uranium fuel is not fabricated any more. There are two procedures for exchanging the fuel in the reactor core: a) removal of partially spent 2% enriched fuel and formation of the core with fresh highly enriched fuel; b) gradually introducing the new fuel into the existing RA reactor core according to a special transfer regime. This report includes some comparative analyses of these two procedures from both economic point of view and the needs of users, as well as some technical conditions. These results are in favour of gradual introducing of new fuel into the reactor core. relevant direct savings amount to 3 000 000 dinars. Some of the most important advantages cannot be estimated in this way. This report does not cover the safety analyses results which are presented in a series of other papers. [Serbo-Croat] Vec vise godina razmatra se mogucnost za povecanje neutronskog fluksa u reaktoru RA. Mogucnosti za rekonstrukciju reaktora RA u tom smislu su minimalne i realno ih treba odbaciti. Prema tome preostaje da se povecanje neutronskog fluksa postigne usavrsavanjem seme izmene goriva, a pre svega uvodjenjem goriva sa visokim stepenom obogacenja u reaktor RA. Donosenje odluke o nabavci visokoobogacenog goriva i njegovom uvodjenju u reaktor ubrzano je i cinjenicom da se staro 2% obogaceno uransko gorivo vise ne proizvodi. Postoje dva postupka za prevodjenje reaktora na ovo gorivo: a) Uklanjanjem poluistrosenog 2% obogacenog goriva iz reaktora i formiranjem jezgra iskljucivo od svezeg visokoobogacenog goriva, b

  5. Radiation catalytical effects in the pre-irradiated and thermally treated catalyst BASF K-3-10

    International Nuclear Information System (INIS)

    Motl, A.

    1987-01-01

    The effects of different heat treatment methods on radiation catalysis, induced by pre-irradiation of the BASF K-3-10 catalyst by γ- or β-radiation or by fast neutrons were investigated. It was found that calcination of the irradiated non-reduced catalyst resulted in a strong decrease in or even a total disappearance of the final radiation catalytical effects; however, at the same time the catalytical activity of the unirradiated catalyst was found to increase. The calcination of the catalyst in a nitrogen atmosphere after reduction also led to a substantial decrease in the resulting positive radiation catalytical effects and the exceedance of a certain calcination temperature also resulted in a decrease in the unirradiated catalyst activity. It could be concluded that calcination in nitrogen of the reduced irradiated samples decreased the radiation catalytical effects to a lesser degree than the calcination in the air of the non-reduced irradiated samples. In both cases, a different thermal stability of effects induced by different types of ionizing radiation was observed and it was found that it increased in the sequence beta radiation - gamma radiation - fast neutrons. The investigation of the γ radiation dose dependence of the radiation catalytical effect on the catalyst calcined before irradiation in the presence of air showed that the final radiation catalytical effects were lower than those observed in case of similarly irradiated but non-calcined samples. The dose dependence of the effect had the same character in both cases. (author). 3 tabs., 8 refs

  6. FRACTURE MECHANICS UNCERTAINTY ANALYSIS IN THE RELIABILITY ASSESSMENT OF THE REACTOR PRESSURE VESSEL: (2D SUBJECTED TO INTERNAL PRESSURE

    Directory of Open Access Journals (Sweden)

    Entin Hartini

    2016-06-01

    BEJANA TEKAN REAKTOR: 2D DENGAN BEBAN INTERNAL PRESSURE. Bejana tekan reaktor (RPV merupakan pressure boundary dalam reaktor tipe PWR yang berfungsi untuk mengungkung material radioaktif  yang dihasilkan pada proses reaksi berantai. Maka dari itu integritas bejana tekan reaktor harus senantiasa terjamin baik reaktor dalam keadaan operasi normal, maupun kecelakaan. Dalam melakukan analisis integritas RPV, khususnya yang berkaitan dengan pecahnya bejana tekan reaktor akibat adanya retak dilakukan analisis secara fracture mechanics. Adanya ketidakpastian input seperti sifat mekanik bahan, lingkungan fisik, dan input pada data, maka dalam melakukan analisis keandalan tidak hanya dilakukan secara deterministik saja. Tujuan dari penelitian ini adalah melakukan analisis ketidakpastian input pada perhitungan fracture mechanik pada evaluasi keandalan bejana tekan reaktor PWR. Pendekatan untuk karakter random dari kuantitas input menggunakan  teori probabilistik. Analisis fracture mechanics dilakukan berdasarkan metode elemen hingga (FEM menggunakan perangkat lunak MSC MARC. Analisis ketidakpastian input dilakukan berdasarkan probability density function dengan Latin Hypercube Sampling (LHS menggunakan python script. Output dari MSC MARC adalah nilai J-integral untuk mendapatkan nilai stress intensity factor pada evaluasi keandalan bejana tekan reactor 2D. Dari hasil perhitungan dapat disimpulkan bahwa SIF probabilistik lebih dulu mencapai nilai batas fracture tougness  dibanding  SIF deterministik. SIF yang dihasilkan dengan metode probabilistik adalah 105,240 MPa m0,5. Sedangkan SIF metode deterministik adalah 100,876 MPa m0,5. Kata kunci: Analisis ketidakpastian, fracture mechanics, LHS, FEM, bejana tekan reaktor

  7. Research nuclear reactor RA - Annual Report 1991; Istrazivacki nuklearni reaktor RA - Izvestaj za 1991. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-01-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Construction of some support elements is almost finished by the local staff. The Institute has undertaken this activity in order to speed up the ending of the project. If all the planned instrumentation would not arrive until the end of March 1992, it would not be possible to start the RA reactor testing operation in the first part of 1993, as previously planned. In 1991, 53 staff members took part in the activities during 1991, which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1991. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci

  8. Research nuclear reactor RA - Annual Report 1994; Istrazivacki nuklearni reaktor RA - Izvestaj za 1994. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-01

    Activities related to revitalisation of the RA reactor stared in 1986, were continued in 1991. A number of interventions on the reactor components were finished that are supposed to enable continuous and reliable operation. The last, and at the same time largest action, related to exchange of complete reactor instrumentation is underway, but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Activities related to improvement of Russian project were continued in 1994. Control and maintenance of the reactor components was done regularly and efficiently. Extensive repair of the secondary coolant loop is almost finished and will be completed in the first part of 1995 according to existing legal procedures and IAEA recommendations. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. Research reactor RA Annual report for year 1991 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U 1994. godini nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1983-12-15

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

  10. RA Research reactor, Annual report 1973; Istrazivacki nuklearni reaktor RA - Izvestaj za 1973. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1973-12-15

    During 1973, RA reactor was operated at nominal power for 4687 hours and 54 hours at lower power levels. The total production was 30504 MWh which is 1.6% higher than planned. Practically there was no discrepancies from the plan, since the action plan was corrected at the beginning of this year caused by the demand of changing the schedule for refuelling for the purpose of 'power excursion' experiment. The reactor was used for irradiation and experiments according to the demand of 336 users. This report contains detailed data about reactor power and experiments performed in 1973. Total number safety shutdowns was 12, of which 7 were caused by power cuts. Three shutdowns caused by failures of the equipment were caused by failures of new electronic tubes. Two shutdowns were caused by the operators. There have been three shorter interruptions announced power cuts. Total personnel exposure dose was lower than during previous years. There were no accidents during this year. Decontamination of surfaces was less than during previous years. Practically there was no surface contamination, and the quantity of collected radioactive waste was lower than previously. There were no liquid radioactive effluents. It was concluded that the successful operation in 1973 has a special significance taking into account the financial crisis. There still remains a number of unsolved problems related to: completing the inventory of spare parts, exchange of some elements of the equipment, exchange of instrumentation, and purchase of the highly enriched fuel. [Serbo-Croat] Reaktor RA je u 1973. godini radio na nominalnoj snazi 4687 sati i 54 sata na manjim snagama. Ukupni rad iznosio je 30504 MWh odnosno 1,6% vise od planiranog. Prakticno nije bilo odstupanja od plana rada koji je pocetkom godine korigovan zbog promene planiranih izmena goriva usled izvodjenja eksperimenta 'ekskurzije snage'. Reaktor je koriscen za ozracivanja i eksperimente za 336 korisnika. Ovaj izvestaj sadrzi detaljne

  11. RA Research reactor, Annual report 1988; Istrazivacki nuklearni reaktor RA - Izvestaj za 1988. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  12. Research nuclear reactor RA - Annual Report 1989; Istrazivacki nuklearni reaktor RA - Izvestaj za 1989. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  13. Research nuclear reactor RA - Annual Report 1997; Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Reaktor RA nije u pogonu od 1984, aktivnosti na revitalizaciji, rekostrukciji i modernizaciji reaktorski sistema zapocete su 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Do septembra 1991. godine isporuceno svega 80% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju usled sankcija uvedenih od strane organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane safeguard inspektora MAAE obavljana

  14. 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

  15. A pulsed fast reactor; Un reacteur pulse a neutrons rapides; Impul'snyj reaktor na bystrykh nejtronakh; Reactor rapido pulsado

    Energy Technology Data Exchange (ETDEWEB)

    Blokhin, G. E.; Blokhintsev, D. I.; Blyumkina, Yu. A.; Bondarenko, I. I.; Deryagin, B. N.; Zajmovskij, A. S.; Zinov' ev, V. P.; Kazachkovskij, O. D.; Krasnoyarov, N. V.; Lejpunskij, A. I.; Malykh, V. A.; Nazarov, P. M.; Nikolaev, S. K.; Stavisskij, Yu. Ya.; Ukraintsev, F. I.; Frank, I. M.; Shapiro, F. Ji.; Yazvitskij, Yu. S. [Akademiya Nauk, Moscow, SSSR (Russian Federation)

    1962-03-15

    los impulsos de potencia. Asimismo, se efectuaron mediciones del periodo de los neutrones instantaneos, de la fraccion efectiva de neutrones retardados y de los coeficientes de variacion de la reactividad en funcion de la temperatura. (author) [Russian] Impul'snyj reaktor na bystrykh nejtronakh (IBR) rabotaet na nominal'noj moshchnosti v Obedinennom institute yadernykh issledovanij s dekabrya 1960 goda. Reaktor ispol'zuetsya v kachestve impul'snogo istochnika nejtronov dlya fizicheskikh ehksperimentov, provodimykh metodom vremeni proleta. Provodyatsya izmereniya polnogo secheniya, secheniya zakhvata dlya promezhutochnykh nejtronov, issledo- vaniya vzaimodejstviya medlennykh nejtronov s tverdym telom i s zhidkost'yu, izmereniya spektrov nejtronov, ustanavlivayushchikhs ya v. razlichnykh sredakh. V doklade opisany osnovy konstruktsii reaktora i rezul'taty ego issledovanij. Osnovnoj rezhim raboty reaktora-rezhim periodicheskikh impul'sov. Impul'sy moshchnosti voznikayut pri bystrom peremeshchenii podvizhnoj chasti aktivnoj zony reaktora cherez ego nepodvizhnuyu zonu. Podvizhnaya chast' aktivnoj zony zakreplena vo vrashchayushchemsya diske i dvizhetsya so skorost'yu-230 m/sek. Chastota impul'sov moshchnosti mozhet izmenyat'sya s pomoshch'yu vspomogatel'noj podvizhnoj zony v diapazone 2,3-88 im/sek. Srednyaya moshchnost' reaktora - 1 kvt. Polushirina impul'sa moshchnosti - 36 mksek. Reaktor snabzhen sistemoj upravleniya i zashchity, obespechivayushchej avtomaticheskoe podderzhanie srednej moshchnosti reaktora i ego bystruyu ostanovku v sluchae narusheniya rezhima. Reaktor snabzhen sistemoj vakuumirovanny kh nektronovodov, ispol'zuemykh v ehksperimentakh po vremeni proleta. Glavnyj nejtronovod imeet dlinu 1000 m. V protsesse puska i fizicheskikh issledovanij reaktora izuchalos' vliyanie peremeshcheniya organov regulirovaniya i podvizhnykh chastej aktivnoj zony na reaktivnost', izmeryalas' dlitel'nost' impul'sa pri razlichnykh rezhimakh raboty reaktora, izuchalis

  16. Slipstream pilot-scale demonstration of a novel amine-based post-combustion technology for carbon dioxide capture from coal-fired power plant flue gas

    Energy Technology Data Exchange (ETDEWEB)

    Krishnamurthy, Krish R. [Linde LLC, Murray Hill, NJ (United States)

    2017-02-03

    Post-combustion CO2 capture (PCC) technology offers flexibility to treat the flue gas from both existing and new coal-fired power plants and can be applied to treat all or a portion of the flue gas. Solvent-based technologies are today the leading option for PCC from commercial coal-fired power plants as they have been applied in large-scale in other applications. Linde and BASF have been working together to develop and further improve a PCC process incorporating BASF’s novel aqueous amine-based solvent technology. This technology offers significant benefits compared to other solvent-based processes as it aims to reduce the regeneration energy requirements using novel solvents that are very stable under the coal-fired power plant feed gas conditions. BASF has developed the desired solvent based on the evaluation of a large number of candidates. In addition, long-term small pilot-scale testing of the BASF solvent has been performed on a lignite-fired flue gas. In coordination with BASF, Linde has evaluated a number of options for capital cost reduction in large engineered systems for solvent-based PCC technology. This report provides a summary of the work performed and results from a project supported by the US DOE (DE-FE0007453) for the pilot-scale demonstration of a Linde-BASF PCC technology using coal-fired power plant flue gas at a 1-1.5 MWe scale in Wilsonville, AL at the National Carbon Capture Center (NCCC). Following a project kick-off meeting in November 2011 and the conclusion of pilot plant design and engineering in February 2013, mechanical completion of the pilot plant was achieved in July 2014, and final commissioning activities were completed to enable start-up of operations in January 2015. Parametric tests were performed from January to December 2015 to determine optimal test conditions and evaluate process performance over a variety of operation parameters. A long-duration 1500-hour continuous test campaign was performed from May to

  17. RA Research nuclear reactor - Annual report 1987; Istrazivacki nuklearni reaktor RA - Izvestaj o radu za 1987. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1987. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3509/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-12-15

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

  19. PEMODELAN KOLIMATOR DI RADIAL BEAM PORT REAKTOR KARTINI UNTUK BORON NEUTRON CAPTURE THERAPY

    Directory of Open Access Journals (Sweden)

    Bemby Yulio Vallenry

    2015-03-01

    Full Text Available Salah satu metode terapi kanker adalah Boron Neutron Capture Therapy (BNCT. BNCT memanfaatkan tangkapan neutron oleh 10B yang terendapkan pada sel kanker. Keunggulan BNCT dibandingkan dengan terapi radiasi lainnya adalah tingkat selektivitas yang tinggi karena tingkatannya adalah sel. Pada penelitian ini dilakukan pemodelan kolimator di radial beamport reaktor Kartini sebagai dasar pemilihan material dan manufature kolimator sebagai sumber neutron untuk BNCT. Pemodelan ini dilakukan dengan simulasi menggunakan perangkat lunak Monte Carlo N-Particle versi 5 (MCNP 5. MCNP 5 adalah suatu paket program untuk memodelkan sekaligus menghitung masalah transpor partikel dengan mengikuti sejarah hidup neutron semenjak lahir, bertranspor pada bahan hingga akhirnya hilang karena mengalami reaksi penyerapan atau keluar dari sistem. Pemodelan ini menggunakan variasi material dan ukurannya agar menghasilkan nilai dari tiap parameter-parameter yang sesuai dengan rekomendasi I International Atomic Energy Agency (IAEA untuk BNCT, yaitu fluks neutron epitermal (Фepi > 9 n.cm-2.s-1, rasio antara laju dosis neutron cepat dan fluks neutron epitermal (Ḋf/Фepi 0,7. Berdasarkan hasil optimasi dari pemodelan ini, material dan ukuran penyusun kolimator yang didapatkan yaitu 0,75 cm Ni sebagai dinding kolimator, 22 cm Al sebagai moderator dan 4,5 cm Bi sebagai perisai gamma. Keluaran berkas radiasi yang dihasilkan dari pemodelan kolimator radial beamport yaitu Фepi = 5,25 x 106 n.cm-2s-1, Ḋf/Фepi =1,17 x 10-13 Gy.cm2.n-1, Ḋγ/Фepi = 1,70 x 10-12 Gy.cm2.n-1, Фth/Фepi = 1,51 dan J/Фepi = 0,731. Berdasarkan penelitian ini, hasil optimasi 5 parameter sebagai persyaratan kolimator untuk BNCT yang keluar dari radial beam port tidak sepenuhnya memenuhi kriteria yang direkomendasikan oleh IAEA sehingga perlu dilakukan penelitian lebih lanjut agar tercapainya persyaratan IAEA. Kata kunci: BNCT, radial beamport, MCNP 5, kolimator   One of the cancer therapy methods is

  20. Research nuclear reactor RA - Annual Report 1995, with comparative review for period 1991-1995; Istrazivacki nuklearni reaktor RA - Izvestaj za 1995. godinu, uz uporedni pregled za period 1991-1995

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued during period 1991-1995. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 56% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 47 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved during the period 1991-1995. This research reactor RA Annual is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U periodu 1991-1995. godina nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom

  1. Studi Model Benchmark Mcnp6 Dalam Perhitungan Reaktivitas Batang Kendali Htr-10

    OpenAIRE

    Jupiter S.Pane, Zuhair, Suwoto, Putranto Ilham Yazid

    2016-01-01

    STUDI MODEL BENCHMARK MCNP6 DALAM PERHITUNGAN REAKTIVITAS BATANG KENDALI HTR-10. Dalam operasi reaktor nuklir, sistem batang kendali memainkan peranan yang sangat penting karena didesain untuk mengendalikan reaktivitas teras dan memadamkan reaktor. Nilai reaktivitas batang kendali harus diprediksi secara akurat melalui eksperimen dan perhitungan. Makalah ini mendiskusikan model Benchmark dalam perhitungan reaktivitas batang kendali reaktor HTR-10. Perhitungan dikerjakan dengan program transpo...

  2. Efek Durasi Pencahayaan Pada Sistem HRAR Untuk Menurunkan Kandungan Minyak Solar Dalam Air Limbah

    Directory of Open Access Journals (Sweden)

    Dian Puspitasari

    2014-09-01

    Full Text Available Kandungan minyak di dalam air limbah industri perminyakan umumnya bersifat toksik terhadap mikroorganisme dan mengganggu proses pengolahan secara biologis. Sistem HRAR diperkirakan dapat mengatasi hambatan tersebut melalui proses fotosintesis untuk menghasilkan oksigen yang dibutuhkan mikroorganisme dalam mendegradasi senyawa hidrokarbon. Penelitian ini bertujuan mengkaji pengaruh perpanjangan waktu pencahayaan pada kemampuan HRAR dalam menurunkan kandungan minyak di dalam limbah. Variabel yang digunakan pada penelitian ini adalah variasi durasi pencahayaan dan variasi penambahan volume minyak solar yang ditambahkan ke dalam reaktor. Variasi durasi pencahayaan yang digunakan adalah pencahayaan selama 12 jam dan pencahayaan selama 24 jam. Sedangkan penambahan volume minyak solar ke dalam masing-masing reaktor adalah sebesar 346 ppm, 519 ppm dan 692 ppm. Hasil yang didapatkan dari penelitian ini adalah durasi pencahayaan selama 12 jam memiliki efek yang lebih baik terhadap penurunan konsentrasi minyak dibandingkan pencahayaan selama 24 jam. Hal ini dapat terlihat dari baiknya pertumbuhan alga dan bakteri di dalam reaktor serta tingginya penurunan konsentrasi minyak solar di dalamnya. Penurunan konsentrasi minyak solar terbaik terdapat pada reaktor dengan penambahan minyak solar sebesar 346 ppm. Pada reaktor dengan durasi pencahayaan selama 12 jam terjadi penurunan konsentrasi minyak sebesar 78,4%. Sedangkan penurunan kandungan minyak solar pada reaktor dengan durasi pencahayaan selama 24 jam adalah sebesar 73,9%.

  3. The Text of the Agreement of 22 July 1977 between Argentina and the Agency for the Application of Safeguards in Connection with a Contract Concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union Gmbh Hanau (Federal Republic of Germany) for Co-Operation in the Field of Fabrication of Fuel Elements for Peaceful Nuclear Activities

    International Nuclear Information System (INIS)

    1977-01-01

    The text of the Agreement of 22 July 1977 between Argentina and the Agency for the application of safeguards in connection with the Contract of 13 August 1976 concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union GmbH (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities is reproduced in this document for the information of all Members. The Agreement entered into force, pursuant to Section 26, on 22 July 1977.

  4. The Text of the Agreement of 22 July 1977 between Argentina and the Agency for the Application of Safeguards in Connection with a Contract Concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union Gmbh Hanau (Federal Republic of Germany) for Co-Operation in the Field of Fabrication of Fuel Elements for Peaceful Nuclear Activities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-11-30

    The text of the Agreement of 22 July 1977 between Argentina and the Agency for the application of safeguards in connection with the Contract of 13 August 1976 concluded between the Comision Nacional de Energia Atomica (Argentina) and the Reaktor Brennelement Union GmbH (Federal Republic of Germany) for co-operation in the field of fabrication of fuel elements for peaceful nuclear activities is reproduced in this document for the information of all Members. The Agreement entered into force, pursuant to Section 26, on 22 July 1977.

  5. Pra Desain Pabrik Sorbitol dari Tepung Tapioka dengan Hidrogenasi Katalitik

    Directory of Open Access Journals (Sweden)

    Hellen Kartika Dewi

    2014-03-01

    Full Text Available Sorbitol yang dikenal juga sebagai glusitol, adalah suatu gula alkohol yang dimetabolisme lambat di dalam tubuh. Sorbitol banyak digunakan sebagai bahan baku untuk industri barang konsumsi dan makanan seperti pasta gigi, permen, kosmetika, farmasi, vitamin C, termasuk industri tekstil dan kulit. Pembuatan sorbitol dari bahan baku tepung tapioka. Pabrik sorbitol ini direncanakan akan didirikan di Propinsi Jawa Tengah tepatnya di Kabupaten Batang dengan kapasitas produksi 30.000 ton/tahun. Proses produksi Sorbitol menggunakan proses hidrogenasi katalitik. Pembuatan sorbitol dari bahan baku pati melalui dua tahap proses utama yaitu proses perubahan starch menjadi glukosa melalui hidrolisa double enzym. Enzim yang digunakan yaitu α-amylase dan glukoamylase. Proses hidrogenasi katalitik dilakukan dengan mereaksikan larutan dekstrose dan gas hidrogen bertekanan tinggi dengan menambahkan katalis nikel dalam reaktor (Reaktor Hidrogenasi. Gas hidrogen masuk dari bawah reaktor secara bubbling dan larutan dekstrose diumpankan dari atas reaktor sehingga kontak yang terjadi semakin baik. Sorbitol yang di hasilkan dalam pradesain pabrik sorbitol ini dengan konsentrasi 58,2%. Pendirian pabrik sorbitol memerlukan biaya investasi modal tetap (fixed capital sebesar Rp 168.801.192.952, modal kerja (working capital  Rp 29.788.445.815, investasi total Rp 198.589.638.767, Biaya produksi per tahun Rp 368.832.813.809 dan  hasil penjualan per tahun Rp 540.000.078.750. Dari analisa ekonomi didapatkan BEP sebesar 26,32%. ROI sesudah pajak 48,5 %, POT sesudah pajak 2,14 tahun. Dari segi teknis dan ekonomis, pabrik ini layak untuk didirikan.

  6. THERMAL-HYDRAULIC ANALYSIS OF SMR WITH NATURALLY CIRCULATING PRIMARY SYSTEM DURING LOSS OF FEED WATER ACCIDENT

    Directory of Open Access Journals (Sweden)

    Susyadi Susyadi

    2016-09-01

    ABSTRAK Reaktor daya kecil modular (SMR memiliki beberapa keunggulan dibanding reaktor daya besar konvensional. Dengan disain yang lebih sederhana dan terintegrasi, penerapan hukum alamiah untuk sistem keselamatannya dan biaya modal yang rendah, reaktor ini sangat cocok untuk dibangun di Indonesia. Salah satunya disain SMR yang sedang dikembangkan menerapkan gaya penggerak alami untuk sistim pendingin primernya. Dengan disain seperti itu, adalah sangat penting untuk memahami implikasinya terhadap aspek keselamatan pada seluruh kondisi operasi. Salah satu yang perlu diinvestigasi adalah kecelakaan kehilangan air umpan (LoFW. Pada studi ini, dilakukan analisis kinerja thermal hidrolik SMR yang menggunakan sistim pendinginan primer sirkulasi alam saat kecelakaan LoFW. Tujuannya adalah untuk menginvestigasi karakteristik aliran sistem primer saat kecelakaan LoFW dan untuk memastikan apakah aliran sirkulasi alam cukup untuk memindahkan panas dari teras guna menjaga kondisi tetap aman selama kecelakaan tersebut. Metoda yang digunakan adalah dengan merepresentasikan sistem reaktor ke dalam model-model generik program RELAP5 dan melakukan simulasi numerik. Hasil perhitungan menunjukkan bahwa setelah kejadian pemicu dan trip reaktor, pada sisi primer laju alirnya berfluktuasi secara signifikan dan temperatur pendinginnya menurun secara bertahap sedangkan  pada sisi sekunder kondisi uap berubah menjadi uap jenuh. Laju alir turun dari ~711 kg/detik menjadi ~263 kg/detik sebelum kembali naik lagi pada t=~46 detik. Saat laju alir di titik terendah, temperatur pusat bahan bakar dan fluida pendingin adalah sekitar  ~565 K dan  ~554 K, yang menujukkan bahwa temperatur bahan bakar masih jauh di bawah batas disain dan temperatur fluidanya juga berada di bawah titik saturasi. Keadaan ini menunjukkan bahwa saat transien kedua parameter utama termohidrolik reaktor tetap dalam kondisi yang dapat diterima sehingga dapat disimpulkan  bahwa saat  kecelakaan kehilangan air umpan, SMR

  7. Integrating 3D CAD data for manufacturing and fabrication the core model of reactor TRIGA PUSPATI

    International Nuclear Information System (INIS)

    Abu Bakar Harun

    2005-01-01

    This paper describe the intrigue integration of digital 3 Dimensional Computer Aided Design (3D CAD) data manipulation for the Core Model fabrication of REAKTOR TRIGA PUSPATI and ready for mass manufacturing. 3 Dimensional CAD data from Computer Aided Design program will be used as an interpreter in the fabrication of this project. The Core Model of REAKTOR TRIGA PUSPATI will be fabricated with the aid of 3D CAD drawings and digital files. The components will be segregated and divided into 2 categories namely Conventional d Rapid Fabrication. (Author)

  8. PENGURANGAN KADAR CO2 MENGGUNAKAN SPIRULINA PLATENSIS DALAM TUBULAR BIOREACTOR

    Directory of Open Access Journals (Sweden)

    Zainal Syam Arifin

    2015-06-01

    Meningkatnya jumlah penduduk berdampak pada peningkatan kebutuhan energi. Di lain pihak, industri pembangkit energi dituding sebagai salah satu penyumbang karbon dioksida sekitar 25% dari total emisi CO2 di seluruh dunia. Disisi lain, produksi biogas yang bertujuan untuk mengatasi peningkatan kebutuhan energi justru menghasilkan karbon dioksida pada kisaran 25 – 50% volume. Untuk mengatasi hal ini, diperlukan metode yang murah, optimum dan efisien serta ramah lingkungan dalam mengurangi kadar CO2 dengan menggunakan spirulina platensis.  Penelitian ini bertujuan membuat model matematik dan menemukan kecepatan aliran yang optimum untuk menurunkan kadar CO2 dengan menggunakan Spirulina Platensis. Penelitian ini menggunakan reaktor tubularterbuat dari kaca (D = 2,6 cm pada suhu 30°C dan disinari dengan lampu TL Philips fluoresen 36 Watt, temperatur warna: 6.200K cool daylight, light output: 2.600 lm, 72 lm/W. Reaktor tubular ditempatkan dalam kotak yang dilapisi dinding dengan kertas perak pada ketiga sisinya. Dengan model matematik reaktor tubular, dapat diprediksi konstanta kecepatan reaksinya. Berdasarkan grafik hasil perhitungan data, kecepatan volumetrik optimumnya juga dapat diprediksi. Variasi flowrate yaitu 0,25 mL/detik, 0,35 mL/detik, 0,5 mL/detik, 0,75 mL/detik, 1 mL/detik. Sumber karbon adalah CO2 99,99%. Pengamatan pertumbuhan Spirulina dilakukan pada flow rate 0,25 mL/detik dengan kadar berat kering mula – mula 2,1208 g/L. Hasil penelitian ini menunjukkan bahwa aliran lambat (flowrate rendah merupakan cara yang lebih efektif dalam mengurangi karbon dioksida menggunakan spirulina platensis (= 2,82×10-4 detik-1. Nilai konversi tertinggi diperoleh pada kecepatan aliran volumetrik 0,25 mL/detik dan kecepatan optimumnya pada kisaran 0,3 – 0,4 mL/detik. Laju flux CO2 masuk sebaiknya kurang dari 0,047 mL/cm2.detik. Nilai Specific Growth Rate (µ Spirulina Platensis dalam penelitian ini yaitu 2,56×10-2 menit-1.   Kata Kunci: Spirulina platensis, reaktor tubular

  9. ANALISA KARAKTERISTIK MINYAK PLASTIK HASIL DUA KALI PROSES PIROLISIS

    Directory of Open Access Journals (Sweden)

    Untung Surya Dharma

    2015-06-01

    Full Text Available Limbah plastik dapat dimanfaatkan sebagai bahan baku minyak plastik dengan menggunakan proses pirolisis. Minyak plastik yang dihasilkan dapat dimanfaatkan sebagai zat aditif atau campuran bahan bakar pada mesin. Pada Penelitian ini, proses pembuatan minyak plastik menggunakan dua kali proses pirolisis. Suhu reaktor pada proses pirolisis yang pertama dan kedua berbeda berturut-turut yaitu 200 oC dan 150 oC. Dari hasil penelitian ini diketahui bahwa pada proses pirolisis pertama dengan suhu reaktor 200 oC, dari 25 kg bahan baku menghasilkan 15,5 liter minyak plastik dalam waktu 80 jam. Sedangkan pada proses pirolisis kedua dengan suhu reaktor 150 oC, dari 15 liter minyak plastik dari hasil proses pirolisis pertama menghasilkan 11,6 liter minyak plastik dalam waktu 3,33 Jam. Adapun karakter minyak plastik yang dihasilkan adalah massa jenis 771,4 kg/m3, Viskositas 0,501 m2/s dan Nilai kalor 10518 kJ/kg

  10. ANALISIS SKENARIO KEGAGALAN SISTEM UNTUK MENENTUKAN PROBABILITAS KECELAKAAN PARAH AP1000

    Directory of Open Access Journals (Sweden)

    D.T. Sony Tjahyani

    2014-03-01

    Full Text Available Kejadian Fukushima telah menunjukkan bahwa kecelakaan parah dapat terjadi, maka dari itu sangatlah penting untuk menganalisis tingkat keselamatan pada reaktor daya. Berdasarkan rekomendasi expert mission IAEA setelah kejadian Fukushima, perlu dilakukan upaya untuk meminimalisasi terjadinya kecelakaan parah yaitu dengan melakukan proses pendinginan yang maksimal. Dalam konsep keselamatan fasilitas nuklir, khususnya reaktor daya telah diterapkan konsep keselamatan berlapis (Defence in Depth, DiD. Konsep keselamatan tersebut terdiri atas 5 level pertahanan yang bertujuan mencegah dan mengurangi lepasan produk fisi ke masyarakat dan lingkungan pada saat reaktor daya mengalami kecelakaan. Dalam reaktor telah didesain sistem atau tindakan yang mempunyai fungsi untuk mengatasi setiap level tersebut. Tujuan dari analisis ini adalah menentukan probabilitas kecelakaan parah dengan melakukan skenario kegagalan sistem dalam proses pendinginan di reaktor. Sebagai obyek analisis adalah reaktor daya AP1000, karena jenis reaktor ini sedang banyak dibangun saat ini. Skenario dilakukan dengan mengasumsikan beberapa kombinasi kegagalan sistem yang termasuk dalam DiD level 2 dan 3. Kegagalan sistem kemudian dianalisis dengan menggunakan analisis pohon kegagalan berdasarkan perangkat lunak SAPHIRE ver. 6.76. Dari analisis didapatkan probabilitas gagal dari kelompok sistem DiD level 2 dan 3 pada AP1000 masih di bawah batas kriteria dari IAEA yaitu lebih kecil dari 10-2, serta probabilitas kecelakaan parah didapatkan sebesar 6,17 x 10-10. Berdasarkan analisis ini disimpulkan bahwa AP1000 mempunyai tingkat keselamatan yang cukup tinggi, karena melalui skenario kegagalan sistem didapatkan probabilitas kecelakaan parah yang sangat kecil.   ABSTRACT Fukushima accident has shown that severe accident could be occurred, therefore it is important to analyze safety level of nuclear power plants. Based on the recommendations of IAEA expert mission after the Fukushima accident

  11. KARAKTERISTIK REAKTIVITAS TERAS KERJA RSG-GAS SELAMA 30 TAHUN BEROPERASI

    Directory of Open Access Journals (Sweden)

    Tukiran Surbakti

    2017-06-01

    Full Text Available RSG-GAS, mulai dari komisioning, operasi teras kerja hingga kini telah 30 tahun beroperasi sehingga perlu dilakukan evaluasi keselamatan parameter neutroniknya. Untuk tujuan keselamatan telah dilakukan berbagai aktivitas penelitian, baik yang berhubungan dengan operasi, keselamatan, maupun dalam rangka penggunaan reaktor. Analisis dan pengelolaan besaran reaktivitas yang menunjang keselamatan operasi reaktor sangat penting dilakukan karena besaran ini mempengaruhi desain, kendali dan jadual operasi reaktor. Besaran tersebut dapat ditentukan melalui pengukuran reaktivitas batang kendali dan eksperimen pemuatan bahan bakar di dalam teras. Pengukuran reaktivitas batang kendali yang dilakukan pada setiap awal siklus teras (dengan kondisi teras dingin dan bersih, bebas pengaruh xenon, menghasilkan nilai reaktivitas batang kendali yang dapat digunakan untuk menentukan nilai reaktivitas lainnya seperti reaktivitas lebih, reaktivitas padam dan reaktivitas total. Pengelolaan reaktivitas teras telah dilakukan dengan baik selama 30 tahun dalam rangka mendukung operasi reaktor untuk keperluan penelitian dan iradiasi target.

  12. 10-{4-[(2-Hydroxybenzylideneamino]phenyl}-5,5-difluoro-1,3,7,9-tetramethyl-5H-dipyrrolo[1,2-c:2′,1′-f][1,3,2]diazaborinin-4-ium-5-uide

    Directory of Open Access Journals (Sweden)

    Zhensheng Li

    2013-07-01

    Full Text Available The title compound, C26H24BF2N3O, comprises a boron–dipyrromethene (BODIPY framework and a phenolic Schiff base substituent group. The BODIPY unit is close to planar [maximum deviation from the least-squares plane = 0.040 (3 Å], and forms a dihedral angle of 80.38 (13° with the meso-substituent phenyl ring and an angle of 56.57 (13° with the phenolic ring in the extended substituent chain. An intramolecular O—H...N hydrogen bond is formed between the phenolic hydroxyl group and the Schiff base N-atom. The crystal studied was a non-merohedral twin with a BASF factor of 0.447 (3 for the two components.

  13. Fission gas release from the sintered UO{sub 2} fuel; Oslobadjanje fisionih gasova iz goriva od sinterovanog UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Sigulinski, F; Stevanovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    This paper shoes the phenomena which control fission gases release from the sintered UO{sub 2} dependent of the burnup rate: ejection, release, diffusion, increased fission gas accumulation causing structural changes in the fuel. release of fission gases from the fuel for power reactors was studied as well. The influence of factors as temperature, characteristics of fuel, burnup rate and burnup level was analyzed. Prikazani su mehanizmi koji kontrolisu izdvajanje fisionih gasova iz sinterovanog UO{sub 2} pri razlicitim brzinama izgaranja: izletanje, izbijanje, difuzija, povecano izdvajanje fisionih gasova koje prati strukturne promene u gorivu. Razmatrano je proucavanje izdvajanja fisionih gasova iz goriva za reaktore snage. Analiziran je uticaj faktora kao sto su temperatura, karakteristike goriva, brzina i stepen izgaranja (author)

  14. External irradiation of the personnel operating the reactor RA at Vinca in the period 1963-1966; Spoljasnje ozracivanje osoblja koje opsluzuje reaktor RA u Vinci u periodu 1963-1966

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M M; Minincic, Z [Institut za nuklearne nauke Vinca, Belgrade (Yugoslavia)

    1967-07-01

    The objective of this paper was the analysis of external radiation exposure of the personnel employed at the RA reactor in Vinca during past four years. During 1963 reactor was not operated because of the general repair and maintenance, and it was operated during 1964, 1965 and 1966. The internal irradiation and the estimation of the beta doses on the skin were not analysed in this paper, they should be treated by separate analyses. The evaluation of external irradiation covered only gamma radiation since yhe neutron doses were negligible. The analysis was based on the the irradiation dose data obtained by film and personal dosemeters. Predmet ovog rada je analiza spoljasnjeg ozracivanja osoblja koje je radilo na reaktoru RA u Vinci u poslednje cetiri godine, u toku kojih je reaktor bio u opstem remontu 1963, odnosno u normalnom radu 1964, 1965 i 1966. U ovom radu nismo se upustali u analizu unutrasnjeg ozracivanja, kao ni procenu doza beta zracenja na kozi, sto treba da bude predmet posebnih analiza. Pri proceni spoljasnjeg ozracivanja operisano je samo sa dozama gama zracenja, jer je ozracivanje neutronima zanemarljivo. Celokupna analiza izvrsena je na osnovu podataka o dozama ozracivanja do kojih se doslo ocitavanjem film o penkalo dozimetara.

  15. Preparation of PtSnCu/C and PtSn/C electrocatalysts and activation by dealloying processes for ethanol electrooxidation

    International Nuclear Information System (INIS)

    Crisafulli, Rudy

    2013-01-01

    PtSnCu/C (with different Pt:Sn:Cu atomic ratios) and PtSn/C (50:50) electrocatalysts were prepared by borohydride (BR) and alcohol-reduction (AR) processes using H 2 PtCl 6 .6H 2 O, SnCl 2 .2H 2 O and CuCl 2 .2H 2 O as metal sources, NaBH 4 and ethylene glycol as reducing agents, 2-propanol and ethylene glycol/water as solvents and carbon black as support. In a further step, these electrocatalysts were activated by chemical (CD) and electrochemical (ED) dealloying processes through acid treatment and thin porous coating technique, respectively. These materials were characterized by energy dispersive X-ray, Xray diffraction, transmission electron microscopy, line scan energy dispersive Xray and cyclic voltammetry. Electrochemical studies for ethanol electro-oxidation were performed by cyclic voltammetry, chronoamperometry and in single Direct Ethanol Fuel Cell using Membrane Electrode Assembly (MEA). The anodic effluents were analysed by gas chromatography. The X-ray diffractograms of the as-synthesized electrocatalysts showed the typical face-centered cubic structure (FCC) of platinum and its alloys. After dealloying, the X-ray diffractograms showed that the Pt FCC structure was preserved. The crystallite sizes of the assynthesized electrocatalysts were in the range of PtSnCu/C (50:40:10) AR/ED > PtSnCu/C (50:10:40) BR/CD. PtSn/C (50:50) BR/CD, PtSnCu/C (50:10:40) BR/CD, PtSnCu/C (50:40:10) AR/CD electrocatalysts and Pt/C BASF, PtSn/C (75:25) BASF commercial electrocatalysts were tested in single Direct Ethanol Fuel Cell. The results showed the following performance for ethanol electro-oxidation: PtSn/C (50:50) BR/CD > PtSnCu/C (50:40:10) AR/CD > PtSnCu/C > PtSn/C (75:25) BASF > PtSnCu/C (50:10:40) BR/CD > Pt/C BASF. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-12-15

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

  17. Kajian Pemilihan Sumber Mikroorganisme Solid Phase Microbial Fuel Cell (SMFC Berdasarkan Jenis dan Volume Sampah, Power Density dan Efisiensi Penurunan COD

    Directory of Open Access Journals (Sweden)

    Ganjar Samudro

    2017-06-01

    Full Text Available Mikroorganisme merupakan salah satu komponen penting dalam proses Solid Phase Microbial Fuel Cell (SMFC untuk degradasi bahan organik dan transfer elektron. Pemilihan sumber mikroorganisme menjadi metode yang paling sederhana untuk dikaji sebagai informasi awal ketersediaan dan identifikasi jenis mikroorganisme yang mendukung proses SMFC. Tujuan kajian ini adalah untuk memilih sumber mikroorganisme tanah, septic tank dan sedimen sungai yang tepat digunakan dalam proses SMFC berdasarkan jenis dan volume sampah, power density, dan efisiensi penurunan COD. Kajian ini didasarkan pada hasil penelitian menggunakan reaktor SMFC tipe single chamber microbial fuel cell dengan variabel jenis dan volume sampah , serta sumber mikroorganisme. Metode perbandingan secara kuantitatif dilakukan berdasarkan kecenderungan nilai power density dan efisiensi penurunan COD tertinggi di antara jenis dan volume sampah kantin, dedaunan dan komposit kantin-dedaunan. Hasil yang didapatkan adalah sumber mikroorganisme tanah dan sedimen sungai tepat digunakan untuk volume sampah 1/3 dan 2/3 dari volume reaktor, sedangkan sumber mikroorganisme septic tank tepat digunakan untuk volume sampah 1/3 dan 1/2 dari volume reaktor. Sumber mikroorganisme dari septic tank menunjukkan kinerja power density dan efisiensi penurunan COD yang lebih rendah dibandingkan sumber mikroorganisme tanah dan sedimen sungai.

  18. RA Research reactor, Annual report 1972; Istrazivacki nuklearni reaktor RA - Izvestaj za 1972. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1972-12-15

    During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO{sub 2} capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system. [Serbo-Croat] Ukupni rad Reaktora RA je u 1972. godini iznosio je 31151 MWh odnosno 3,8% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 381 korisnika od cega 340 iz Instituta i 41 za korisnike izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i

  19. Strength of High Performance Grouts

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.

    The present report describes tests carried out on 5 experimental grouts developed by BASF Construction Materials and designed for use in grouted connections of offshore windmill foundations.......The present report describes tests carried out on 5 experimental grouts developed by BASF Construction Materials and designed for use in grouted connections of offshore windmill foundations....

  20. Strength of Experimental Grouts

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.

     The present report describes tests carried out on 5 experimental grouts developed by BASF Construction Materials and designed for use in grouted connections of offshore windmill foundations....... The present report describes tests carried out on 5 experimental grouts developed by BASF Construction Materials and designed for use in grouted connections of offshore windmill foundations....

  1. APLIKASI TEKNIK AAN DI REAKTOR RSG-GAS PADA PENENTUAN UNSUR ESENSIAL DAN TOKSIK DI DALAM IKAN DAN PAKAN IKAN

    Directory of Open Access Journals (Sweden)

    Saeful Yusuf

    2015-03-01

    Full Text Available Pada makalah ini diuraikan tentang aplikasi teknik AAN (Analisis Aktivasi Neutron dalam penentuan konsentrasi unsur-unsur esensial dan cemaran yang terkandung di dalam beberapa spesies ikan dan pakan ikan. Unsur-unsur esensial yang terkandung dalam pakan ikan buatan juga dianalisis untuk mengetahui pengaruhnya terhadap ikan. Penentuan unsur menggunakan teknik AAN dengan metode perbandingan dan metode k0-AAN. Sampel diiradiasi di reaktor RSG-GAS yang memiliki fluks neutron thermal 5 x 1013 n.cm-2.s-1 pada daya 15 MW. Hasil penelitian menunjukkan bahwa 12 unsur di dalam 11 spesies ikan air laut dan air tawar telah ditentukan yaitu As, Br, Cr, Co, Cs, Fe, Hg, K, Na, Rb, Se and Zn. Konsentrasi cemaran As didalam ikan laut sudah melampaui batas maksimum 1 mg/kg, sedangkan konsentrasi cemaran Hg masih dibawah batas maksimum 0,5 mg/kg, baik untuk ikan laut maupun ikan air tawar. Unsur K dan Na merupakan unsur makroesensial sedangkan unsur Cr, Co, Fe, Se and Zn adalah termasuk unsur mikroesensial. Secara umum ditunjukkan bahwa kandungan mineral didalam ikan laut lebih tinggi konsentrasinya dibandingkan ikan air tawar. Br, Cs dan Rb merupakan unsur-unsur non esensial yang teridentifikasi dalam semua ikan yang dianalisis. Penelitian terhadap pakan ikan air tawar menunjukkan bahwa semua unsur yang teridentifikasi juga terdapat di dalam ikan laut dan ikan air tawar. Hal ini menunjukkan bahwa pakan ikan berkontribusi terhadap konsentrasi unsur di dalam ikan air tawar. Kata kunci : Analisis aktivasi neutron, unsur esensial, unsur cemaran, ikan, pakan ikan   This paper reported on the application of NAA (Neutron Activation Analysis Technique in the determination of the concentration of the essential and toxic elements in some species of fish and fish feed. Determination of elements using instrumental NAA technique with comparison and k0-INAA methods. Samples were irradiated in the RSG-GAS which has a thermal neutron flux  5.0E +13 ncm-2s-1. The results

  2. Shale gas opportunities. Dehydrogenation of light alkanes

    Energy Technology Data Exchange (ETDEWEB)

    Patcas, F.C.; Dieterle, M.; Rezai, A.; Asprion, N. [BASF SE, Ludwigshafen (Germany)

    2013-11-01

    The discovery and use of shale gas in North America has become a game changer for the chemical industry by access to a cheaper feedstock compared to conventional oil. Increased number of ethane crackers spurred increasing interest in light alkanes dehydrogenation. Several companies have announced their interest in new propane dehydrogenation units in North America. BASF is developing light alkanes dehydrogenation technologies for two decades now. BASF developed jointly with Linde the isothermal C3 dehydrogenation process. The latest dehydrogenation catalyst development at BASF focused on a supported and steam resistant Pt-Sn catalyst which yielded excellent selectivity and activity. Intense research work both internally as well as in cooperation with universities contributed to the understanding of the relationship between the surface structure and catalyst performances like activity, selectivity and coking resistance. Using such type of catalysts BASF developed an autothermal propane dehydrogenation as well as a butane dehydrogenation process. The most recent catalyst development was a dehydrogenation catalyst coated on a honeycomb monolith to improve catalyst usage and pressure drop. This will probably be the first industrial usage of catalytic monoliths in a chemical synthesis process. (orig.) (Published in summary form only)

  3. The reactor accident in the Three Mile Island-2 reactor plant. (Harrisburg, USA)

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The presentation of the accident development is based on the bulletin of the Atomic Industrial Forum (AIF) from the 6th of April, 1979. In addition, there are some short pieces of information, No. 14 and 15 of the association for reactor security as well as written and verbal information of the firms Brown, Boveri and Co/Babcock-Brown Boveri Reaktor GmbH (BBC/BBR). (orig.) [de

  4. Dichlorido{2-[(5-methyl-1H-pyrazol-3-yl-κN2methyl]-1H-1,3-benzimidazole-κN3}zinc

    Directory of Open Access Journals (Sweden)

    Karim Chkirate

    2017-01-01

    Full Text Available The asymmetric unit of the title complex, [ZnCl2(C12H12N4], contains two independent molecules having similar conformations. The coordination about the ZnII atom is distorted tetrahedral, with the geometrical constraints of the chelating ligand responsible for the observed distortion. Each of the independent molecules forms chains in the crystal through pairs of N—H...Cl hydrogen bonds, using the pyrazole and benzimidazole N—H groups as donors. The first molecule forms chains running parallel to the b axis, while the other molecule affords the same kind of one-dimensional supramolecular structure parallel to the a axis. The structure was refined as a two-component twin with BASF = 0.0437 (4.

  5. High-capacity electrode materials for electrochemical energy storage

    Indian Academy of Sciences (India)

    2015-06-02

    Jun 2, 2015 ... We discuss the role of nanoscale effects on the electrochemical ..... tems and BASF for developing high energy density lithium ion cells for plug-in electric ..... SEM and STEM images showing typical shapes and sizes of FeF2 ...

  6. Progress in the development of uranium silicide (U3Si2) fuel at BATAN

    International Nuclear Information System (INIS)

    Suripto, A.; Soentono, S.

    1995-01-01

    After successful fabrication of two full-size prototype fuel elements containing ∼3.0 gU/cm 3 in the form of U 3 Si 2 -Al dispersion now undergoing irradiation in the Reaktor Serba Guna G.A. Siwabessy (RSG-GAS) core since 1990, further development in U 3 Si 2 -A2 dispersion fuel element manufacturing has been pursued, whose progress in discussed in this paper, with a special attention on the use of much higher-loading aimed at obtaining a better understanding on the influence of higher-loading on fuel core and plate manufacturing and quality. At present, high-loading U 3 Si 2 -AI dispersion miniplates are being manufactured for preparing some mini-fuel elements to be test-irradiated in the new MTR in-pile loop of the RSG-GAS. (author)

  7. μ-(2,6-Bis{[3-(dimethylaminopropyl]iminomethyl}-4-methylphenolato-μ-hydroxido-bis[(thiocyanato-κNcopper(II

    Directory of Open Access Journals (Sweden)

    M. G. Meera

    2013-10-01

    Full Text Available In the title compound, [Cu2(C19H31N4O(OH(NCS2], the molecular structure of the dinuclear complex reveals two pentacoordinated CuII ions, which are bridged by the phenolate O atom of the ligand and by an exogenous hydroxide ion. The bridging atoms occupy equatorial positions in the coordination sphere of the metal atoms and complete the equatorial coordination planes with two ligand N atoms, the apical positions being occupied by thiocyanate N atoms. The crystal structure also features π–π stacking interactions involving the benzene rings with a centroid–centroid distance of 3.764 (4Å. The crystal studied was a non-merohedral twin, with a refined BASF value of 0.203 (2

  8. EFEK DENSITAS BAHAN BAKAR TERHADAP PARAMETER KOEFISIEN REAKTIVITAS TERAS RRI

    Directory of Open Access Journals (Sweden)

    Rokhmadi Rokhmadi

    2015-03-01

    Full Text Available Manfaat yang luas penggunaan reaktor riset membuat banyak negara membangun reaktor riset baru. Kecenderungan saat ini adalah tipe reaktor serbaguna (MPR dengan teras yang kompak untuk mendapatkan fluks neutron yang tinggi dengan daya yang relatif rendah. Reaktor riset yang ada di Indonesia usianya sudah tua semuanya. Oleh karena itu diperlukan desain reaktor riset baru sebagai alternatif, disebut reaktor riset inovatif (RRI, kelak pengganti reaktor riset yang sudah ada. Tujuan dari riset ini untuk melengkapi data desain RRI sebagai salah satu persyaratan untuk perizinan desain. Perhitungan dilakukan untuk memperoleh nilai koefisien reaktivitas teras RRI dengan konfigurasi teras setimbang yang optimal dengan konfigurasi teras 5×5 dan daya 20 MW, memiliki panjang operasi satu siklus lebih dari 40 hari. Perhitungan koefisien reaktivitas teras RRI dilakukan untuk bahan bakar baru U-9Mo-Al dengan kerapatan bervariasi. Perhitungan dilakukan dengan paket program WIMSD-5B dan BATAN-FUEL. Hasil pehitungan digunakan untuk melengkapi data desain konseptual teras yang menunjukkan bahwa teras setimbang reaktor RRI dengan konfigurasi 5×5, tingkat muat 235U sebesar 450 g, 550 g dan 700 g memiliki nilai koefisien reaktivitas temperatur bahan bakar, temperatur moderator, densitas moderator dan void semuanya negatif dan nilainya sangat bervariasi. Hal ini sudah memenuhi kriteria keselamatan desain konseptual teras RRI. Kata kunci: desain konseptual, bahan bakar uranium-molibdenum, koefisien reaktivitas, WIMS, BATANFUEL   The multipurpose of research reactor utilization make many countries build the new reserach reactor. Trend of this reactor for this moment is multipurpose reactor type with a compact core to get high neutron flux at the low or medium level of power. The research reactor in Indonesia right now is already 25 year old. Therefor, it is needed to design a new research reactor as a alternative called it innovative research reactor (IRR and then as

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

    Directory of Open Access Journals (Sweden)

    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

  10. External irradiation of the personnel operating the reactor RA at Vinca in the period 1963-1966; Spoljasnje ozracivanje osoblja koje opsluzuje reaktor RA u Vinci u periodu od 1963. do 1966. godine

    Energy Technology Data Exchange (ETDEWEB)

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

    1968-06-15

    The paper first gives a survey of the characteristic operations performed on the Vinca reactor RA in which most of the personnel become irradiated. Following is a schematic diagram of the irradiations in the period 1963-1966 in which the reactor was in continual operation. The surveys are given for each month and each year separately, while the irradiated personnel are grouped in several characteristic irradiation dose ranges. In this analysis special emphasis is given to a survey of irradiation of the personnel classified according to their profession, i.e. their post. This kind of analysis is indispensable in planning work, proper disposition of the personnel and undertaking special protective measures for reducing the irradiations (author) [Serbo-Croat] U radu je najpre dat pregled mesta na reaktoru RA, sa topografijom zracenja, na kojima radno osoblje pretezno biva ozracivano. Zatim su dati tabelarno i graficki pregledi ozracivanja za protekli period u kome je reaktor neprekidno radio, tj. od 1963. do 1966. god. Pregledi su dati po mesecima za svaku godinu i to tako sto su ozracivana lica razvrstavana u nekoliko karakteristicnih intervala doza ozracivanja. Posebno mesto u ovoj analizi zauzima pregled ozracivanja osoblja razvrstanog po strukama, odnosno radnim mestima. Ovakva analiza je nuzna za planiranje poslova, pravilan raspored radnog osoblja kao i preduzimanje posebnih zastitnih mera u cilju smanjivanja ozracivanja (author)

  11. Studi Awal Desain Pebble Bed Reactor Berbasis Htr-pm Dengan Skema Resirkulasi Bahan Bakar Once-through-then-out

    OpenAIRE

    Setiadipura, Topan; Pane, Jupiter Sitorus; Zuhair, Zuhair

    2016-01-01

    STUDI AWAL DESAIN PEBBLE BED REACTOR BERBASIS HTR-PM DENGAN RESIRKULASI BAHAN BAKAR ONCE-THROUGH-THEN-OUT. Reaktor nuklir tipe pebble bed reactor (PBR) adalah salah satu reaktor canggih dengan fitur keselamatan pasif yang kuat. Pada desain tipe ini berpotensi untuk dilakukan kogenerasi yang bermanfaat untuk pengolahan berbagai mineral di berbagai pulau di Indonesia. Operasi PBR dapat lebih disederhanakan dengan menerapkan skema pengisian bahan bakar once-through-then-out (OTTO) dimana bahan b...

  12. CO2 Capacity Sorbent Analysis Using Volumetric Measurement Approach

    Science.gov (United States)

    Huang, Roger; Richardson, Tra-My Justine; Belancik, Grace; Jan, Darrell; Knox, Jim

    2017-01-01

    In support of air revitalization system sorbent selection for future space missions, Ames Research Center (ARC) has performed CO2 capacity tests on various solid sorbents to complement structural strength tests conducted at Marshall Space Flight Center (MSFC). The materials of interest are: Grace Davison Grade 544 13X, Honeywell UOP APG III, LiLSX VSA-10, BASF 13X, and Grace Davison Grade 522 5A. CO2 capacity was for all sorbent materials using a Micromeritics ASAP 2020 Physisorption Volumetric Analysis machine to produce 0C, 10C, 25C, 50C, and 75C isotherms. These data are to be used for modeling data and to provide a basis for continued sorbent research. The volumetric analysis method proved to be effective in generating consistent and repeatable data for the 13X sorbents, but the method needs to be refined to tailor to different sorbents.

  13. Pengaruh penambahan Ca(OH2 pada Proses Pirolisis terhadap Hasil Gasifikasi Batubara Bituminus dengan medium Gas CO2

    Directory of Open Access Journals (Sweden)

    Saripah Sobah

    2014-06-01

    Full Text Available Pemanfaatan batubara melalui proses gasifikasi perlu dikembangkan lebih lanjut karena proses ini dapat dijadikan alternatif untuk menggantikan peranan  gas alam sebagai sumber gas sintesis. Di samping itu, proses ini dapat mengurangi pencemaran lingkungan karena teknologi gasifikasi merupakan teknologi yang bersih dan dapat mengurangi jumlah gas CO2 yang dibuang ke lingkungan. Penelitian ini bertujuan untuk mengetahui pengaruh penambahan Ca(OH2 pada proses pirolisis terhadap hasil gasifikasi arang batubara bituminus dengan medium gas CO2. Reaksi karbon dari arang batubara dengan gas CO2 pada proses gasifikasi merupakan reaksi endotermis dan berlangsung sangat lambat pada suhu di bawah 1000oC sehingga digunakan Ca(OH2 sebagai katalisator. Proses gasifikasi batubara dijalankan dalam reaktor fixed bed. Hasil penelitian menunjukkan bahwa gasifikasi arang batubara dengan penambahan Ca(OH2 pada proses pirolisis memberikan pengaruh terhadap komposisi gas hasil yaitu berkurangnya kadar gas CO2 dan menyebabkan berkurangnya kadar belerang pada arang hasil pirolisis dan gasifikasi. Proses ini juga dapat mengurangi kadar gas CO2 sebesar 63,17% dan untuk  gasifikasi tanpa Ca(OH2 , CO2 dapat dikurangi kadarnya sampai 35,2%.

  14. Perancangan dan Simulasi MRAC untui Proses Pengendalian Temperatur pada Continuous Stirred Tank Reactor (CSTR

    Directory of Open Access Journals (Sweden)

    Amelia Sylvia

    2014-03-01

    Full Text Available Temperatur merupakan salah satu variabel proses dasar yang dikendalikan untuk menjaga suhu cairan di dalam reaktor. Model Reference Adaptive Controller (MRAC dengan MIT rule dipilih untuk mencapai spesifikasi respon yang diinginkan pada CSTR. Beban yang bervariasi berupa debit aliran likuid yang masuk ke dalam reaktor dapat menyebabkan perubahan parameter yang mempengaruhi perubahan temperatur output produk pada CSTR. Sebuah simulasi dilakukan dengan menggunakan MATLAB dan hasilnya dianalisa. Respon plant dapat melakukan adaptasi parameter – parameter kontrolernya cukup baik pada nilai gain adaptasi dengan rentang 0.00000010000 sampai 0.00000000001. Waktu yang dibutuhkan untuk mengatasi beban yang bervariasi berupa debit aliran yang masuk ke dalam reaktor dengan nilai yang maksimal (1.5 m^3/min menghasilkan respon plant lebih cepat 42 detik dari pada debit aliran masuk dengan nilai yang nominal (1 m^3/min 63 detik dan minimal (0.5 m^3/min 75 detik.

  15. Studi Efisiensi Penyisihan COD dalam Lindi dengan Sistem Evapotranspirasi Menggunakan Tumbuhan Sente (Alocasia macrorrhiza dan Rumput Belulang (Eleusine indica

    Directory of Open Access Journals (Sweden)

    Badrus Zaman

    2017-11-01

    Full Text Available COD dalam lindi merupakan salah satu parameter yang secara umum berada pada konsentrasi yang tiggi sebagai salah satu hasil biodegradasi material organik dan anorganik dalam sampah di TPA. Sistem evapotranspirasi yang menggunakan tumbuhan lokal merupakan salah satu sistem yang menjanjikan. Penelitian dilakukan untuk mengetahui efisiensi penyisihan COD dalam lindi dengan reaktor evapotranspirasi secara kontinyu yang menggunakan tumbuhan Tumbuhan Sente (Alocasia macrorrhiza dan Rumput Belulang (Eleusine indica. Hasil uji menunjukkan efisiensi pada semua reaktor mulai sekitar hari ke 3 hingga hari ke 25 mengalami fluktuasi yang cenderung menurun (dari ± 75% menjadi ± 50%, tetapi hari selanjutnya cenderung meningkat. Pola tersebut dipengaruhi oleh peran media tanam, bakteri dalam media tanam, bakteri pada akar tumbuhan dan aktivitas metabolisme tumbuhan uji. Secara keseluruhan reaktor yang menggunakan Tumbuhan Sente (Alocasia macrorrhiza lebih fluktuatif dibandingkan denga menggunakan Rumput Belulang (Eleusine indica yang dipengaruhi pola pertumbuhan dan perkembangannya.

  16. A new polymorph of aquabis(1,10-phenanthroline-κ2N,N′copper(II dinitrate

    Directory of Open Access Journals (Sweden)

    Mehdi Boutebdja

    2014-05-01

    Full Text Available The title molecule, [Cu(C12H8N22(H2O](NO32, is a new polymorph of a compound which up to now has been reported to crystallize space groups in C2/c and Cc. The crystal studied was twinned by non-merohedry (final BASF factor of 0.40043 with the structure being solved and refined in P-1. The CuII atom is coordinated by four N atoms from two 1,10-phenanthroline ligands and an O atom from a water molecule in an approximate trigonal–bipyramidal geometry. Discrete entities of one cation and two nitrate anions are formed by water–nitrate O—H...O hydrogen bonds. The components are further assembled into a three-dimensional network by C—H...O hydrogen bonds.

  17. Pengolahan Sampah Secara Pirolisis dengan Variasi Rasio Komposisi Sampah dan Jenis Plastik

    Directory of Open Access Journals (Sweden)

    Qonita Rachmawati

    2015-03-01

    Full Text Available Pada tahun 2012, sampah yang dihasilkan sebesar 1200 ton/hari. Jika permasalahan sampah di Kota Surabaya tidak ditangani dengan baik maka akan menimbulkan beberapa masalah antara lain: masalah kesehatan dan masalah kebersihan. Oleh karena itu, diperlukan metode yang dapat mengolah sampah namun tidak menimbulkan masalah baru lainnya. Salah satu metode pengolahan sampah yang telah dikembangkan, yaitu metode pirolisis. Penelitian ini bertujuan untuk menentukan pengaruh jenis plastik dan komposisi terhadap produk hasil pirolisis. Pada penelitian ini digunakan reaktor dengan kapasitas 500 g yang berbahan stainless steel. Variabel yang digunakan yaitu jenis sampah plastik dan komposisi sampah. Jenis sampah yang digunakan yaitu sampah plastik HDPE (High Density Polyethylene, PET (Poly Ethylene Terephthalate, dan PS (Poly Styrene. Komposisi sampah yang digunakan antara lain: 100:0, 75:25, dan 50:50. Temperatur yang digunakan pada reaktor yaitu 500°C dengan waktu 30 menit. Penelitian dimulai dari persiapan bahan uji, persiapan reaktor, percobaan pendahuluan, dan penelitian dengan reaktor pirolisis. Selanjutnya dilakukan analisis untuk masing-masing hasil produk. Penelitian ini jenis sampah plastik yang menghasilkan gas tertinggi yaitu jenis plastik PET sebesar 45,40% dan jenis plastik yang menghasilkan wax tertinggi yaitu jenis plastik HDPE sebesar 69,91%. Sedangkan komposisi yang menghasilkan gas tertinggi yaitu komposisi dengan ranting 25% dan PET 75% sebesar 71,24% dan komposisi yang menghasilkan wax tertinggi yaitu komposisi dengan ranting 25% dan PS 75% sebesar 61,36%.

  18. Research nuclear reactor RA - Annual Report 1990 with the comparative evaluation for the period 1986-1990; Istrazivacki nuklearni reaktor RA - Izvestaj za 1990. godinu uz uporedni pregled za period 1986 - 1990

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1990, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1990. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  19. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

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

  20. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

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

  1. Komposit Nano TiO2 Dengan PCC, Zeolit atau Karbon Aktif Untuk Menurunkan Total Krom dan Zat Organik Pada Air Limbah Industri Penyamakan Kulit

    Directory of Open Access Journals (Sweden)

    Bumiarto Nugroho Jati

    2012-04-01

    Full Text Available Telah dilakukan penelitian untuk menurunkan total krom dan zat organik pada limbah industri penyamakan kulit dengan menggunakan nano TiO2 yang dikompositkan dengan adsorben karbon aktif, zeolit, dan precipitated calcium carbonate (PCC dalam suatu reaktor fotokatalitik yang disusun secara batch dan dilengkapi dengan 6 buah lampu UV dan magnetic stirrer. Penurunan kadar krom total diukur dengan menggunakan Atomic Absorption Spectro-photometer (AAS dan penurunan zat organik dianalisa dengan menggunakan titrasi permanganatometri. Hasil penelitian menunjukkan pengolahan terbaik untuk penurunan kadar krom total adalah dengan menggunakan komposit TiO2:PCC = 8:2 yang dapat menurunkan total krom hampir 100% pada menit ke-170 dengan konsentrasi awal 214,35 mg/L. Untuk penurunan kadar zat organik, pengolahan terbaik dengan menggunakan komposit TiO2:PCC = 9:1 yang dapat menurunkan kadar zat organik hingga 100% pada menit ke-180. 

  2. Penurunan Logam Timbal (Pb pada Limbah Cair TPA Piyungan Yogyakarta dengan Constructed Wetlands Menggunakan Tumbuhan Eceng Gondok (Eichornia Crassipes

    Directory of Open Access Journals (Sweden)

    Eko Siswoyo

    2015-10-01

    Full Text Available Salah satu permasalahan lingkungan yang ditimbulkan dari adanya lindi di TPA Piyungan yaitu pencemaran pada badan air, sungai dan air tanah. Untuk mengatasi permasalahan ini salah satunya dengan sistem Constructed Wetlands dengan menggunakan tumbuhah eceng gondok. Tujuan dari penelitian ini adalah untuk mengetahui tingkat penurunan konsentrasi Timbal (Pb yang terdapat dalam limbah cair TPA Piyungan dengan Constructed Wetlands menggunakan tumbuhan eceng gondok dan untuk mengetahui seberapa besar kapasitas serapan tumbuhan eceng gondok terhadap kandungan Timbal (Pb dalam limbah cair TPA Piyungan.Dalam penelitian ini digunakan reaktor yang terbuat dari kayu yang dilapisi plastik dengan ukuran 0,5 m x 1,0 m. Setiap reaktor diberi media tanah 5 cm, dan diberi tumbuhan sebanyak 14 buah. Reaktor tersebut diberi perlakuan dengan konsentrasi limbah yang bervariasi (100%, 75%, 50%, 25%, dan 0%, dan waktu pengambilan sampel (0, 3, 6, 9, 12 hari. Dengan menggunakan metode SSA (Spektrofotometri Serapan Atom.Berdasarkan pengujian diperoleh bahwa penurunan logam Pb pada limbah cair TPA Piyungan hari ke- 12, yaitu sebesar 0.0501mg/L pada konsentrasi 100%, 0.0295mg/L pada konsentrasi 75%, 0.0267mg/L pada konsentrasi 50% dan 0.0041 mg/L pada konsentrasi 25%.

  3. Dry reforming of methane with CO{sub 2} at elevated pressures

    Energy Technology Data Exchange (ETDEWEB)

    Milanov, A.; Schwab, E.; Wasserschaff, G. [BASF SE, Ludwigshafen (Germany); Schunk, S. [hte AG, Heidelberg (Germany)

    2013-11-01

    The indirect conversion of natural gas into higher value chemicals and fuels via syngas is superior with regard to efficiency compared to the currently available direct conversion technologies and remains the industrially preferred route. Typically the syngas production route is generally dictated by the H{sub 2}/CO ratio requirements of the downstream synthesis process. Processes such as direct DME synthesis, high-temperature Fischer-Tropsch and acetic acid synthesis require CO rich syngas that is not readily accessible by established technologies like steam methane reforming (SMR) and autothermal reforming of methane (ATR). The CO{sub 2} reforming of methane, also known as dry reforming (DRM), is an attractive alternative technology for the production of CO-rich syngas. This paper gives an overview of the current joint research activities at BASF and hte AG aiming to develop suitable catalysts for CO{sub 2} reforming of methane at elevated pressures with minimized input of process steam. The performance profiles of two newly developed base metal catalysts are presented and discussed. The catalysts exhibit high degrees of methane and CO{sub 2} conversion in combination with an extraordinary coking resistance under high severity process conditions. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-06-15

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

  5. Servicing NPPs in Japan, Korea and Taiwan

    International Nuclear Information System (INIS)

    Bohmann, W.; Poetz, F.

    1991-01-01

    More than 45 comparable orders (for equipment or services ) have been carried out in Japan, Korea and Taiwan by ABB Reaktor since 1982. Recently contracts to deliver inspection and repair equipment for the core baffle former bolts of Japanese NPPs, and in 1990, a contract to clean two steam generators in Korea, together with Pacific Nuclear Services, USA, were won. 2 figs

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

    Directory of Open Access Journals (Sweden)

    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.

  7. Preparation of PtSnCu/C and PtSn/C electrocatalysts and activation by dealloying processes for ethanol electrooxidation; Preparacao de eletrocatalisadores PtSnCu/C e PtSn/C e ativacao por processos de dealloying para aplicacao na oxidacao eletroquuimica do etanol

    Energy Technology Data Exchange (ETDEWEB)

    Crisafulli, Rudy

    2013-06-01

    PtSnCu/C (with different Pt:Sn:Cu atomic ratios) and PtSn/C (50:50) electrocatalysts were prepared by borohydride (BR) and alcohol-reduction (AR) processes using H{sub 2}PtCl{sub 6}.6H{sub 2}O, SnCl{sub 2}.2H{sub 2}O and CuCl{sub 2}.2H{sub 2}O as metal sources, NaBH{sub 4} and ethylene glycol as reducing agents, 2-propanol and ethylene glycol/water as solvents and carbon black as support. In a further step, these electrocatalysts were activated by chemical (CD) and electrochemical (ED) dealloying processes through acid treatment and thin porous coating technique, respectively. These materials were characterized by energy dispersive X-ray, Xray diffraction, transmission electron microscopy, line scan energy dispersive Xray and cyclic voltammetry. Electrochemical studies for ethanol electro-oxidation were performed by cyclic voltammetry, chronoamperometry and in single Direct Ethanol Fuel Cell using Membrane Electrode Assembly (MEA). The anodic effluents were analysed by gas chromatography. The X-ray diffractograms of the as-synthesized electrocatalysts showed the typical face-centered cubic structure (FCC) of platinum and its alloys. After dealloying, the X-ray diffractograms showed that the Pt FCC structure was preserved. The crystallite sizes of the assynthesized electrocatalysts were in the range of <=2 nm to 3 nm and after dealloying there were no significant variations in sizes. The energy dispersive Xray analysis of the as-synthesized electrocatalysts showed a Pt:Sn and Pt:Sn:Cu atomic ratios similar to the nominal values. After chemical and electrochemical dealloying of the electrocatalysts the ranged Pt:Sn and Pt:Sn:Cu atomic ratios showed that Cu and Sn atoms were removed. However, chemical dealloying process proved to be more efficient for removing Cu and electrochemical dealloying for removing Sn. The line scan energy dispersive X-ray analysis showed that acid and electrochemical treatments were efficient to dealloying Cu and/or Sn superficial atoms of

  8. Wpływ czasu napowietrzania na pracę reaktora SBR i SBBR

    Directory of Open Access Journals (Sweden)

    Małgorzata Makowska

    2016-06-01

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

  9. Design of fuel loading for Bohunice V-1 Unit 2 reaktor for fuel cycle No.19

    International Nuclear Information System (INIS)

    Majercik, J.

    1998-01-01

    The report contains description of the design of fuel loading for the fuel cycle No. 19 in the V-1 Bohunice Unit 2 reactor. Input data and computer codes used for the development of the design are shown. The fuel loading is characterized by the assortment of the fuel loaded and by the scheme of re shuffling of assemblies in the core. An evaluation of basic neutronic core parameters as relates to the compliance with safety criteria is a part of the report as well

  10. Põhja-Korea lubas taas jätta tuumaplaanid / Jürgen Tamme

    Index Scriptorium Estoniae

    Tamme, Jürgen

    2007-01-01

    Pekingis toimunud kuuepoolsete desarmeerimiskõneluste tulemusena on Põhja-Korea nõus andma ülevaate riigi tuumarajatistest ning alustama nende likvideerimist. 14. juulil suleti Yongbyoni tuumakeskuse reaktor. Lisa: Tuumavaidlus

  11. ANALISA PENGASUTAN MOTOR INDUKSI 3 FASA 2500 KW SEBAGAI PENGGERAK FAN PADA BAG FILTER

    Directory of Open Access Journals (Sweden)

    Budi Yanto Husodo

    2017-11-01

    Full Text Available Salah satu persoalan yang timbul pada pengoperasian motor induksi adalah arus pengasutan yang tinggi yang nilainya bisa mencapai sepuluh kali arus nominal. Arus pengasutan yang besar ini mengakibatkan penurunan tegangan sesaat (sag pada sistem jaringan. Selain itu juga menyebabkan tingginya pemakaian daya hingga sebesar 1,5 - 2,5 kali daya nominal yang berakibat pada tingginya energi pemakaian pada saat pengasutan. Metode pengasutan diperlukan untuk mengurangi arus pengasutan dan pemakaian energi yang besar tersebut. Pada makalah ini dilakukan perbandingan tiga metode pengasutan motor induksi yaitu berupa autotrafo, reaktor dan rangkaian star-delta. Dengan menggunakan software ETAP, pengujian dilakukan pada motor induksi 6 kV, 279 A, 2500 kW, dan faktor daya sebesar 0,879, sebagai penggerak fan pada bag filter. Hasil simulasi menunjukkan bahwa autotrafo memberikan penurunan arus pengasutan yang paling besar yaitu 73,82% dari arus pengasutan motor tanpa bantuan alat pengasutan. Sedangkan konsumsi energi yang paling kecil didapatkan dengan mengunakan pengasutan reaktor, di mana energi pemakaian berkurang dari 31,102 kWh tanpa pengasutan menjadi 17,676 kWh atau setara dengan 43,17%.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-12-15

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

  13. Nord Stream 2: keeping the head cool

    International Nuclear Information System (INIS)

    Aoun, Marie-Claire

    2016-01-01

    Nord Stream 2 is the name of a project of a pipeline which will transport Russian natural gas into the European Union. The author first presents the context of this project announced during a forum in Saint Petersburg, and signed in september 2015 between Gazprom and several European stakeholders (Eon, BASF, Engie, Shell and OMV). The objective is for Moscow to secure its north-western European market on the long term. Some physical characteristics of the project are evoked, and the European dependence on gas imports is described. The author then discusses how European countries are divided about this project: some support it (like mainly Germany) while some others are fiercely against (Eastern European countries which complain about their loss of transfer revenues, or countries like Bulgaria, Greece and Italy about the loss of an alternative gas corridor). The project also faces legal obstacles related to patrimony separation and access of third parties to the network. Finally, and while mentioning other projects (Nord Stream 1 and South Stream), the author shows that the difficulties and problems faced by this project are a perfect illustration of a fractured European gas sector

  14. Presidential Green Chemistry Challenge: 2005 Greener Reaction Conditions Award

    Science.gov (United States)

    Presidential Green Chemistry Challenge 2005 award winner, BASF, invented a one-component, urethane acrylate oligomer primer system for automobile refinishing that is UV-curable, has VOCs, and is free of diisocyanates.

  15. Mechanical Properties of High Performance Cementitious Grout Masterflow 9200

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.

    The present report describes tests carried out on the high performance grout Masterflow 9200, developed by BASF Construction Chemicals A/S and designed for use in grouted connections of windmill foundations....

  16. Energy and greenhouse balance of photocatalytic CO2 conversion to methanol

    Directory of Open Access Journals (Sweden)

    Muench W.

    2012-10-01

    Full Text Available Within the Leading-Edge Cluster “Forum Organic Electronic”, the research project “Solar2Fuel” funded by the German Ministry of education and research (BMBF (2009 – 2012, EnBW, BASF, Karlsruhe Institute of Technology and Ruprecht-Karls-University of Heidelberg aim to develop a future solar powered CO2 to methanol conversion technology. CO2 from stationary sources such as power plants shall be catalytically converted together with water to a product such as methanol by use of solar irradiation. For this purpose a catalyst shall be developed. EnBW investigates the required boundary conditions to make such a principle interesting with respect to energy and greenhouse gas balance as well as economic evaluations. The assessment of boundary conditions includes the analysis of the whole chain from power generation, CO2 capture and transport, a virtual photocatalytic reactor, the product purification and use in the traffic sector. Most important technical factors of the process such as CO2 conversion efficiency is presented. CO2 capturing and liquefaction are the most energy intensive process steps, CO2 transport in pipeline is highly energy efficient and depending on energy need of the photoconversion step and the product purification, the overall greenhouse gas balance is comparable with the underground storage of the captured CO2.

  17. Leading Players of the Global Petrochemical Industry. Overview of Groups - SWOTs - Benchmarking - Company Profiles and Financials

    International Nuclear Information System (INIS)

    2017-02-01

    This study presents: The medium-term and mega trends of the industry market developments and geographical segments; The competitive landscape and the main corporate rankings; The main conclusions of the report, summarised in 10 analytical slides. Content: 1. Overview: The Sector, Ranking, Performance Analysis; 2. Company Profiles: ExxonMobil, Total, BASF, Dow Chemical, Reliance Industries, Sabic, LyondellBasell, Mitsubishi Chemical, LG Chem, Sumitomo Chemical; 3. Sources; 4. Annexes

  18. INVESTIGATION ON THERMAL-FLOW CHARACTERISTICS OF HTGR CORE USING THERMIX-KONVEK MODULE AND VSOP'94 CODE

    Directory of Open Access Journals (Sweden)

    Sudarmono Sudarmono

    2015-03-01

      Kegagalan sistem pembuangan panas pada reaktor berpendingin air jenis PWR, Three Mile Islands dan reaktor BWR Fukushima Daiichi, menyebabkan masyarakat nuklir mulai memikirkan penggunaan reaktor pembangkit daya jenis temperatur tinggi berpendingin gas (HTGR. Bidang Fisika dan Teknologi Reaktor di Pusat Teknologi Reaktor dan Keselamatan Nuklir (PTRKN mempunyai tugas melaksanakan kegiatan litbang desain konseptual reaktor kogenerasi dengan tingkat daya menengah yang berpendingin gas helium dengan daya 200 MWt. Desain HTGR200K merupakan salah satu sistem pembangkit energi yang memiliki efisiensi energi paling besar, dan tingkat keselamatan inheren yang tinggi dan bersih. Komposisi geometri dan struktur teras didesain agar dapat menghasilkan keluaran pendingin gas helium bertemperatur 950 0C sehingga dapat digunakan untuk produksi hidrogen dan atau unit industri proses lainnya secara kogeneratif. Luaran gas helium bertemperatur sangat tinggi ini akan menimbulkan tegangan termal pada bola bahan bakar yang mengancam integritas sistem pengungkungan produk fisi di dalamnya. Oleh karena itu perlu dilakukan evaluasi karakteristika termal flow untuk menentukan distribusi temperatur bahan bakar bola dan outlet temperatur pendingin gas helium teras HTGR. Hal ini dilakukan dengan menggunakan modul Thermix-Konvek yang terintegrasi dalam program VSOP’94. Geometri teras HTGR dikerjakan dalam modul BIRGIT untuk model teras 2-D (R-Z dengan 5 kanal aliran pebble dalam teras aktif arah radial. Hasil evaluasi menunjukkan bahwa nilai tertinggi dan terendah temperatur yang terdapat pada teras   adalah sebesar 999.3 °C dan 886,5 °C. Demikian pula hasil temperatur tertinggi bahan bakar TRISO dan bahan bakar pebble di dalam teras, yaitu diperoleh sebesar  1510,20°C yang terletak pada lapisan bahan bakar inti UO2, di posisi z= 335.51 cm dan  r=0 cm. Analysis di lakukan pada laju massa aliran pendingin, tekanan dan daya masing-masing sebesar 120 kg/s, 7 Mpa dan 200MWth. Hasil

  19. PENGOLAHAN LIMBAH CAIR INDUSTRI FARMASI FORMULASI DENGAN METODE ANAEROB-AEROB DAN ANAEROB-KOAGULASI

    OpenAIRE

    Farida Crisnaningtyas; Hanny Vistanty

    2016-01-01

    Studi ini membahas mengenai pengolahan limbah cair industri farmasi dalam skala laboratorium dengan menggunakan konsep anaerob-kimia-fisika dan anaerob-aerob. Proses anaerob dilakukan dengan menggunakan reaktor Upflow Anaerobic Sludge Bed reactor (UASBr) pada kisaran OLR (Organic Loading Rate) 0,5 – 2 kg COD/m3hari, yang didahului dengan proses aklimatisasi menggunakan substrat gula. Proses anaerob mampu memberikan efisiensi penurunan COD hingga 74%. Keluaran dari proses anaerob diolah lebih ...

  20. Presidential Green Chemistry Challenge: 2010 Greener Synthetic Pathways Award

    Science.gov (United States)

    Presidential Green Chemistry Challenge 2010 award winners, Dow and BASF, jointly developed a route to make propylene oxide from hydrogen peroxide that eliminates almost all waste and greatly reduces water and energy use.

  1. Adamkus : EU might be willing to negotiate on postponing Ignalina reactor closure

    Index Scriptorium Estoniae

    2008-01-01

    President Valdas Adamkus teatas võimalusest, et EL alustab arutelu Ignalina tuumaelektrijaama sulgemise edasilükkamisest. Uue jaama valmimise aeg pole teada ning praegune reaktor on tänu rootslaste abile turvaline

  2. Karakterisasi Unjuk Kerja Diesel Engine Generator Set Sistem Dual Fuel Solar-Syngas Hasil Gasifikasi Briket Municipal Solid Waste (MSW Secara Langsung

    Directory of Open Access Journals (Sweden)

    Achmad Rizkal

    2017-01-01

    Full Text Available Sejalan dengan semakin banyaknya kebutuhan energi untuk dapat digunakan sebagai bahan bakar maka perlu adanya pengembangan gas biomassa sebagai bahan bakar alternatif pada motor pembakaran dalam maka akan dilakukan penelitian mengenai aplikasi sistem dual fuel gas hasil gasifikasi biomassa municipal solid waste (msw pada sistem downdraft dengan minyak solar pada motor diesel stasioner. Penelitian ini bertujuan untuk mengetahui seberapa besar solar yang tersibtitusi dengan adanya penambahan syngas yang disalurkan secara langsung. Penelitian ini dilakukan secara eksperimental dengan proses pemasukan aliran syngas yang dihasilkan downdraft municipal solid waste (MSW kedalam saluran udara mesin diesel generator set secara langsung menggunakan sistem mixer. Pengujian dilakukan dengan putaran konstan 2000 rpm dengan pembebanan bervariasi dari 200 watt sampai dengan 2000 watt dengan interval 200 watt. Bahwa produksi syngas dari reaktor gasifikasi ditambahkan sistem bypass untuk mengetahui kesesuaian antara reaktor gasifikasi dan mesin generatorset data ṁ syngas yang dibutuhkan mesin diesel, ṁ syngas yang di bypass untuk mendapatkan kesesuaian antara produksi syngas dan yang di bypass.  Data-data yang diukur dari penelitian ini menunjukkan bahwa besar nilai mass flowrate gas syngas yang dibutuhkan mesin diesel pada AFR reaktor gasifier 1,39 sebesar 0,0003748 kg/s. Mass flowrate gas syngas yang di bypass menunjukkan nilai 0 pada saat sistem dijalankan karena seluruh gas syngas masuk kedalam ruang bakar. AFR rata-rata sebesar 14,54 ,Nilai Spesifik fuel consumption (sfc mengalami peningkatan 68% dari kondisi standar single fuel , Nilai efesiensi thermal mengalami kenaikan sebesar 7% dari kondisi single fuel, Nilai daya rata-rata sebesar 2,28kW, Nilai torsi rata-rata sebesar 10,94 N.m. Solar yang tersibtitusi sebesar 48%. Nilai temperatur (coolant, mesin, oil, dan gas buang pada setiap pembebanan mengalami kenaikan.

  3. 77 FR 26450 - Metconazole; Pesticide Tolerances

    Science.gov (United States)

    2012-05-04

    ... (PP 0F7807) by BASF Corporation, 26 Davis Drive, P.O. Box 13528, Research Triangle Park, NC 27709-3528... = 1x........ day. increased liver (M) weights and associated hepatocellular lipid vacuolation (M) and...

  4. Mechanical Properties of High Cementitious Grout (I)

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.

     The present report describes tests carried out on the high performance grout MASTERFLOW 9500, marked WMG 7145 FP, developed by BASF Construction Materials and designed for use in grouted connections of offshore windmill foundations....

  5. Preparation and optical properties of mesoporous TiO2 thin films by a two-step sol-gel technique

    International Nuclear Information System (INIS)

    Kartini, I.; Lu, G.Q.; Meredith, P.; Zhao, X.S.

    2002-01-01

    This paper concerns the preparation of mesoporous titania nanopowders and thin films for use in next generation photoelectrochemical solar cells. We have recently developed a novel method for preparing mesoporous TiO 2 powders using a Two-Step Sol-gel method (TSS). These materials have crystalline domains characteristic of anatase. The first step of the process involves the hydrolysis of titanium isopropoxide in a basic aqueous solution mediated by neutral surfactant. The solid product resulting from Step-1 is then treated in acidified ethanol solution containing a titanium precursor to yield anatase TiO 2 . The resultant powder exhibits a high surface area and large pore volume with uniform mesopores. Slurries made from the resultant powder of Steps 1 and 2 have been used to produce thin titania films on glass slides. The optical and structural properties of these films have been compared to the films made of a commercial titania (Degussa P25, BASF). We will discuss these properties with respect to the possible use of such mesoporous titania films as the wide band gap semiconductor in dye-sensitized nanocrystalline TiO 2 solar cells

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-12-15

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

  7. 78 FR 23246 - Underground Injection Control Program; Hazardous Waste Injection Restrictions; Petition for...

    Science.gov (United States)

    2013-04-18

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9804-8] Underground Injection Control Program; Hazardous Waste Injection Restrictions; Petition for Exemption--Class I Hazardous Waste Injection; BASF... exemption to the land disposal Restrictions, under the 1984 Hazardous and Solid Waste [[Page 23247...

  8. Johann Friedrich Wilhelm Adolf von Baeyer

    Indian Academy of Sciences (India)

    IAS Admin

    ... did groundbreaking research in sixteen different areas of organic chemistry, such ... The methodology they used may seem to be primitive now, but that was a .... BASF chemical company by which he greatly contributed to the development of ...

  9. Mobile medium-voltage switching system. Temporary standby power supply in record time; Mobile Mittelspannungsschaltanlage. Vorlaeufige Wiederversorgung in Rekordzeit

    Energy Technology Data Exchange (ETDEWEB)

    Thiery, Matthias; Schwarz, Stefan [Siemens AG, Mannheim (Germany); Wingerter, Dieter [BASF SE, Ludwigshafen (Germany); Doering, Holger [B. Goebel und Sohn GmbH, Asschaffenburg (Germany). Fahrzeugbau

    2011-02-28

    BASF SE Ludwigshafen operates more than 100 medium-voltage switching stations for power supply to its plants. The complexity of the production plants and production method make it necessary to have immediate standby power supply in case of interruption of a medium-voltage switching station. For this purpose, a transportable emergency container was acquired that contains a medium-voltage switching system. Power can be supplied at very short notice, simply by plugging the necessary cable connections. No cranes or other tools are required for installation. The emergency container is designed for use at varying voltage levels and can be transported by road to other BASF sites in Europe. The switching station is a gas-insulated medium-voltage switching station 8DA10 by Siemens, designed for operating voltages of 6, 10, 20, and 35 kW.

  10. Quantitative Determination of Engine Water Ingestion.

    Science.gov (United States)

    1986-12-01

    4II- lIII.s;I.I. iN [ I I.S( NIC ID) LINIA.) 4 5v1fil I [:,SS(I~r. III.G’I.141 ) lS;; NE141I))=NI IF" (i’* IIw JI)).I.’".N2) ESINE [LI)-1NZ %t...Tulsa, OK 74150 Be. hMr. Ronald Cam Allied Pilot Association BASF Wyandotte CorporationEquipment Evaluation Comm.":" .O.Box 5241609 Biddle Avenue P.O

  11. 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

  12. NEUTRONICS ANALYSIS ON MINI TEST FUEL IN THE RSG-GAS CORE

    Directory of Open Access Journals (Sweden)

    Tukiran Surbakti

    2016-03-01

    Full Text Available Abstract NEUTRONICS ANALYSIS ON MINI TEST FUEL IN THE RSG-GAS CORE. Research of UMo fuel for research reactor has been developing  right now. The fuel of  research reactor used is uranium low enrichment with high density. For supporting the development of fuel, an assessment of mini fuel in the RSG-GAS core was performed. The mini fuel are U7Mo-Al and U6Zr-Al with densitis of 7.0gU/cc and 5.2 gU/cc, respectively. The size of both fuel are the same namely 630x70.75x1.30 mm were inserted to the 3 plates of dummy fuel. Before being irradiated in the core, a calculation for safety analysis  from neutronics and thermohydrolics aspects were required. However, in this paper will discuss safety analysis of the U7Mo-Al and U6Zr-Al mini fuels from neutronic point of view.  The calculation was done using WIMSD-5B and Batan-3DIFF code. The result showed that both of the mini fuels could be irradiated in the RSG-GAS core with burn up less than 70 % within 12 cycles of operation without over limiting the safety margin. Power density of U7Mo-Al mini fuel bigger than U6Zr-Al fuel.   Key words: mini fuel, neutronics analysis, reactor core, safety analysis   Abstrak ANALISIS NEUTRONIK ELEMEN BAKAR UJI MINI DI TERAS RSG-GAS. Penelitian tentang bahan bakar UMo untuk reaktor riset terus berkembang saat ini. Bahan bakar reaktor riset yang digunakan adalah uranium pengkayaan rendah namun densitas tinggi.  Untuk mendukung pengembangan bahan bakar dilakukan uji elemen bakar mini di teras reakror RSG-GAS dengan tujuan menentukan jumlah siklus di dalam teras sehingga tercapai fraksi bakar maksimum. Bahan bakar yang diuji adalah U7Mo-Al dengan densitas 7,0 gU/cc dan U6Zr-Al densitas 5,2 gU/cc. Ukuran kedua bahan bakar uji tersebut adalah sama 630x70,75x1,30 mm dimasukkan masing masing kedalam 3 pelat dummy bahan bakar. Sebelum diiradiasi ke dalam teras reaktor maka perlu dilakukan perhitungan keselamatan baik secara neutronik maupun termohidrolik. Dalam makalah ini

  13. DESAIN KONSEP TANGKI PENAMPUNG BAHAN BAKAR PASSIVE COMPACT MOLTEN SALT REACTOR

    Directory of Open Access Journals (Sweden)

    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

  14. Gazprom pani Euroopas jala tugevalt maha / Krister Paris

    Index Scriptorium Estoniae

    Paris, Krister, 1977-

    2006-01-01

    Venemaa ja Saksamaa suurkokkuleppe kohaselt kasvab Gazpromi osalus BASF-i energiaüksusega loodud ühisfirmas Wingas ligi pooleni, tugevdades Vene kontserni haaret Euroopa tarneturul. Kantsler Angela Merkeli ja president Vladimir Putini kohtumine Tomskis. Lisa: Venemaal endal ei jagu energiat

  15. Eesti Energia valib Ameerikas tuumajaamale reaktoreid / Andres Reimer

    Index Scriptorium Estoniae

    Reimer, Andres

    2009-01-01

    Eesti Energia liitus rahvusvahelise tuumareaktoriprojektiga IRIS, projekti eesmärk on luua lihtsa konstruktsiooniga, ohutu ja suhteliselt odav reaktor. Jürgen Ligi sõnul saab Eesti oma IRIS-tüüpi tuumajaama juba 2019. aastal. Joonis: Potentsiaalne tuumajaam

  16. Irradiation effects on Zr-2.5Nb in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Song, C., E-mail: Carol.Song@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, 'High Power Channel-type Reactor') reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr- 2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge. (author)

  17. Na velikosti nezáleží - je to fraktální

    Czech Academy of Sciences Publication Activity Database

    Řípa, Milan

    2014-01-01

    Roč. 7, červen (2014) Institutional support: RVO:61389021 Keywords : fusion * tokamak * fractal * turbulence * Bohm diffusion Subject RIV: BL - Plasma and Gas Discharge Physics http://3pol.cz/1614-na-velikosti-nezalezi-je-to-fraktalni-aneb-slunecni-termojaderny-reaktor

  18. ANALISA PENGARUH SUHU AWAL PELAT PANAS PADA PROSES QUENCHING CELAH SEMPIT REKTANGULAR

    Directory of Open Access Journals (Sweden)

    M. Hadi Kusuma

    2015-03-01

    Full Text Available Pemahaman terhadap manajemen termal apabila terjadi suatu kecelakaan parah reaktor nuklir seperti melelehnya bahan bakar dan teras reaktor, menjadi prioritas utama untuk menjaga integritas bejana tekan reaktor. Dengan demikian hasil lelehan bahan bakar dan teras reaktor (debris tidak keluar dari bejana tekan reaktor dan mengakibatkan dampak lain yang lebih besar ke lingkungan. Salah satu cara yang dilakukan untuk menjaga integritas bejana tekan reaktor adalah dengan melakukan pendinginan terhadap panas berlebih yang dihasilkan akibat dari kecelakaan tersebut. Untuk mempelajari dan mendapatkan pemahaman mengenai hal tersebut, maka dilakukan penelitian mengenai pengaruh suhu awal pelat panas dalam proses quenching (pendinginan secara tiba-tiba celah sempit rektangular. Penelitian difokuskan pada penentuan suhu rewetting dari pendinginan pelat panas dengan suhu awal pelat 220 0C, 400 0C, dan 600 0C dengan laju aliran air pendingin 0,2 liter/detik. Eksperimen dilakukan dengan menginjeksikan air pada laju aliran 0,2 liter/detik pada suhu air pendingin 85 0C ke dalam celah sempit rektangular. Data hasil pengukuran digunakan untuk mengetahui suhu rewetting yang terjadi pada pendinginan pelat panas tersebut. Tujuannya adalah untuk memahami pengaruh suhu awal pelat panas terhadap rewetting pada proses quenching di celah sempit rektangular. Hasil yang diperoleh menunjukkan bahwa titik rewetting pada pendinginan pelat panas 220 0C, 400 0C, dan 600 0C terjadi pada suhu rewetting yang berbeda-beda. Pada suhu awal pelat panas 220 0C, suhu rewetting terjadi pada 220 0C yaitu langsung ketika air dilewatkan melalui celah sempit rektangular. Pada suhu awal pelat panas 400 0C, suhu rewetting terjadi pada 379,51 0C. Dan pada suhu awal pelat panas 600 0C, suhu rewetting terjadi pada 426,63 0C. Perbedaan suhu awal pelat panas yang sangat signifikan menyebabkan terjadinya perubahan sifat fisik benda uji, berbedanya rejim pendidihan yang dialami oleh fluida yang

  19. An inter-laboratory stability study of roll-to-roll coated flexible polymer solar modules

    DEFF Research Database (Denmark)

    Gevorgyan, Suren; Medford, Andrew James; Bundgaard, Eva

    2011-01-01

    A large number of flexible polymer solar modules comprising 16 serially connected individual cells was prepared at the experimental workshop at Risø DTU. The photoactive layer was prepared from several varieties of P3HT (Merck, Plextronics, BASF and Risø DTU) and two varieties of ZnO (nanoparticu......A large number of flexible polymer solar modules comprising 16 serially connected individual cells was prepared at the experimental workshop at Risø DTU. The photoactive layer was prepared from several varieties of P3HT (Merck, Plextronics, BASF and Risø DTU) and two varieties of Zn......O (nanoparticulate, thin film) were employed as electron transport layers. The devices were all tested at Risø DTU and the functional devices were subjected to an inter-laboratory study involving the performance and the stability of modules over time in the dark, under light soaking and outdoor conditions. 24...

  20. Radiological protection in nucleus reactor; Perlindungan radiologi di reaktor nukleus

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

    The chapter briefly discussed the following subjects: radiological protection problems of reactor 1. in operation 2. types of reactor i.e. power reactors, research reactors, etc. 3. during maintenance and installation of fuels. 4. nuclear fuels.

  1. Pengolahan Limbah Rumah Makan dengan Proses Biofilter Aerobik

    Directory of Open Access Journals (Sweden)

    Laily Zoraya Zahra

    2015-03-01

    Full Text Available Berkembangnya rumah makan/restoran yang semakin pesat dapat dipastikan akan turut menambah buangan air limbah domestik dengan kadar organik yang tinggi dalam jumlah yang tidak sedikit yang dibuang ke badan air.Tingginya kadar organik dalam limbah domestik rumah makan akan menyebabkan aroma yang tidak sedap jika tidak ada pengolahan terlebih dahulu, maka pengolahan yang dapat digunakan untuk mengolah air limbah rumah makan tersebut adalah proses biofilter aerobik. Penelitian dilakukan dengan proses biofilter aerobik dengan aliran downflow dan menggunakan sistem intermitten.Variabel dalam penelitian ini adalah media biofilter berupa kerikil dan batu alam serta Hydraulic Retention Time (HRT 8 jam. Parameter pencemar yang diukur efisiensinya adalah BOD, COD, dan TSS. Besarnya penyisihan parameter BOD, COD dan TSS dengan menggunakan biofilter aerob berturut-turut mencapai 94,83%, 92,95%, dan 95%. Reaktor paling baik dalam mengolah air limbah adalah reaktor biofilter dengan media kerikil pada HRT 8 jam.

  2. The Quality Standard 50-SG-Q8 Application On Research And Development Activities In P2TRR

    International Nuclear Information System (INIS)

    Nababan, N.; Rofei, A.

    2000-01-01

    Utilization of nuclear reactor installation should reference safety, Environment, and instalation requrement, and shoul incorporate user requirement. The requirement are adequately addressed in the IAEA standar No. 50-sg-Q8 for R and D work in nuclear instalation. A study to this standar has been carried out and it is found that there are three important factor of QA methodologi necessary to be aplied for R and D activities. They are management responsibilities, performance of the R and D works, and carrying out assesment over the R and D project. The R and D activities performing in Centre for Recearch Reaktor Technology Development (P2TRR) shoul meet the requirement in the R and D program assigned by Batan management, Such as Strastegy and Policy (jakarta), Strategic Plan (Restra), and Five-Year Plan. A study to this program also has been carried out and it is found that QA methodologies are necessary to be aplied, Especially during the data gathering activities, and its contribution to the safety function or as input to actual nuclear reactor installation or systems

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-11-15

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

  4. 78 FR 41853 - Safety Advisory Guidance: Heating Rail Tank Cars To Prepare Hazardous Material for Unloading or...

    Science.gov (United States)

    2013-07-12

    ... rail tank car due to chemical self-reaction and expansion of the toluene diisocyanate matter wastes. On...: Cheryl West Freeman, Division of Engineering and Research, Pipeline and Hazardous Materials Safety... catastrophically ruptured at a transfer station at the BASF Corporation chemical facility in Freeport, Texas. The...

  5. Viscosity overshoot followed by steady state measured in uni-axial elongation of LDPE. Ole Hassager, Henrik Koblitz Rasmussen, Anders Bach and Jens Kromann Nielsen

    DEFF Research Database (Denmark)

    Rasmussen, Henrik Koblitz; Hassager, Ole; Bach, Anders

    2004-01-01

    The transient (e.g. start up of) elongational viscosity of three low-density polyethylene (LDPE) melts (BASF Lupolen 1810H, 1840D and 3020D) was measured using a filament stretching rheometer (FSR) capable of measuring at elevated temperatures. The transient uni-axial elongational viscosity showe...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

    During 1976 the Ra reactor was operating for about 30% shorter period than usual. The reason were extraordinary repair activities within regular and investment maintenance as well as repair of failures caused by neglected maintenance during previous 6 years. Delay was caused by unavailability of fuel (2% enriched fuel elements are spent) and the new 80% enriched fuel demanded experimental and theoretical analyses before being introduced into the core. Safety analyses concerned with using 80% enriched fuel both experimental and theoretical were successfully fulfilled. The December 1976 successful experimental campaign can be marked as end of the 17 years period of using 2% enriched fuel and start of the new period of using highly enriched fuel. This is significant not only for the reactor itself but for the users, because it would result in increase of neutron flux by 50% with the increase of costs by only 4%. Demand was submitted for obtaining the final license for transition operating regime with highly enriched fuel which would save at least 2 200 000 dinars. This will enable reactor operation in 1977 and later on, without interruption by 'critical' and other experiments related to new highly enriched fuel. A high number of repair and other urgent activities were fulfilled in order to enable safe operation. Some of these activities were done never before and some were neglected during past 6 years. The most important tasks were: purchase of Al tubes made of special alloy, fabrication and mounting of the fuel channel; overall investigation of reactor vessel leakage; repair of the heavy water pump; exchange of two vertical channels. basic equipment for construction of emergency cooling system was purchased. Hot cells are equipped for independent utilisation. [Serbo-Croat] Reaktor RA je u 1976. godini radio za oko 30% krace vreme od uobicajenog. Razlog su bill izuzetno veliki obim remontnih i drugih radova u okviru tekuceg i investicionog odrzavanja, kao i krupnih

  7. Red Emitting Phenyl-Polysiloxane Based Scintillators for Neutron Detection

    International Nuclear Information System (INIS)

    Dalla Palma, Matteo; Quaranta, Alberto; Marchi, Tommaso; Gramegna, Fabiana; Cinausero, Marco; Carturan, Sara; Collazuol, Gianmaria

    2013-06-01

    In this work, the performances of new red emitting phenyl- substituted polysiloxane based scintillators are described. Three dyes were dispersed in a phenyl-polysiloxane matrix in order to shift the scintillation wavelength towards the red part of the visible spectrum. PPO, Lumogen Violet (BASF) and Lumogen Red (BASF) were mixed to the starting resins with different wt. % and the analysis of the different samples was performed by means of fluorescence measurements. The scintillation yield to alpha particles at the different dye ratios was monitored by detecting either the full spectrum or the red part of the emitted light. Finally, thin red scintillators with selected compositions were coupled to Avalanche Photodiode sensors, which are usually characterized by higher efficiency in the red part of the spectrum. An increased light output of about 17% has been obtained comparing the red scintillators to standard blue emitting systems. Preliminary results on the detection of fast neutrons with the APD-red scintillator system are also presented. (authors)

  8. Simulation of atmosphere stratification in the HDR test facility with the CONTAIN code

    International Nuclear Information System (INIS)

    Skerlavaj, A.; Mavko, B.; Kljenak, I.

    2001-01-01

    The test E11.2 'Hydrogen distribution in loop flow geometry', which was performed in the Heissdampf Reaktor containment test facility in Germany, was simulated with the CONTAIN computer code. The predicted pressure history and thermal stratification are in relatively good agreement with the measurements. The compositional stratification within the containment was qualitatively well predicted, although the degree of the stratification in the dome area was slightly underestimated. The analysis of simulation results enabled a better understanding of the physical phenomena during the test.(author)

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1964-07-01

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

  10. RA reactor operation and maintenance in 1992, Part 1; Deo 1 - Pogon i odrzavanje nuklearnog reaktoro RA u 1992. Godini

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-12-01

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems. [Serbo-Croat] U toku 1992 godine poslovi u okviru projekta 'Istrazivacki nuklearni reaktor RA' obavljani su u skladu sa programom i planom rada. Osnovne aktivnosti na kojima je radjeno odnosile su se na revitalizaciju reaktora RA, kao i na odrzavanje opreme. U ovom periodu reaktor nije bio u pogonu. Svo osoblje je bilo angazovano na poslovima rekonstrukcije i modernizacije postojecih i dogradnje novih reaktorskih sistema, na odrzavanju opreme a deo tehnickog osoblja je bio obucavan za vrsenje odgovarajucih poslova u pogonu i odrzavanju opreme.

  11. Validation of CESAR Thermal-hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments

    Science.gov (United States)

    Tregoures, Nicolas; Bandini, Giacomino; Foucher, Laurent; Fleurot, Joëlle; Meloni, Paride

    The ASTEC V1 system code is being jointly developed by the French Institut de Radioprotection et Sûreté Nucléaire (IRSN) and the German Gesellschaft für Anlagen und ReaktorSicherheit (GRS) to address severe accident sequences in a nuclear power plant. Thermal-hydraulics in primary and secondary system is addressed by the CESAR module. The aim of this paper is to present the validation of the CESAR module, from the ASTEC V1.2 version, on the basis of well instrumented and qualified integral experiments carried out in the BETHSY facility (CEA, France), which simulates a French 900 MWe PWR reactor. Three tests have been thoroughly investigated with CESAR: the loss of coolant 9.1b test (OECD ISP N° 27), the loss of feedwater 5.2e test, and the multiple steam generator tube rupture 4.3b test. In the present paper, the results of the code for the three analyzed tests are presented in comparison with the experimental data. The thermal-hydraulic behavior of the BETHSY facility during the transient phase is well reproduced by CESAR: the occurrence of major events and the time evolution of main thermal-hydraulic parameters of both primary and secondary circuits are well predicted.

  12. Wingas in natural gas supply in Belgium

    International Nuclear Information System (INIS)

    2003-01-01

    Recently Wingas has become active in the transport and supply of natural gas in Belgium and succeeded in entering contracts for the supply of natural gas which cover 6% of the Belgian market. Wingas is a German-Russian joint venture between BASF-daughter Wintershall and OAO Gasprom [nl

  13. Calcium montmorillonite clay for the reduction of aflatoxin residues in milk and dairy products

    Science.gov (United States)

    In this study, dairy cows were treated with calcium montmorillonite clay (NovaSil Plus (NSP); BASF Corp., Ludwigshaven, Germany) in a replicated 5x5 Latin square design. The primary objectives were to determine if milk composition was altered following ingestion of NSP, and to investigate the abili...

  14. Mechanical Properties of High Performance Cementitious Grout (II)

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.

    The present report is an update of the report “Mechanical Properties of High Performance Cementitious Grout (I)” [1] and describes tests carried out on the high performance grout MASTERFLOW 9500, marked “WMG 7145 FP”, developed by BASF Construction Chemicals A/S and designed for use in grouted...

  15. Viscosity overshoot in the start-up of uniaxial elongation of low density polyethylene melts

    DEFF Research Database (Denmark)

    Rasmussen, Henrik K.; Nielsen, Jens Kromann; Bach, Anders

    2005-01-01

    The transient uniaxial elongational viscosity of BASF Lupolen 1840D and 3020D melts has been measured on a filament stretch rheometer up to Hencky strains of 6-7. The elongational viscosity of both melts was measured at 130 degrees C within a broad range of elongational rates. At high elongation ...

  16. PENENTUAN KOEFISIEN DISPERSI ATMOSFERIK UNTUK ANALISIS KECELAKAAN REAKTOR PWR DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Pande Made Udiyani

    2015-03-01

    Full Text Available Atmosfer merupakan pathway penting pada perpindahan radionuklida yang lepas dari Pembangkit Listrik Tenaga Nuklir (PLTN ke lingkungan dan manusia. Penerimaan dosis pada lingkungan dan manusia dipengaruhi oleh sourceterm dan kondisi tapak PLTN. Untuk mengetahui penerimaan dosis lingkungan untuk PLTN di Indonesia, maka diperlukan nilai koefisien dispersi untuk tapak potensial yang dipilih. Model perhitungan dalam penelitian ini menggunakan model yang diterapkan pada paket program pada modul ATMOS dan CONCERN dari PC-Cosyma yaitu model perhitungan segmented plume model. Perhitungan dilakukan untuk PLTN tipe PWR kapasitas 1000 MWe berbahan bakar UO2, postulasi kejadian untuk kecelakaan DBA, kondisi tapak kasar, untuk 6 tapak contoh tapak Semenanjung Muria, Pesisir Banten, dan tapak yang didominasi oleh stabilitas cuaca C,D,E, dan F. Koefisien dispersi dihitung untuk 8 kelompok nuklida produk fisi yang lepas dari PLTN yaitu: kelompok gas mulia, lantanida, logam mulia, halogen, logam alkali, tellurium, cerium, dan kelompok stronsium & barium. Perhitungan input menggunakan paket program ORIGEN-2 dan Arc View untuk penyiapan input perhitungan. Hasil pemetaan untuk parameter dispersi maksimum rerata diperoleh pada jarak radius 800 m dari sumber lepasan untuk nuklida dari kelompok logam mulia, logam alkali dan kelompok nuklida cerium. Parameter dispersi untuk Tapak Muria maksimum 1,53E-04 s/m3, Tapak Serang adalah 1,40E-03 s/m3, tapak dengan stabilitas C: 1,72E-04 s/m3, stabilitas D: 1,40E-04 s/m3, Stabilitas E: 1,07E-04 s/m3, dan tapak dengan stabilitas F : 2,14E-05 s/m3. Kata kunci: koefisien dispersi, atmosferik, PWR, kecelakaan, Indonesia   The atmosphere is an important pathway in the migration of radionuclides transport from the Nuclear Power Plant (NPP to the environment and humans. The dose accepted in the environment and humans is influenced by the sourceterm and NPP siting condition. Distribution of radionuclides in the atmosphere is determined

  17. Comparative study of the break in process of post doped and sol–gel high temperature proton exchange membrane fuel cells

    DEFF Research Database (Denmark)

    Vang, Jakob Rabjerg; Andreasen, Søren Juhl; Araya, Samuel Simon

    2014-01-01

    In this paper six High Temperature PEM (HTPEM) MEAs from two manufacturers have been tested. The MEAs are three Dapozol 77 from Danish Power Systems (DPS) with varying electrode composition and two Celtec P2100 and one Celtec P1000 from BASF. The break in process of the MEAs has been monitored us...

  18. Pengaruh Aerasi dan Sumber Nutrien terhadap Kemampuan Alga Filum Chlorophyta dalam Menyerap Karbon (Carbon Sink untuk Mengurangi Emisi CO2 di Kawasan Perkotaan

    Directory of Open Access Journals (Sweden)

    Lancur Setoaji

    2013-09-01

    Full Text Available Penelitian terkait mitigasi pemanasan global, khususnya dalam penyerapan karbon dioksida (CO2, menjadi fokus utama di kalangan ilmuwan dunia. Secara alamiah, karbon dioksida dapat diserap oleh tumbuhan hijau, laut, karbonasi batuan kapur, dan alga. Pigmen hijau dalam alga atau klorofil dapat menyerap karbon dioksida dalam proses fotosintesis. Alga memiliki pertumbuhan yang sangat cepat sehingga cocok digunakan sebagai carbon sink. Penelitian terkait carbon sink ini bertujuan untuk menentukan kemampuan rata-rata serapan CO2 oleh alga di kawasan perkotaan dan menentukan pengaruh aerasi dan variasi sumber N terhadap pertumbuhan dan perkembangan alga. Penelitian ini dilakukan dalam skala laboratorium menggunakan reaktor dengan proses batch. Sampel alga yang digunakan didapatkan dari hasil pengembangbiakan yang bersumber dari perairan di kawasan perkotaan. Penelitian ini menggunakan dua variabel uji, yaitu aerasi dan sumber nutrien. Jumlah karbon dioksida yang diserap didapatkan dari perbandingan stoikiometri pada reaksi fotosintesis.  Berdasarkan perbandingan stoikiometri tersebut diketahui bahwa 1 gram sel alga yang terbentuk sebanding dengan 1,92 gram CO2 yang diserap. Dari hasil penelitian, alga dengan penambahan pupuk urea dapat menyerap 4,87 mg CO2/hari dalam kondisi tanpa aerasi atau 3,84 mg CO2/hari dengan aerasi. Sedangkan alga dengan penambahan pupuk NPK dapat menyerap 3,61 mg CO2/hari dalam kondisi tanpa aerasi atau 3,01 mg CO2/hari dengan aerasi.

  19. Corrosion mapping in pipelines

    International Nuclear Information System (INIS)

    Zscherpel, U.; Alekseychuk, O.; Bellon, C.; Ewert, U.; Rost, P.; Schmid, M.

    2002-01-01

    In a joint research project, BASF AG and BAM analyzed the state of the art of tangential radiography of pipes and developed more efficient methods of evaluation. Various PC applications were developed and tested: 1. A program for routine evaluation of digital radiographic images. 2. 3D simulation of the tangential projection of pipes for common radiation sources and various different detectors. 3. Preliminary work on combined evaluation of digital projections and wall thickness changes in radiation direction resulted in a new manner of image display, i.e. the so-called 'corrosion mapping', in which the wall thickness is displayed as a 2D picture above the pipe surface [de

  20. Globalising Synthetic Nitrogen: The Interwar Inauguration of a New Industry.

    Science.gov (United States)

    Travis, Anthony S

    2017-02-01

    The most spectacular development in industrial chemistry during the early twentieth century concerned the capture of atmospheric nitrogen by the Haber-Bosch high-pressure ammonia process at the German chemical enterprise Badische Anilin- & Soda-Fabrik (BASF), of Ludwigshafen. This firm, confident that its complex process could not be readily imitated, set out to dominate the global nitrogen fertiliser market. The response was the emergence of rival high-pressure ammonia processes in Western Europe, the United States, and Japan during the 1920s. This article is an historical appreciation of the settings in which several countries, often driven by concerns over national security, were encouraged to develop and adopt non-BASF high-pressure nitrogen capture technologies. Moreover, synthetic ammonia was at the forefront of large-scale strategic self-sufficiency and state sponsored programmes in three countries - Italy, Russia, and Japan - at the very same time when the newer technologies became available. As a result, the chemical industries of these nations, under the influences of fascism, communism, and colonial modernisation projects, began moving into the top ranks.

  1. Degradasi Zat Warna Pada Limbah Cair Industri Tekstil Dengan Metode Fotokatalitik Menggunakan Nanokomposit Tio2 – Zeolit

    Directory of Open Access Journals (Sweden)

    Siti Naimah

    2014-10-01

    Full Text Available Telah dilakukan penelitian degradasi zat warna pada limbah cair industri tekstil menggunakan metode fotokatalitik dengan penambahan nanokomposit TiO2 - zeolit. Tujuan penelitian ini untuk mengetahui efektifitas kemampuan nanokomposit dalam mendegradasi zat warna serta parameter-parameter yang ditetapkan dalam Peraturan Pemerintah Nomor 82 Tahun 2001 tentang pengelolaan kualitas air dan pengendalian pencemaran air. Zeolit alam diaktivasi terlebih dahulu sebelum dikompositkan dengan TiO2. Perbandingan TiO2 : zeolit yang digunakan pada pembuatan nanokomposit adalah 100:0, 20:80, 40:60, 50:50, 60:40, dan 0:100. Percobaan pendahuluan dilakukan dengan menggunakan limbah cair tekstil buatan yang dibuat dari pewarna Synolon yellow S- G6LS (untuk warna kuning dan B/Blue R 150% special (untuk warna biru, sedangkan limbah cair industri tekstil diambil dari salah satu industri di Bogor. Waktu degradasi zat warna dilakukan dalam reaktor fotokatalitik selama 180 menit. Pada perbandingan TiO2 : zeolit 40:60 didapatkan degradasi zat warna tekstil buatan berwarna kuning maksimal adalah 99,9 % dan zat warna tekstil buatan berwarna biru maksimal 99,8%. Analisis warna menggunakan spektrofotometer dan HPLC. Nanokomposit TiO2 : zeolit 40 : 60 merupakan perbandingan optimal sehingga digunakan pada uji coba limbah cair industri tekstil. Degradasi maksimal warna kuning dengan pengolahan fotokatalitik yang ditambahkan nanokomposit pada limbah cair industri tekstil sebesar 98,4%, sedangkan untuk parameter uji zat organik, TSS, TDS, BOD, COD, dan lemak/minyak diperoleh nilai di bawah baku mutu yang dipersyaratkan. 

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

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

  3. Crystal structure of bis{μ2-2,2′-[(4,10-dimethyl-1,4,7,10-tetraazacyclododecane-1,7-diylbis(methylene]bis(4-oxo-4H-pyran-3-olato}dicobaltcalcium bis(perchlorate 1.36-hydrate

    Directory of Open Access Journals (Sweden)

    Patrizia Rossi

    2017-12-01

    Full Text Available The title compound, [CaCo2(C22H30N4O62](ClO42·1.36H2O or {Ca[Co(H–2L1]22ClO4·1.36H2O {where L1 is 4,10-bis[(3-hydroxy-4-pyron-2-ylmethyl]-1,7-dimethyl-1,4,7,10-tetraazacyclododecane}, is a trinuclear complex whose asymmetric unit comprises a quarter of the {Ca[Co(H–2L1]2}2+ trinuclear complex, half of a perchlorate ion and 0.34-water molecules. In the neutral [Co(H–2L1] moiety, the cobalt ion is hexacoordinated in a trigonal–prismatic fashion by the surrounding N4O2 donor set. A Ca2+ cation holds together two neutral [Co(H–2L1] moieties and is octacoordinated in a distorted trigonal–dodecahedral fashion by the surrounding O atoms belonging to the deprotonated oxide and carbonyl groups of two [Co(H–2L1] units. The coordination of the CoII cation preorganizes L1 and an electron-rich area forms, which is able to host hard metal ions. The comparison between the present structure and the previously published ones suggests a high versatility of this ligand; indeed, hard metal ions with different nature and dimensions lead to complexes having different stoichiometry (mono- and dinuclear monomers and trinuclear dimers or even a polymeric structure. The heterotrinuclear CoII–CaII–CoII complexes are connected in three dimensions via weak C—H...O hydrogen bonds, which are also responsible for the interactions with the perchlorate anions and the lattice water molecules. The perchlorate anion is disordered about a twofold rotation axis and was refined giving the two positions a fixed occupancy factor of 0.5. The crystal studied was refined as a two-component inversion twin [BASF parameter = 0.14 (4].

  4. Structure of the mercury(II mixed-halide (Br/Cl complex of 2,2′-(5-tert-butyl-1,3-phenylenebis(1-pentyl-1H-benzo[d]imidazole

    Directory of Open Access Journals (Sweden)

    Varsha Rani

    2017-03-01

    Full Text Available The mercury(II complex of 2,2′-(5-tert-butyl-1,3-phenylenebis(1-pentyl-1H-benzimidazole, namely catena-poly[[dihalogenidomercury(II]-μ-2,2′-(5-tert-butyl-1,3-phenylenebis(1-pentyl-1H-benzimidazole-κ2N3:N3′], [HgBr1.52Cl0.48(C34H42N4], 2, has a polymeric structure bridging via the N atoms from the benzimidazole moieties of the ligand. The compound crystallizes in the orthorhombic space group Pca21 and is a racemic twin [BASF = 0.402 (9]. The geometry around the HgII atom is distorted tetrahedral, with the HgII atom coordinated to two N atoms, one Br atom, and a fourth coordination site is occupied by a mixed halide (Br/Cl. For the two ligands in the asymmetric unit, there is disorder with one of the two tert-butyl groups and benzimidazole moieties showing twofold disorder, with occupancy factors of 0.57 (2:0.43 (2 for the tert-butyl group and 0.73 (3:0.27 (3 for the benzimidazole group. In addition, there is threefold disorder for two of the four n-pentyl groups, with occupancy factors of 0.669 (4:0.177 (4:0.154 (4 and 0.662 (4:0.224 (4:0.154 (4, respectively. The molecules form a one-dimensional helical polymer propagating in the b-axis direction. The helices are held together by intra-strand C—H...Br and C—H...Cl interactions. Each strand is further linked by inter-strand C—H...Br and C—H...Cl interactions. In addition, there are weak C—H...N inter-strand interactions which further stabilize the structural arrangement.

  5. PENURUNAN COD, TSS DAN TOTAL FOSFAT PADA SEPTIC TANK LIMBAH MATARAM CITRA SEMBADA CATERING DENGAN MENGGUNAKAN WASTEWATER GARDEN (Degradation of COD, TSS and Total Phosphate in Septic Tank Wastewater of Mataram Citra Sembada Catering Using Wastewater

    Directory of Open Access Journals (Sweden)

    Dradjat Suhardjo

    2008-07-01

    Full Text Available ABSTRAK  Sumber limbah berasal dari septictank industri restauran (catering Citra Sembada Catering, termasuk dalam kategori limbah domestik. Limbah tersebut banyak mengandung komponen yang tidak diinginkan bila dibuang ke badan air. Konsentrasi limbah yang masih di atas baku mutu, di antaranya akan memunculkan masalah pencemaran. Reaktor Wastewater Garden yang menggunakan krikil (0,5Cm-1cm dan 6 jenis tanaman yaitu : melati air (Echinodoras paleafias, Cyperus (Cyperus, Futoi (Hippochaetes lymnenalis, Pisang air (Typhonodorum indleyanum, Pickerel rush (Pontedoria cordata, Cattail (Typha latifulia. Penelitian ini bertujuan untuk mengetahui tingkat efektivitas reaktor Wastewater Garden, apabila digunakan untuk menurunkan konsentrasi Chemical Oxygen Demand (COD, Total Suspended Solid (TSS dan Fosfat Total sebagai faktor pencemar pada limbah industri restauran (Citra Sembada Catering yang tertampung pada septictank. Penelitian dilakukan dengan menggunakan reaktor Wastewater Garden dengan sistem batch dan dimensi reaktor lm x 0.5m x lm. Zona air limbah 75 cm, dan zona substrat atau krikil 80 cm, akar tanaman ditanam sedalam l0-15 cm. Metode penelitian yang digunakan berdasarkan SNI, di mana COD mengacu pada SNI 06-6989.2-2004 metode refluks tertutup secara spektrofotometri, TSS mengacu pada SK SNI M-03-1990-F metode pengujian secara gravimetri dan Fosfat total mengacu pada SNI M-52-1990-03 metode asam askorbat dengan alat spektrofotometer. Penelitian ini dilakukan selama 12 hari di mana setiap 3 hari sampel diambil pada outlel kemudian dianalisis. Berdasarkan hasil penelitian ini, diperoleh bahwa penggunaan wastewater garden pada limbah cair Mataram Citra Sembada Catering dapat menurunkan COD dengan efektivitas optimum 40,81% pada hari ke-6, penurunan TSS 89,l2% pada efektifitas optirnum hari ke-12 dan penurunan fosfat total dengan efektivitas optimum pada hari ke-6 yaitu sebesar 99,73 %. Tanaman dapat hidup dengan subur.   ABSTRACT  Wastewater

  6. Karakterisasi Paduan AlMgSi Untuk Kelongsong Bahan Bakar U3Si2/Al Dengan Densitas Uranium 5,2 gU/cm3

    Directory of Open Access Journals (Sweden)

    Aslina Br. Ginting

    2018-03-01

    Full Text Available Meningkatnya densitas uranium dari 2,96 gU/cm3 menjadi 5,2 gU/cm3 bahan bakar U3Si2/Al harus diikuti dengan penggunaan kelongsong yang kompatibel. Bahan bakar berdensitas tinggi mempunyai kekerasan yang tinggi, sehingga bila menggunakan paduan AlMg2 sebagai kelongsong dapat menyebabkan terjadi dogbone pada saat perolan. Selain fenomena dogbone, pada saat bahan bakar tersebut digunakan di reaktor dapat terjadi swelling karena meningkatnya hasil fisi maupun burn up. Oleh karena itu, perlu dicari pengganti bahan kelongsong untuk bahan bakar U3Si2/Al densitas tinggi. Pada penelitian ini telah dilakukan karakterisasi paduan AlMgSi sebagai kandidat pengganti kelongsong AlMg2. Karakterisasi yang dilakukan meliputi analisis termal, kekerasan, mikrostruktur dan laju korosi. Analisis termal dilakukan menggunakan DTA (Differential Thermal Analysis dan DSC (Differential Scanning Calorimetry. Analisis kekerasan menggunakan alat uji kekerasan mikro, mikrostruktur menggunakan SEM (Scanning Electron Microscope dan analisis laju korosi dilakukan dengan pemanasan pada temperatur 150 oC selama 77 jam di dalam autoclave. Hasil analisis menunjukkan bahwa kelongsong AlMgSi maupun AlMg2 mempunyai kompatibilitas panas dengan bahan bakar U3Si2/Al cukup stabil hingga temperatur 650 oC. Kelongsong AlMgSi mempunyai kekerasan sebesar 115 HVN dan kelongsong AlMg2 sebesar 70,1 HVN. Sementara itu, analisis mikrostruktur menunjukkan bahwa morfologi ikatan antarmuka (interface bonding kelongsong AlMgSi lebih baik dari kelongsong AlMg2, demikian halnya dengan laju korosi bahwa kelongsong AlMgSi mempunyai laju korosi lebih kecil dibanding kelongsong AlMg2. Hasil karakterisasi termal, kekerasan, mikrostruktur dan laju korosi menunjukkan bahwa PEB U3Si2/Al densitas 5,2 gU/cm3 menggunakan kelongsong AlMgSi lebih baik dibanding PEB U3Si2/Al  densitas 5,2 gU/cm3  menggunakan kelongsong AlMg2. Kata kunci: U3Si2/Al, densitas 5,2 gU/cm3, kelongsong AlMgSi dan AlMg2.

  7. Ultrasonics aids the identification of failed fuel rods

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Over a number of years Brown Boveri Reaktor of West Germany has developed and commercialized an ultrasonic failed fuel rod detection system. Sipping has up to now been the standard technique for failed fuel detection, but sipping can only indicate whether or not an assembly contains defective rods; the BBR system can tell which rod is defective. (author)

  8. Quick scan developments dairy markets for GDF-business partner BASF

    NARCIS (Netherlands)

    Daatselaar, C.H.G.; Beldman, A.C.G.; Prins, A.M.

    2015-01-01

    With the increasing consumption of milk and dairy products in some of the major developing markets and the fall of the quota system in the major milk producing region, Europe, milk producers are getting ready for the new opportunities. Simultaneously China, as a state controlled economy is

  9. Analisis Computational Fluid Dynamics untuk Perancangan Reaktor Gasifikasi Sekam Padi Tipe Downdraft

    Directory of Open Access Journals (Sweden)

    Dziyad Dzulfansya

    2014-10-01

    Full Text Available Rice husk is one of biomass type which can be utilized as gasification’s feedstock for producing combustible gas which can be used as fuel in internal combustion engine. The objective of this research was to obtain the best design of small scale rice husk gasifier from among geometry scenarios by applying computational fluid dynamics method. The geometry scenarios used in this study were angle of throat 70O, 80O, and 90O, and also angle of nozzel 10O and 20O. The softwares used in this study were Gambit 2.4.6 (meshing 3D model and Ansys Fluent 13.0 (simulation. The reactions involved in gasification (3 heterogeneous reactions and 6 homogeneous reactions were solved by finite rate/Eddy dissipation model. Results of simulation showed that gasifier with angle of throat 90O and angle of nozzel 10O produced the highest heating value of gas with volume fraction of CO, H2, and CH4 is 14.49%, 9.65%, and 2.39% respectively. This result showed reasonable agreement with experimental data from other researchers on rice husk gasification.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-12-15

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

  12. Definition of task (Phase II) B, 'Leak testing'; Definicija zadatka (II faza) B, 'Ispitivanje hermeticnosti'

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-01-15

    In order to ensure safe Ra reactor operation and fulfilling the conditions for performing irradiation experiments it was necessary to test and verify the leak tightness of the sample containers and thermocouples, as well as the irradiation capsule before it was placed in the VISA-2 channel. Leak testing of VISA-2 channel with capsules and thermocouples was done before and after it was built-in the reactor. [Serbo-Croat] U cilju bezbednosti i sigurnosti rada reaktora RA i ispunjavanja uslova ozracivanja izvrsena je provera hermeticnosti kenera sa uzorcima i termoparovima, kao i hermeticnost kapsule pre ugradjivanja kapsule u kanal VISA-2. Izvrseno je i ispitivanje hermeticnosti kanala VISA-2 sa kapsulama i termoparovima pre ugradjivanja u reaktor i posle montaze.

  13. Thermal stability and ionic conductivity of polymeric complexes Pva-KHSO4

    International Nuclear Information System (INIS)

    Vargas, R.A.; Vargas, M.A.; Garcia, A

    1996-01-01

    Its had synthesized highly conductive thin films of polymeric electrolytes, based on commercial glue (BASF's colbon) and KHSO4 salt, by means the solving casting method, using H3PO2 as common solvent. By high resolution thermal analysis and impedance spectroscopy we found that these complexes are highly amorphous and thermally stable in the 160 - 450 K temperature range. The glass transition temperature, Tg, varies with the salt concentration. The highest electrical conductivity at ambient temperature is obtained for x=0.16 salt concentration (on the higher concentrations range) and its value is around 10-2 (gamma cm)-1 , one of the highest reported in the literature for this type of compounds

  14. Services provided to other organizational units, Annex 7; Prilog 7 - Usluge drugim organizacionim jedinicama

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-15

    During 1965, the RA reactor staff provided services to other organizational units in: designing new systems, repair of electronic equipment, installing measuring devices, constructing mechanical elements in the workshop. [Serbo-Croat] U toku 1965. godine reaktor RA je pruzio usluge drugim jedinicama i to: projektovanjem novih sistema, popravkom elektronskih uredjaja, instaliranjem mernih sistema, izradom mehanickih elemenata i sklopova u mehanickoj radionici.

  15. Experimental verification of reflector savings calculated by REDIR code using two-group method; Eksperimentalna provera dvogrupnog racunanja reflektorske ustede koriscenog u REDIR-u

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1968-12-15

    Radial buckling and reflector savings for heavy water reactor with 2% enriched uranium fuel were measured and calculated by the REDIR code. A comparison of the obtained values is presented in this paper dependent on the reactor lattice pitch and reflector thickness. Experimental results obtained for lattice pitch of 16 cm prove the validity of applying the REDIR code for power reactors. U radu je dato uporedjenje izmedju izmerenih i teorijski izracunatih vrednosti (prema programu REDIR) radijalnih baklinga i reflektorske ustede za teskovodni reaktorski sistem sa 2% obogacenim uranskim gorivom u zavisnosti od koraka resetke i debljine reflektora. Rezultati dobijeni eksperimentima pri koraku resetke od 16 cm potvdjuju ispravnost primene programa REDIR za energetske reaktore. (author)

  16. BUSCAS DE INFORMAÇÕES TECNOLÓGICAS COM BASE EM DADOS DE PATENTES: ESTUDO DE CASO DOS LÍQUIDOS IÔNICOS NO BRASIL

    Directory of Open Access Journals (Sweden)

    Marcelo Gomes Speziali

    2015-09-01

    Full Text Available This study describes the application of the Art of Scientific and Technological Search to strategically analyze areas of technological and industrial development. Application of scientific search strategies such as the creation of Patent Landscape has been shown to be useful for writing research projects, earning grants, publishing papers, drafting patent applications, and analyzing the market and economic potentials of a previous determined subject. The Patent Landscape regards a simplified analysis of technologies concerning ionic liquids patents applied in Brazil and published by Instituto Nacional da Propriedade Industrial(INPI. A total of 93 patent applications using the keywords "ionic liquids" were found in the INPI database. Among these, 75% were nonresident applications and 25% were Brazilian resident applications. Interestingly, BASF, Chevron Industries, and the Universidade Federal do Rio Grande do Sul (UFRGS were discovered as higher patent applicant assignees. Differences in the patent application areas were also observed between these applicants, with new solvents and petrochemical applications as the areas of focus for the industrial applications (BASF and Chevron Industries, and energy production, catalysis, and chemical reaction media as the focus for the university applications.

  17. PENGUJIAN AKTIVITAS KOMPOSIT Fe2O3-SiO2 SEBAGAI FOTOKATALIS PADA FOTODEGRADASI 4-KLOROFENOL (The Activity Test of Fe2O3-SiO2 Composite As Photocatalyst on 4-Chlorophenol Photodegradation

    Directory of Open Access Journals (Sweden)

    Eko Sri Kunarti

    2009-03-01

    Full Text Available ABSTRAK  Pada penelitian ini telah dilakukan pengujian aktivitas komposit Fe2O3-SiO2 sebagai fotokatalis pada fotodegradasi 4-klorofenol. Penelitian diawali dengan preparasi dan karakterisasi fotokatalis Fe2O3-SiO2. Preparasi dilakukan dengan metode sol-gel pada temperatur kamar menggunakan tetraetil ortosilikat (TEOS dan besi (III nitrat sebagai prekursor diikuti dengan perlakuan termal pada temperature 500 oC. Karakterisasi dilakukan dengan metode spektrometri inframerah, difraksi sinar-X dan spektrometri fluoresensi sinar-X. Uji aktivitas komposit untuk fotodegradasi 4-klorofenol dilakukan dalam reaktor tertutup yang dilengkapi dengan lampu UV. Pada uji ini telah dipelajari pengaruh waktu penyinaran dan pH larutan terhadap efektivitas fotodegradasi 4-klorofenol. Hasil penelitian menunjukkan bahwa komposit Fe2O3-SiO2 dapat dipreparasi dengan metode sol-gel pada temperatur kamar diikuti perlakuan termal. Komposit Fe2O3-SiO2 dapat meningkatkan efektivitas fotodegradasi 4-klorofenol dari 11,86 % menjadi 55,38 %. Efektivitas fotodegradasi 4- klorofenol dipengaruhi waktu penyinaran dan pH larutan yang semakin lama waktu penyinaran efektifitas fotodegradasi semakin tinggi, namun waktu penyinaran yang lebih lama dari 4 jam dapat menurunkan efektivitasnya. pH larutan memberikan pengaruh yang berbeda-beda pada efektivitas fotodegradasi 4-klorofenol.   ABSTRACT The activity test of Fe2O3-SiO2 composite as photocatalyst on 4-chlorophenol photodegradation has been studied. The research was initiated by preparation of Fe2O3-SiO2 photocatalyst and followed by characterization. The preparation was conducted by sol-gel method at room temperature using tetraethylorthosilicate (TEOS and iron (III nitrate as precursors followed by thermal treatment at a temperature of 500oC. The characterizations were performed by X-ray Diffraction (XRD, Infrared and X-ray Fluorescence Spectrophotometry. The photocatalytic activity test of composites for 4 chlorophenol

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-01-15

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

  19. Investigating the effects of methanol-water vapor mixture on a PBI-based high temperature PEM fuel cell

    DEFF Research Database (Denmark)

    Araya, Samuel Simon; Andreasen, Søren Juhl; Nielsen, Heidi Venstrup

    2012-01-01

    This paper investigates the effects of methanol and water vapor on the performance of a high temperature proton exchange membrane fuel cell (HT-PEMFC). A H3PO4-doped polybenzimidazole (PBI) membrane electrode assembly (MEA), Celtec P2100 of 45 cm2 of active surface area from BASF was employed....... A long-term durability test of around 1250 h was performed, in which the concentrations of methanol-water vapor mixture in the anode feed gas were varied. The fuel cell showed a continuous performance decay in the presence of vapor mixtures of methanol and water of 5% and 8% by volume in anode feed...

  20. Scaling effects on H2-deflagration in containment-geometries - BASSIM. Further development and verification. Final report

    International Nuclear Information System (INIS)

    Rastogi, A.K.; Wennerberg, D.; Fischer, K.

    1998-01-01

    A multidimensional mechanistic calculation procedure for simulating H 2 -deflagration in multiroom geometries was developed at Battelle in a previous project. This calculation method was verified against a number of experiments performed in BMC (Battelle Model Containment) and HDR (Heissdampf Reaktor) facilities. It turned out that the above mentioned procedure overpredicted the H 2 -burnrates in experiments in smaller facilities and therefore was unable to predict the important 'scaling influences'. It is the purpose of the present work to develop the above mentioned calculation procedure BASSIM-H 2 (mod 2.3) further in order to predict the scaling influences correctly. In the present work the combustion model was developed further such that the important phenomena e.g. ignition phase, quasi-laminar initial phase, and the turbulent phase of a H 2 premixed flame would be modelled realistically. The model developed has been verified against 16 very different experiments from 9 different facilities. The computed cases varied in volumes from 0.022 m 3 up to 2100 m 3 . These cases have also been computed with the older model verified in [15]. Based on the comparison between the computed results obtained with the new model and the computed results obtained with the old model as well as with the experimental data, the model put forward in this work is evaluated. The present model computes the scaling effects on H 2 -deflagration satisfactorily with the same set of empirical constants. The flame propagation in horizontal as well as vertical (both upwards and downwards) directions can be computed satisfactorily. The influence of flow obstructions and heat loss at walls is considered as well. (orig.) [de

  1. Quality management in an international nuclear power plant project

    International Nuclear Information System (INIS)

    Brion, J.; Crustin, J.

    1975-01-01

    SNR (Schneller Natriumgekuehlter Reaktor) is the fast reactor power plant being erected at Kalkar, Federal German Republic. Quality management in this project is a contractual obligation. Quality management is subdivided into quality engineering, set of actions performed before manufacturing, and quality control, set of material controls performed during fabrication. The two successive phases of the quality management are presented. The difficulties and improvment possibilities are discussed [fr

  2. Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Wright, Ronald E.; Fletcher, Norman; Sidnev, Victor E.; Bickel, John H.; Vianello, Aldo; Pearsall, Raymond D.

    2003-01-01

    The Ignalina nuclear power plant (NPP) Units 1 and 2 are Soviet-designed, RBMK (Reaktor Bolshoi Moschnosti Kipyashchiy), channelized, large power-type reactors. The original-design electrical capacity for each unit was 1500 MW. Unit 1 began operating in 1983, and Unit 2 was started up in 1987. In 1994, the government of Lithuania agreed to accept grant support for the Ignalina NPP Safety Improvement Program with funding supplied by the Nuclear Safety Account of the European Bank for Reconstruction and Development (EBRD). As conditions for receiving this funding, the Ignalina NPP agreed to prepare a comprehensive safety analysis report that would undergo independent peer review after it was issued. The EBRD Safety Panel oversaw preparation and review of the report. In 1996, the safety analysis report for Unit 1 was completed and delivered to the EBRD. Part of the analyses covered anticipated transients without scram (ATWS). The analysis showed that some ATWS scenarios could lead to unacceptable consequences in <1 min. The EBRD Safety Panel recommended to the government of Lithuania that the Ignalina NPP develop and implement a program of compensatory measures for the control and protection system before the unit would be allowed to return to operation following its 1998 maintenance outage. A compensatory control and protection system that would mitigate the unacceptable consequences was designed, procured, manufactured, tested, and installed. The project was funded by U.S. Department of Energy

  3. A study to investigate the performance of the Benfield-HiPure process of natural gas sweetening using computer simulations

    Science.gov (United States)

    Ochieng, Richard

    capacity and plant energy efficiency. Due to the complexity and high investment cost of the Benfield HiPure process, potential alternatives are evaluated. The alternatives are basically MDEA based solvents with promoters to enable the simultaneous removal of H 2S and CO2. BASF's MDEA, MDEA/DEA or MDEA/DGA processes seem to be the best alternatives to the Benfield HiPure process. Using MDEA/DEA or MDEA/DGA process will reduce the capital costs of ADGAS by 50% , and up to 48% will be saved on the annual power consumption (0.33 million dollars per years) . BASF's MDEA has slightly higher capital costs due to the additional units required on the high pressure flash and the quenching units used to generate the semi-lean solution. However, BASF's MDEA process still stands as one of the best alternatives with a savings of about 102 million dollars (48%) on the capital costs and up to 36% (3.96 USD per ton of acid gas removed) on the cost stripping.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-12-15

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

  5. JPRS Report, Science & Technology, Europe, Economic Competitiveness

    Science.gov (United States)

    1991-04-25

    business), and entertainment electronics com- panies such as Sony , Pioneer, JVC, Hitachi and Mat- sushita ("National Panasonic") in particular are...of outsiders from Southeast Asia, who are making life miser- able for the already too numerous big producers, such as BASF, Sony , TDK, Maxell, FDM...Motor, Mitsubishi Motor, and Yamaha Motor (motorcycles, alongside its parent com- pany Yamaha Corporation, which is also in the musical instrument

  6. Sakslased vallutasid Siberi gaasimaardla / Arne Luht

    Index Scriptorium Estoniae

    Luht, Arne

    2005-01-01

    Venemaa president Vladimit Putin ja Saksama kantsler Gerhard Schröder viibisid Hannoveris maailma suurimal tööstusmessil. Sõlmiti leping, mille kohaselt hakkab Saksa keemiakontserni BASF tütarfirma Wintershall esimese välisfirmana Siberis koos Gazpromiga gaasi puurima, alla kirjutati ka lepingule gaasijuhtme rajamise kohta Viiburist läbi Läänemere Saksamaale. Vene kartelliamet välistas Saksa firma Siemens osaluse ettevõttes Silovõje Mashinõ

  7. SAFIRA project B.3.3: in-situ-treatment of contaminated ground water by catalytic oxidation. Final report; Sanierungsforschung in regional kontaminierten Aquiferen (SAFIRA). Projekt B.3.3: In situ-Behandlung von kontaminierten Grundwaessern durch katalytische Oxidation. Teilvorhaben 1: Untersuchungen im Labormassstab. Teilvorhaben 2: Tests in der bench-scale-Anlage und Teilvorhaben 3: Die Erprobung in der Pilotanlage am Modellstandort. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hofmann, J.; Haentzschel, D.; Freier, U.; Wecks, M.

    2003-06-27

    A new technology for treatment of contaminated ground water was developed. In this process heterogeneous catalysts (full metal catalyst, mixed oxide catalyst or iron-containing zeolites) in combination with hydrogen peroxide are used. In the reactor catalytic oxidation and aerob biological degradation occur simultaneously. A complete degradation of chlorobenzene was observed in a bench-scale-equipment (2 liter) and also in the pilot plant at the model site located in Bitterfeld (30 liter reactor). The technology can be applied to the ground and waste water treatment. (orig.) [German] Fuer die Behandlung von Grundwaessern, die mit organischen Schadstoffen belastet sind, wurde ein neuartiges Verfahren entwickelt. Bei der katalytischen Oxidation werden heterogene Katalysatoren in Form von Vollmetall-, Mischoxid- und Traegerkatalysatoren in Verbindung mit Wasserstoffperoxid als Oxidationsmittel eingesetzt. In den Katalysereaktoren laufen die heterogen-katalytische Oxidation und der aerob-biologische Abbau nebeneinander ab. Es werden synergistische Effekte erzielt. Mit dem Verfahren wurde in einer bench-scale-Angle (2 Liter) und in der Pilotanlage am Modellstandort in Bitterfeld (30 l Reaktor) der Schadstoff Chlorbenzol vollstaendig umgesetzt. Das Verfahren kann zur Grund- und Abwasserbehandlung eingesetzt werden. (orig.)

  8. Use of wastes in high-temperature processes of the chemical industry; Verwertung von Abfaellen in Hochtemperaturprozessen der chemischen Industrie

    Energy Technology Data Exchange (ETDEWEB)

    Seifert, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany); Domschke, T.; Steinebrunner, K. [BASF AG, Ludwigshafen am Rhein (Germany)

    1998-09-01

    The examples presented in this paper from diverse application areas of the chemical industry serve as an illustration of the many different ways in which wastes can be used for high-temperature processes in this branch. A review of the environmentally friendly concepts implemented at BASF AG in Ludwigshafen in the course of the past five years gives an idea of the immense potential opened up by a consistent application of the four-stage model for the prevention, reduction, and utilisation of wastes. In this period it was possible to reduce waste arisings by 34%, down from a potential 2 million tons, physically recycle 51%, and convert 11.5% to energy. This left a comparatively small fraction of 3.5%, or 70,000 tons, to be disposed of in an environmentally acceptable way. Furthermore, the amount of pollutants produced per tonne of products sold fell from 40.6 kg in 1987 to 6.7 kg in 1997. [Deutsch] Die Beispiele aus den unterschiedlichsten Anwendungsbereichen der chemischen Industrie koennen als Auswahl der vielfaeltigen Verwertungsmoeglichkeiten von Abfaellen in Hochtemperaturprozessen der Chemie betrachtet werden. Das immense Potential, das sich durch konsequente Anwendung des 4-Stufen-Modells zur Vermeidung, Verminderung und Verwertung von Abfaellen eroeffnet, zeigt sich in einer Fuenfjahresbilanz der umgesetzten Umweltschutzbetrachtungen in der BASF AG in Ludwigshafen. So konnten in diesem Zeitraum von potentiellen 2 Mio t Abfall/a ca. 34% vermieden und vermindert, 51% stofflich und 11,5% energetisch verwertet werden, so dass nur noch ein geringer Anteil von 3,5%, entsprechend ca. 70000 t/a, umweltgerecht entsorgt werden musste. Dies fuehrte auch zu einer drastischen Reduktion der auf der Tonne Verkaufsprodukt bezogenen Menge an umweltbelastenden Stoffen von 40,6 kg im Jahre 1987 auf 6,7 kg im Jahre 1997. (orig.)

  9. Biodegradable plastics in composting. Results of a practical experiment in the Bad Duerkheim district; Einsatz von biologisch abbaubaren Kunststoffen in der Kompostwirtschaft. Erkenntnisse und Erfahrungen aus dem Praxisversuch im Landkreis Bad Duerkheim

    Energy Technology Data Exchange (ETDEWEB)

    Pabst, Klaus [Abfallwirtschaftsbetrieb Landkreis Bad Duerkheim, Bad Duerkheim (Germany)

    2012-11-01

    For collecting biomass waste, about 65,000 households in the Bad Duerkheim district were given ten bags each of the compostable BASF plastic material Ecovio {sup registered} FS. The biomass waste collected in the Ecovio {sup registered} bags were composted in a composting plant. After the compost process, no residues of the Ecovio {sup registered} bags were found in the rotting, i.e. they are completely degradable. Neither the compost quality nor the working processes in the composting plant were affected, and there was no bigger volume of sorting residues. 90% of the users stated that they were satisfied with the new biomass waste bags. (orig.) [German] Fuer die Entsorgung des Bioabfalls erhielten rund 65.000 Haushalte aus dem Landkreis Bad Duerkheim je zehn Biomuelltuten aus dem kompostierbaren BASF-Kunststoff Ecovio {sup registered} FS. Die in diesen Ecovio {sup registered} -Tueten gesammelten Bioabfaelle wurden im Biokompostwerk zu Kompost verarbeitet. Nach dem Kompostierungsprozess konnten keine Reste der Ecovio {sup registered} -Folien mehr in der Rotte gefunden werden, und sie wurden vollstaendig biologisch abgebaut. Durch den Einsatz dieser Tueten wurden weder die Kompostqualitaet noch die Arbeitsablaeufe im Biokompostwerk beeintraechtigt. Eine Erhoehung der Sortierreste war nicht festzustellen. Im Rahmen einer Kundenbefragung aeusserten sich rund 90% zufrieden mit dem Einsatz dieser Biomuelltueten. (orig.)

  10. Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I; Tehnicka realizacija projekta VISA-2, ugovor: 2.01/I faza, Album br. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    , radijacionog ostecenja materijala. Projekat je podeljen u tri faze. Prva faza obuhvata radove koji se odnose na rekonstrukciju tehnoloskih kanala reaktora RA za potrebe projekta VISA-2. Druga faza obuhvata radove koji se odnose na merne sisteme kojima ce se meriti temperatura ulazne i izlazne teske vode u 5 kanala VISA-2, kao i temperature uzoraka (55 termoparova) kao i radove na ispitivanju kanala i kapsula pre i posle ugradnje u reaktor. Treca faza obuhvata radove koji se odnose na probleme transporta aktivnih tehnoloskih kanala i kapsula VISA-2, probleme njihovog secenja i odvajanje od kanala, kao i probleme pakovanja i transporta ozracenih uzoraka od Vince do Sacley-a. Ovaj album sadrzi sve dokumente relevantne za izvrsenje zadatka ukljucujuci ugovore, neophodne preliminarne proracune kao i analizu sigurnosti.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1974-12-15

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

  12. Report on the activity of the RA reactor operation for the period from July 1 1961 - Sept. 30 1961; Tromesecni izvestaj za period od 1.VII do 30.IX 1961. g

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Laboratorija za eksploataciju reaktora RA, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1961-09-15

    During the reporting period the reactor was permanently ready for operation and responding to the demands of the experimenters. The reactor was operating for 408.5 hours at power levels from 50 - 5000 kW, or 1985 MWh in total, burnup of the first batch of fuel was 22.55%. Reactor core was made of 56 fuel channels. Activities related to construction of new and improvement of the existing equipment was continued in order to enable safe operation and successful utilization of the RA reactor. Exchange of the electronic tubes was continued in order to increase the stability of the reactor control and reactor protection systems. About 65% of tubes planned to be exchanged this year was done. Cooperation with the CEN Saclay, France related to construction of experimental loops VISA-1 and VISA-2 was continued as well as cooperation with Poland concerned with exchange of experts. The problem of lack of properly trained staff was nor solved. [Serbo-Croat] U izvestajnom periodu reaktor je uvek bio spreman za rad i odgovarao je zahtevima eksperimentatora. Reaktor je radio 408,5 casova na snagama od 50-5000 kW, odnosno ukupno 1985 MWh, pri cemu je ukupan utrosak prve sarze goriva bio 22,55%. Jezgro reaktora bilo je sacinjeno od 56 tehnoloskih kanala. Radi bezbednijeg pogona i sto uspesnije eksploatacije reaktora RA nastavljeno je sa radovima na realizaciji novih i poboljsanju postojecih uredjaja. U cilju povecanja stabilnosti elektronskih instrumenta u sistemu upravljanja i zastiti reaktora nastavljeno je sa zamenom elektronskih cevi, do sada je zamenjeno oko 65% radova predvidjenih za ovu godinu. Nastavljena je saradnja sa nuklearnim centrom u Saclay, Francuska na izradi petlje VISA-1 i VISA-2 i saradnja sa Poljskom u razmeni strucnjaka. Problem nedostatka kadrova nije resen.

  13. Efektivitas Pengolahan Air Limbah Batik dengan Cara Kimia dan Biologi

    Directory of Open Access Journals (Sweden)

    Istihanah Nurul Eskani

    2016-04-01

    Full Text Available Kebanyakan industri batik membuang air limbah ke lingkungan tanpa diolah terlebih dahulu dengan alasan keterbatasan tempat, dana dan penguasaan teknologi. Beberapa cara pengolahan air limbah telah dilakukan untuk mengatasi penurunan mutunlingkungan akibat pembuangan air limbah.Telah dilakukan penelitian proses pengolahan air limbah batik secara kimia, biologi aerob dan biologi anaerob. Proses kimia dilaksanakan dengan menambahkan koagulan tawas dan kapur ke dalam air limbah batik. Proses biologi aerob dijalankan dalam reaktor terbuka selama 5 hari, sedang proses biologi anaerob  dijalankan dalam reaktor tertutup selama 12 hari. Hasil proses kemudian diukur parameter warna, COD dan alkalinitasnya.Hasil penelitian pengolahan air limbah batik secara kimia dapat menurunkan parameter warna yang berasal dari zat warna Naphtol sebesar 83,15 %, COD sebesar 28,82% dan pH hasil proses 7. Proses biologi anaerob menurunkan parameter warna sebesar 94,95%, COD sebesar 59,89% dan pH hasil proses 5. Proses biologi aerob dapat menurunkan parameter warna yang berasal dari zat warna Naphtol sebesar 97,82%, COD sebesar 72, 88% dan pH hasil proses 6,5. Sehingga dapat disimpulkan bahwa pengolahan limbah cair batik secara biologi aerob lebih efektif daripada pengolahan secara biologi anaerob maupaun secara kimia. Kata kunci : pengolahan air limbah batik, proses kimia, proses biologi

  14. Nuclear Reactor RA Safety Report, Vol. 13, Causes of possible accidents

    International Nuclear Information System (INIS)

    1986-11-01

    This volume includes the analysis of possible accidents on the RA research reaktor. Any unwanted action causing decrease of integrity of any of the reactor safety barriers is considered to be a reactor accident. Safety barriers are: fuel element cladding, reactor vessel, biogical shield, and reactor building. Reactor accidents can be classified in four categories: (1) accidents caused by reactivity changes; (2) accidents caused by mis function of the cooling system; (3) accidents caused by errors in fuel management and auxiliary systems; (4) accidents caused by natural or other external disasters. The analysis of possible causes of reactor accidents includes the analysis of possible impacts on the reactor itself and the environment [sr

  15. Vermikompos Sampah Kebun dengan Menggunakan Cacing Tanah Eudrilus eugeneae dan Eisenia fetida

    Directory of Open Access Journals (Sweden)

    Etik Rahmawati

    2016-04-01

    Full Text Available Durasi yang panjang diperlukan dalam pengomposan konvensional sampah organik yang memerlukan waktu selama 2-3 bulan. Pengurangan waktu pengomposan dapat dilakukan dengan digunakannya cacing sebagai dekomposer. Penelitian ini bertujuan untuk menentukan tingkat degradasi sampah kebun menggunakan proses vermikomposting dan menentukan pengaruh jenis cacing Eudrilus eugeneae dan Eisenia fetida. Empat reaktor berukuran 8 L digunakan dalam penelitian ini. Percobaan dilakukan secara duplo selama 60 hari. Parameter yang dianalisis pada penelitian ini adalah ammonia nitrogen (NH3-N, nitrat nitrogen (NO3-N, Total Kjeldahl Nitrogen (TKN, dan C/N. Hasil penelitian menunjukkan bahwa tingkat degradasi sampah kebun dengan pengolahan vermikomposting yang dapat dicapai adalah 64,94-72,52%. Produksi kompos yang lebih tinggi dengan penggunaan Eisenia fetida.

  16. Influence of dissolved product gas on organism retention in biogas tower reactors; Der Einfluss geloester Produktgase auf den Organismenrueckhalt in Biogas-Turmreaktoren

    Energy Technology Data Exchange (ETDEWEB)

    Pietsch, T.; Maerkl, H. [Technische Univ. Hamburg-Harburg, Hamburg (Germany). Arbeitsbereich Bioprozess- und Bioverfahrenstechnik

    1999-07-01

    In biogas tower reactors, considerable oversaturations of CO{sub 2} dissolved in molecular form in the liquid phase can occur, compared to the thermodynamic steady state with the gas phase. In buildings of low height, upflow designs cause biological CO{sub 2} production along the reactor to saturate the liquid phase with carbonic acid, and also cause the pH value increasing from acid degradation to bind CO{sub 2} in the form of hydrogen carbonate HCO{sup -}{sub 3}. Where buildings are very high, the liquid phase becomes degassed through a decrease in CO{sub 2} partial pressure because of decreasing hydrostatic pressure along the length of the reactor. Rising gas bubbles in the liquid phase as well as enclosed gas bubbles in biomass particles slow down their sedimentation considerably and can result in flotation of biomass particles owing to gas expansion from declining hydrostatic pressure. A sedimentation characteristics for biomass under decreasing hydrostatic pressure is given. Conditions critical to biomass retention are energy input into CO{sub 2}-oversaturated liquids as well as dynamically rapid drops in pH value owing to associated CO{sub 2} degassing. (orig.) [German] In Biogas-Turmreaktoren koennen erhebliche Uebersaettigungen von molekular geloestem CO{sub 2} in der Fluessigphase gegenueber dem thermodynamischen Gleichgewichtszustand mit der Gasphase auftreten. Bei geringer Bauhoehe fuehrt bei upflow-Konzepten die biologische CO{sub 2}-Produktion entlang des Reaktors zu einer Aufsaettigung der Fluessigphase mit Kohlensaeure und der durch Saeureabbau ansteigende pH-Wert zu einer Bindung des CO{sub 2} in Form des Hydrogencarbonats HCO{sub 3}{sup -}. Sehr grosse Bauhoehen fuehren zu einer Entgasung der Fluessigphase durch Abnahme des CO{sub 2}-Partialdruckes aufgrund des abnehmenden hydrostatischen Druckes entlang der Reaktorhoehe. Aufsteigende Gasblasen in der Fluessigphase sowie eingeschlossene Gasblasen in Biomassepartikeln mindern deren

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-15

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

  18. Inspection and repair of nuclear components

    International Nuclear Information System (INIS)

    Lahner, K.; Poetz, F.

    1993-01-01

    Despite careful design, manufacturing and operation, some of the important safety-relevant components show deterioration with time. Because of activation and contamination of these components, their inspection and repair has to be performed with manipulators. Some sophisticated manipulators are described, built by ABB Reaktor and used for inspection, maintenance and repair of PWR steam generators, fuel alignment pins, core baffle former bolts and reactor pressure vessel head penetrations. (Z.S.) 7 figs

  19. High performance ZIF-8/6FDA-DAM mixed matrix membrane for propylene/propane separations

    KAUST Repository

    Zhang, Chen; Dai, Ying; Johnson, Justin R.; Karvan, Oguz; Koros, William J.

    2012-01-01

    We report significantly enhanced propylene/propane (C 3H 6/C 3H 8) selectivity in mixed matrix membranes fabricated using 6FDA-DAM polyimide and a zeolitic imidazolate framework (ZIF-8). Equilibrium isotherms and sorption kinetics of C 3H 6 and C 3H 8 at 35°C were studied on a 200nm commercially available ZIF-8 sample produced by BASF. Mixed matrix dense films were formed with 6FDA-DAM and 200nm BASF ZIF-8 particles. SEM imaging showed generally good adhesion between the ZIF-8 and 6FDA-DAM without the need for surface-treating ZIF-8. Pure gas permeation showed significantly enhanced mixed matrix ZIF-8/6FDA-DAM membrane C 3H 6/C 3H 8 separation performance over the pure 6FDA-DAM membrane performance. A C 3H 6 permeability of 56.2Barrer and C 3H 6/C 3H 8 ideal selectivity of 31.0 was found in ZIF-8/6FDA-DAM mixed matrix membrane with 48.0wt% ZIF-8 loading, which are 258% and 150% higher than the pure 6FDA-DAM membrane, respectively for permeability and selectivity. Permeation properties of C 3H 6 and C 3H 8 in ZIF-8 were back-calculated by the Maxwell model for composite permeability using pure gas permeation data, leading to a C 3H 6 permeability of 277Barrer and C 3H 6/C 3H 8 selectivity of 122. Mixed gas permeation also verified that selectivity enhancements were achievable in mixed gas environment by ZIF-8. © 2011 Elsevier B.V.

  20. High performance ZIF-8/6FDA-DAM mixed matrix membrane for propylene/propane separations

    KAUST Repository

    Zhang, Chen

    2012-02-01

    We report significantly enhanced propylene/propane (C 3H 6/C 3H 8) selectivity in mixed matrix membranes fabricated using 6FDA-DAM polyimide and a zeolitic imidazolate framework (ZIF-8). Equilibrium isotherms and sorption kinetics of C 3H 6 and C 3H 8 at 35°C were studied on a 200nm commercially available ZIF-8 sample produced by BASF. Mixed matrix dense films were formed with 6FDA-DAM and 200nm BASF ZIF-8 particles. SEM imaging showed generally good adhesion between the ZIF-8 and 6FDA-DAM without the need for surface-treating ZIF-8. Pure gas permeation showed significantly enhanced mixed matrix ZIF-8/6FDA-DAM membrane C 3H 6/C 3H 8 separation performance over the pure 6FDA-DAM membrane performance. A C 3H 6 permeability of 56.2Barrer and C 3H 6/C 3H 8 ideal selectivity of 31.0 was found in ZIF-8/6FDA-DAM mixed matrix membrane with 48.0wt% ZIF-8 loading, which are 258% and 150% higher than the pure 6FDA-DAM membrane, respectively for permeability and selectivity. Permeation properties of C 3H 6 and C 3H 8 in ZIF-8 were back-calculated by the Maxwell model for composite permeability using pure gas permeation data, leading to a C 3H 6 permeability of 277Barrer and C 3H 6/C 3H 8 selectivity of 122. Mixed gas permeation also verified that selectivity enhancements were achievable in mixed gas environment by ZIF-8. © 2011 Elsevier B.V.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-12-15

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

  2. B-Carotene-a long road to commercial implementation

    CSIR Research Space (South Africa)

    Gardiner, NS

    2006-09-01

    Full Text Available ) • Animal feed supplements • Food supplements – colorant, Vitamin A supplement • OTC pharmaceuticals (health supplements) – anti-oxidant, Vitamin A supplement © CSIR 2006 www.csir.co.zaSlide 4 Production • Chemical synthesis... • BASF, DSM (formerly Roche) • Algal production (Dunaliella salina) • Betatene (Cognis), Koor Foods, NCSA • Extraction from natural sources (carrots, palm oil) • DSM (formerly Roche), Hanson and Darius • Fungal production (Blakeslea trispora) • DSM...

  3. PROTECTION OF YIELD AND SOIL: NEW MULCHING TECHNOLOGY

    OpenAIRE

    N. V. Sorokina; L. A. Uzhaninova

    2016-01-01

    Biodegradable ecovio® plastic films for mulching is a solution of BASF engineering.It offers the excellent mechanical properties, and it is completely destructedas polymer is to be fully composted. Without recycling this covering plastic filmis entirely digested by soil microorganisms. The only thing is to do after harvestingis to bury scraps of plastics into the soil to start the process of biodigestion. Development of ecovio® solution opens new page for wide use of this technology in agricu...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-15

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in July 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The following major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the power supply system. Project concerned with renewal of RA reactor complete instrumentation was started at the end of 1988. Contract was signed between the IAEA and Soviet Atomenergoexport for supplying the new instrumentation for the RA reactor. Project concerned with increase of the storage space and the efficiency of handling the spent fuel elements has started in 1988. In 1989, device for water purification designed by the reactor staff started operation and spent fuel handling equipment is being mounted. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula 1984. Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Zavrseni su radovi na izgradnji sistema za udesno hladjenje, rekonstrukciji postojeceg sistema specijalne ventilacije i rekonstrukciji sistema za napajanje elektricnom energijom. Krajem 1988, medjunarodna agencija za atomsku energiju potpisala je ugovor sa sovjetskom firmom Atomergexport za izradu novog sistema instrumentacije. Sa ciljem da se poveca i efikasnije koristi prostor za skladistenje ozracenog goriva, 1987. godine zapoceta je realizacija projekata preciscavanja vode u bazenima za odlezavanje

  5. Annual report of the group for maintenance of electrical equipment; Godisnji izvestaj elektro grupe

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-12-15

    This report includes detailed description of repairs and revisions of the electrical equipment of the RA reactor which were done according to the annual plan during the periods when reactor was not operated. Unplanned repairs are part of this report as well. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis remontnih i revizionih radova na elektroopremi reaktora RA izvrsenih prema godisnjem planu u periodima kada reaktor nije radio. Vanplanski poslovi ukljucujuci popravke elektroopreme su takodje deo ovog izvestaja.

  6. Comparative studies in farther-reaching waste water cleaning in different reactor systems; Vergleichende Untersuchungen zur weitergehenden Abwasserreinigung in unterschiedlichen Reaktorsystemen

    Energy Technology Data Exchange (ETDEWEB)

    Dockhorn, T. [Technische Univ. Braunschweig (Germany). Inst. fuer Siedlungswasserwirtschaft

    1999-07-01

    Three semi-technical pilot plants (completely mixed reactor, cascade, SBR) were operated in parallel under equal starting conditions. The influence of the type of reactor on the processes COD elimination, nitrification, denitrification and biological P elimination under operating conditions was studied. (orig.) [German] Es wurden drei halbtechnische Versuchsanlagen (volldurchmischter Reaktor, Kaskade, SBR) unter gleichen Ausgangsbedingungen parallel betrieben. Hierbei wurde der Einfluss des Reaktortyps auf die Prozesse CSB-Elimination, Nitrifikation, Denitrifikation sowie biologische P-Elimination unter Betriebsbedingungen untersucht. (orig.)

  7. Optimization of NMP extraction in 1, 3-butadiene production line

    OpenAIRE

    Mortaheb, H.R.; Mafi, M.; Mokhtarani, B.; Khosravi, K.; Mashkini, F.

    2010-01-01

    N-methylpyrrolidone is a powerful solvent for variety of chemical processes due to its vast chemical properties. It has been used in manufacturing processes of polymers, detergents, pharmaceuticals rubber and many more chemical substances. However, it creates large amount of residue in some of these processes which has to be dealt with. Many well known methods such as BASF in rubber producing units have tried to regenerate the solvent at the end of each run, however, there is still discarding...

  8. The treatment of uranyl nitrate from the AMOR process for VKTA Rossendorf

    International Nuclear Information System (INIS)

    Boessert, W.; Krempl, R.; Miller, J.W.

    2003-01-01

    The blending of uranyl nitrate solutions at VKTA and its subsequent treatment at BNFL-Sellafield is a significant step towards the safe and effective treatment of these enriched uranyl nitrate solutions. Overall the integration of the expertise of the international company BNFL/Westinghouse will lead to the achievement of a successful solution. This success has involved the integration of the project management and operational facilities of BNFL Sellafield with the local planning, design and manufacture capacities of Westinghouse Reaktor GmbH. (orig.)

  9. Kinetics parameter measurements on RSG-GAS, a low-enriched fuel reactor

    International Nuclear Information System (INIS)

    Jujuratisbela, U; Arbie, B; Pinem, S.; Tukiran; Suparlina, L.; Singh, O.P.

    1995-01-01

    Kinetics parameter measurements, such as reactivity worths of control rods and fuel elements, beam tube void reactivity, power reactivity coefficient and xenon poisoning reactivity have been performed on different cores of Reaktor Serba Guna G.A. Siwabessy (RSG-GAS). In parallel, a programme was also initiated to measure the other kinetics parameters like effective delayed neutron life time, prompt neutron decay constant, validation of period reactivity relationship and zero power frequency response function. The paper provides the results of these measurements. (author)

  10. Monitoring the degradation of partly decomposable plastic foils

    Directory of Open Access Journals (Sweden)

    Rétháti Gabriella

    2014-11-01

    Full Text Available We have monitored the behaviour of different polyethylene foils including virgin medium density polyethylene (MDPE, MDPE containing pro-oxydative additives (238, 242 and MDPE with pro-oxydative additives and thermoplastic starch (297 in the soil for a period of one year. A foil based on a blend of polyester and polylactic acid (BASF Ecovio served as degradable control. The experiment was carried out by weekly measurements of conductivity and capacity of the soil, since the setup was analogous to a condenser, of which the insulating layer was the foil itself. The twelve replications allowed monthly sampling; the specimen taken out from the soil each month were tested visually for thickness, mechanical properties, morphological and structural changes, and molecular mass. Based on the obtained capacity values, we found that among the polyethylene foils, the one that contained thermoplastic starch extenuated the most. This foil had the greatest decrease in tensile strength and elongation at break due to the presence of thermoplastic starch. The starch can completely degrade in the soil; thus, the foil had cracks and pores. The polyethylene foils that contained pro-oxydant additives showed smaller external change compared to the virgin foil, since there was no available UV radiation and oxygen for their degradation. The smallest change occurred in the virgin polyethylene foil. Among the five examined samples, the commercially available BASF foil showed the largest extenuation and external change, and it deteriorated the most in the soil.

  11. ANALISIS EFEK KECELAKAAN WATER INGRESS TERHADAP REAKTIVITAS DOPPLER TERAS RGTT200K

    Directory of Open Access Journals (Sweden)

    Zuhair Zuhair

    2015-03-01

    Full Text Available Dalam high temperature reactor, koefisien reaktivitas temperatur yang didesain negatif menjamin reaksi fisi dalam teras tetap berada di bawah kendali dan panas peluruhan tidak akan pernah melelehkan bahan bakar yang menyebabkan terlepasnya zat radioaktif ke lingkungan. Namun masuknya air (water ingress ke dalam teras reaktor akibat pecahnya tabung penukar panas generator uap, yang dikenal sebagai salah satu kecelakaan dasar desain, dapat mengintroduksi reaktivitas positif dengan potensi bahaya lainnya seperti korosi grafit dan kerusakan material struktur reflektor. Makalah ini akan menganalisis efek kecelakaan water ingress terhadap reaktivitas Doppler teras RGTT200K. Kapabilitas koefisien reaktivitas Doppler untuk mengkompensasi reaktivitas positif yang timbul selama kecelakaan water ingress akan diuji melalui serangkaian perhitungan dengan program MCNPX dan pustaka ENDF/B-VII untuk perubahan temperatur bahan bakar dari 800K hingga 1800K. Tiga opsi kernel bahan bakar UO2, ThO2/UO2 dan PuO2 dengan tiga model kisi bahan bakar pebble di teras reaktor diterapkan untuk kondisi water ingress dengan densitas air dari 0 hingga 1.000 kg/m3. Hasil perhitungan memperlihatkan koefisien reaktivitas Doppler tetap negatif untuk seluruh opsi bahan bakar yang dipertimbangkan bahkan untuk posibilitas water ingress yang besar. Efek water ingress lebih kuat pada model kisi dengan fraksi packing lebih rendah karena lebih banyak volume yang tersedia untuk air yang memasuki teras reaktor. Efek water ingress juga lebih kuat di teras uranium dibandingkan teras thorium dan plutonium sebagai konsekuensi dari fenomena Doppler dimana absorpsi neutron di daerah resonansi 238U lebih besar daripada 232Th dan 240Pu. Secara keseluruhan dapat disimpulkan bahwa, koefisien Doppler teras RGTT200K mampu mengkompensasi insersi reaktivitas yang diintroduksi oleh kecelakaan water ingress. Teras RGTT200K dengan bahan bakar UO2, ThO2/UO2 dan PuO2 dapat mempertahankan fitur keselamatan

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-15

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

  13. Activity-based costing applied to the internal logistics of a chemical company

    OpenAIRE

    Vasconcellos, Themis Castro de; Marins, Fernando Augusto Silva [UNESP; Muniz Junior, Jorge [UNESP

    2008-01-01

    Este trabalho tem como objetivo apresentar como o método ABC - activity based costing foi implantado para realizar o custeio da logística interna da empresa química BASF SA., situada na cidade de Guaratinguetá - SP. Apresentam-se: a descrição do processo de mudança do método de custeio tradicional para o método ABC, as dificuldades encontradas e como foram ultrapassadas, bem como as vantagens constatadas pela empresa. O departamento de logística da empresa funciona como um prestador de serviç...

  14. Research in Nickel/Metal Hydride Batteries 2016

    Directory of Open Access Journals (Sweden)

    Kwo-Hsiung Young

    2016-10-01

    Full Text Available Nineteen papers focusing on recent research investigations in the field of nickel/metal hydride (Ni/MH batteries have been selected for this Special Issue of Batteries. These papers summarize the joint efforts in Ni/MH battery research from BASF, Wayne State University, the National Institute of Standards and Technology, Michigan State University, and FDK during 2015–2016 through reviews of basic operational concepts, previous academic publications, issued US Patent and filed Japan Patent Applications, descriptions of current research results in advanced components and cell constructions, and projections of future works.

  15. Petrochemistry; Petrochimie

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2005-12-15

    The two partners Total and Samsung will invest 600 millions of dollars in a plan whose aim is to increase the ethylene, propylene and polyethylene capacities in the site of Daesan (South Korea). Siam Cement and Dow will invest in a second steam-cracker in Thailand. The Filipino petroleum industry Petron wants to enter on the market of the petrochemistry. BASF is considering to build a steam-cracker in Russia. PetroChina will increase the ethylene capacities of its Lanzhou site to 100000 tons per year. (O.M.)

  16. Spectroscopic databases - A tool for structure elucidation

    Energy Technology Data Exchange (ETDEWEB)

    Luksch, P [Fachinformationszentrum Karlsruhe, Gesellschaft fuer Wissenschaftlich-Technische Information mbH, Eggenstein-Leopoldshafen (Germany)

    1990-05-01

    Spectroscopic databases have developed to useful tools in the process of structure elucidation. Besides the conventional library searches, new intelligent programs have been added, that are able to predict structural features from measured spectra or to simulate for a given structure. The example of the C13NMR/IR database developed at BASF and available on STN is used to illustrate the present capabilities of online database. New developments in the field of spectrum simulation and methods for the prediction of complete structures from spectroscopic information are reviewed. (author). 10 refs, 5 figs.

  17. Atomic Energy Research benchmark activity

    International Nuclear Information System (INIS)

    Makai, M.

    1998-01-01

    The test problems utilized in the validation and verification process of computer programs in Atomic Energie Research are collected into one bunch. This is the first step towards issuing a volume in which tests for VVER are collected, along with reference solutions and a number of solutions. The benchmarks do not include the ZR-6 experiments because they have been published along with a number of comparisons in the Final reports of TIC. The present collection focuses on operational and mathematical benchmarks which cover almost the entire range of reaktor calculation. (Author)

  18. Towards rational design of redox-stratified biofilms

    DEFF Research Database (Denmark)

    Lackner, Susanne

    Biologisk kvælstoffjernelse er en central proces indenfor avanceret spildevandsrensning. Denne afhandling beskriver anvendelsen af beluftede membran biofilm reaktorer (eng: MABRs) til fuld autotrof kvælstoffjernelse. Denne ret nye kvælstofomsætningsvej baseres på delvis omdannelse af ammonium til....... Som illustreret ved modelundersøgelserne, kan biofilm afrivning påvirke rektorfunktionen alvorligt. Den udførte forsøg for at vurdere om kemisk modificering af biofilmoverfladen kan øge dens modstandsdygtighed overfor afrivning og give forbedret biofilm tykkelseskontrol. Alt i alt kan MABR, hvor ilt...

  19. Heavy water pumps; Pumpe D{sub 2}O

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V; Nikolic, M

    1963-12-15

    Continuous increase of radiation intensity was observed on all the elements in the heavy water system during first three years of RA reactor operation. The analysis of heavy water has shown the existence of radioactive cobalt. It was found that cobalt comes from stellite, cobalt based alloy which was used for coating of the heavy water pump discs in order to increase resistance to wearing. Cobalt was removed from the surfaces due to friction, and transferred by heavy water into the reactor where it has been irradiated for 29 876 MWh up to 8-15 Ci/g. Radioactive cobalt contaminated all the surfaces of aluminium and stainless steel parts. This report includes detailed description of heavy water pumps repair, exchange of stellite coated parts, decontamination of the heavy water system, distillation of heavy water. [Serbo-Croat] U toku prve tri godine eksploatacije reaktora RA uocen je neprekidni porast intenziteta zracenja na svim elementima u teskovodnom sistemu. Analizom teske vode utvrdjeno je postojanje radioaktivnog kobalta. Ustanovljeno je da kobalt potice od stelita, legure na bazi kobalta kojim su presvuceni rukavci vratila teskovodnih pumpi radi otpornosi na habanje. Kobalt je trenjem skidan sa povrsina, u toku rada prenosen je teskom vodom u reaktor i ozracivan u toku 29 876 MWh do specificne aktivnosti 8-15 Ci/g. Radioaktivni kobalt je kontaminirao sve povrsine od aluminijuma i nerdjajuceg celika. Ovaj izvestaj sadrzi detaljan opis remonta pumpi, zamene delova teskovodnih pumpi novim delovima bez stelitnog sloja, dekontaminacije teskovodnog sistema, destilacije teske vode.

  20. Performance and endurance of a high temperature PEM fuel cell operated on methanol reformate

    DEFF Research Database (Denmark)

    Araya, Samuel Simon; Grigoras, Ionela; Zhou, Fan

    2014-01-01

    This paper analyzes the effects of methanol and water vapor on the performance of a high temperature proton exchange membrane fuel cell (HT-PEMFC) at varying temperatures, ranging from 140 °C to 180 °C. For the study, a H3PO4 – doped polybenzimidazole (PBI) – based membrane electrode assembly (MEA......) of 45 cm2 active surface area from BASF was employed. The study showed overall negligible effects of methanol-water vapor mixture slips on performance, even at relatively low simulated steam methanol reforming conversion of 90%, which corresponds to 3% methanol vapor by volume in the anode gas feed....... Temperature on the other hand has significant impact on the performance of an HT-PEMFC. To assess the effects of methanol-water vapor mixture alone, CO2 and CO are not considered in these tests. The analysis is based on polarization curves and impedance spectra registered for all the test points. After...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

    Start of utilization of the new 80% enriched dispersion nuclear fuel is underway in the RA reactor core. Both economic and technical analyses were in favor of introducing the new fuel elements gradually into the RA reactor core. Thus overall theoretical and experimental analyses as well as other preparations are directed to transition regime based on gradual introducing of new fuel into the core, i.e. reactor core with two types of fuel. The objective of these analyses and preparation is establishment of conditions for safe reactor operation during transition period. The analyses and preparations are almost completed. The experimental data about fuel burnup during a time period of operation at nominal power i.e. daily decrease of excess reactivity is missing. This data is needed for planning the refueling (quantity of fresh fuel and frequency of refueling) during the transient period. This data can be obtained only by normal operation of the reactor during a period of time significantly longer than the period of attaining equilibrium poisoning, as time between two D{sub 2}O condensate overflows into the RA reactor core. Thus a ten day experimental campaign was planned to be done in December 1976. This report presents the most important results of safety analyses and preparation which show that, during this experimental period, the reactor operation is absolutely safe taking into account the most important parameters influencing reactor safety, as reactivity, thermal and temperature limits for fuel and the reactor, etc. Data to be obtained during this experimental campaign are significant because they would enable definition of future supply of fresh fuel during the transition period. [Serbo-Croat] Predstoji pocetak koriscenja novog 80% obogacenog uranskog disperzionog goriva u reaktoru RA. Ekonomske i tehnicke analize dale su prednost postupku postepenog uvodjenja novog goriva u reaktor RA. Prema tome, obimne teorijske i eksperimentalne analize i druge pripreme

  2. New developments in FCC catalysis

    Energy Technology Data Exchange (ETDEWEB)

    Kelkar, C.P. [BASF Corporation, Iselin, NJ (United States)

    2011-07-01

    Fluid catalytic cracking (FCC) unit is one of the primary boiling point reduction units in the refinery that converts longer chain crude oil to useful products such as distillate, gasoline and LPG. As the quality of feedstock deteriorates, while specifications on the product side are becoming more and more stringent, the FCC unit is being severely challenged. Over the past few years BASF has introduced two new platform technologies that will assist in this challenge. This paper will present an overview of those platforms and also provide a brief update on the research underway to mitigate the current REO crisis. (orig.)

  3. PROTECTION OF YIELD AND SOIL: NEW MULCHING TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    N. V. Sorokina

    2016-01-01

    Full Text Available Biodegradable ecovio® plastic films for mulching is a solution of BASF engineering.It offers the excellent mechanical properties, and it is completely destructedas polymer is to be fully composted. Without recycling this covering plastic filmis entirely digested by soil microorganisms. The only thing is to do after harvestingis to bury scraps of plastics into the soil to start the process of biodigestion. Development of ecovio® solution opens new page for wide use of this technology in agriculture. The usage of biodegradable plastic films has shown the good results in plant nursery gardens, vegetable and grape growing.

  4. Selective hydrogenation processes in steam cracking

    Energy Technology Data Exchange (ETDEWEB)

    Bender, M.; Schroeter, M.K.; Hinrichs, M.; Makarczyk, P. [BASF SE, Ludwigshafen (Germany)

    2010-12-30

    Hydrogen is the key elixir used to trim the quality of olefinic and aromatic product slates from steam crackers. Being co-produced in excess amounts in the thermal cracking process a small part of the hydrogen is consumed in the ''cold part'' of a steam cracker to selectively hydrogenate unwanted, unsaturated hydrocarbons. The compositions of the various steam cracker product streams are adjusted by these processes to the outlet specifications. This presentation gives an overview over state-of-art selective hydrogenation technologies available from BASF for these processes. (Published in summary form only) (orig.)

  5. Implantação do método activity based costing na logística interna de uma empresa química Activity-based costing applied to the internal logistics of a chemical company

    Directory of Open Access Journals (Sweden)

    Themis Castro de Vasconcellos

    2008-08-01

    Full Text Available Este trabalho tem como objetivo apresentar como o método ABC - activity based costing foi implantado para realizar o custeio da logística interna da empresa química BASF SA., situada na cidade de Guaratinguetá - SP. Apresentam-se: a descrição do processo de mudança do método de custeio tradicional para o método ABC, as dificuldades encontradas e como foram ultrapassadas, bem como as vantagens constatadas pela empresa. O departamento de logística da empresa funciona como um prestador de serviços, atendendo a todos os processos produtivos das divisões (unidades de negócio existentes na planta de Guaratinguetá, no que concerne à armazenagem e ao fornecimento de matérias-primas, além de atuar na retirada e na armazenagem de produto acabado. Como principais resultados, obteve-se uma distribuição de custos mais justa entre as divisões da planta, identificação de oportunidades de melhoria nos processos logísticos, identificação de processo e atividades que não agregavam valor aos produtos, entre outros. Finalmente, o processo de implantação e os resultados foram muito bem avaliados pelos gestores, o que foi decisivo para a adoção do método ABC como sistema gerencial de custos logísticos da empresa.This paper describes an Activity-Based Costin (ABC model implemented for the costing of the internal logistics of the chemical company BASF S.A. located in Guaratinguetá, state of São Paulo, Brazil. All the phases involved in the change from the traditional costing model to the ABC model adopted by the company as presented, as are the difficulties, the solutions for detected problems, and the advantages gained. The Logistics Department of BASF acts as a service provider for all the productive processes of the company's departments (Sales Business Units - SBUs in the Guaratinguetá plant in terms of raw material storage and supply, and in the removal and storage of end products. The main results were improved costing of the

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1965-12-15

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

  7. Radiation protection at the RA Reactor in 1995, Part -2, Annex 2, Decontamination and actions, collection of liquid effluents and solid radioactive waste; Deo 2 - Prilog 2 - Dekontaminacija i intervencije, skupljanje tecnih efluenata i cvrstih radioaktivnih otpadnih materijala

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-12-01

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

  8. PENGOLAHAN LIMBAH CAIR ORGANIK SECARA BIOLOGI MENGGUNAKAN REAKTOR ANAEROBIK LEKAT DIAM

    OpenAIRE

    Indriyati, Indriyati

    2018-01-01

       Organic waste water can be treated biolocally by using anaerobic fixed bed reactor. Fixed bed reactor is bioreactor which is compleeted with support material inside reactor for bacteria fixation in the surface area of support material. The benefit of using this kind of technology are it needs low energy, low nutrien, low sludge production and could treat high organic concentraion waste water.   The support material  has important role in the  Fixed Bed reactor performance, therefore it mus...

  9. BASF catalysts for the removal of NO{sub x} and dioxin in various applications

    Energy Technology Data Exchange (ETDEWEB)

    Morsbach, B; Odermatt, P; Spahl, R [BASF AG, Ludwigshafen (Germany)

    1997-12-31

    The aim of this paper is to give an overview on the catalytic removal of NO{sub x} and dioxin. In the first part of this paper possible locations of the SCR (Selective Catalytic Reduction) units will be presented. The second part will concentrate on the mathematical models of the SCR-reaction with titanium-tungsten-vanadium catalysts. (author)

  10. BASF catalysts for the removal of NO{sub x} and dioxin in various applications

    Energy Technology Data Exchange (ETDEWEB)

    Morsbach, B.; Odermatt, P.; Spahl, R. [BASF AG, Ludwigshafen (Germany)

    1996-12-31

    The aim of this paper is to give an overview on the catalytic removal of NO{sub x} and dioxin. In the first part of this paper possible locations of the SCR (Selective Catalytic Reduction) units will be presented. The second part will concentrate on the mathematical models of the SCR-reaction with titanium-tungsten-vanadium catalysts. (author)

  11. Research in Nickel/Metal Hydride Batteries 2017

    Directory of Open Access Journals (Sweden)

    Kwo-Hsiung Young

    2018-02-01

    Full Text Available Continuing from a special issue in Batteries in 2016, nineteen new papers focusing on recent research activities in the field of nickel/metal hydride (Ni/MH batteries have been selected for the 2017 Special Issue of Ni/MH Batteries. These papers summarize the international joint-efforts in Ni/MH battery research from BASF, Wayne State University, Michigan State University, FDK Corp. (Japan, Institute for Energy Technology (Norway, Central South University (China, University of Science and Technology Beijing (China, Zhengzhou University of Light Industry (China, Inner Mongolia University of Science and Technology (China, Shenzhen Highpower (China, and University of the Witwatersrand (South Africa from 2016–2017 through reviews of AB2 metal hydride alloys, Chinese and EU Patent Applications, as well as descriptions of research results in metal hydride alloys, nickel hydroxide, electrolyte, and new cell type, comparison work, and projections of future works.

  12. Sintesis Furfural dari Bagas Tebu Via Reaksi Hidrolisa dengan Menggunakan Katalis Asam Asetat pada Kondisi Atmosferik

    Directory of Open Access Journals (Sweden)

    Nine Tria Rossa

    2015-12-01

    Full Text Available Telah dilakukan penelitian tentang hidrolisa bagas tebu menggunakan asam asetat sebagai katalis. Sebanyak 30 gram dihidrolisa dalam 300ml air yang mengandung katalis asam menggunakan  asetat sebesar 7 sampai 9% v/v dengan variabel waktu dan temperatur hidrolisa selama 1 sampai 4 jam dan 80oC sampai 103oC pada kondisi atmosferik menggunakan reaktor tipe batch. Penelitian ini bertujuan untuk mengetahui pengaruh temperatur dan waktu hidrolisa, serta konsentrasi katalis asam asetat terhadap perolehan furfural. Kemudian untuk menemukan kondisi paling efisien untuk memproduksi furfural menggunakan Response Surface Methodology (RSM dengan Software Design Expert 7.0.0. Hasil penelitian menunjukkan bahwa dengan penambahan waktu dan temperatur hidrolisa akan meningkatkan perolehan furfural. Perolehan asam asetat juga meningkat rata-rata hingga 2 kali dari konsentrasi asam asetat awal. Hal ini terjadi karena pemutusan gugus acetyl dari fraksi hemiselulosa pada bagas tebu. Perolehan kondisi optimum yakni pada waktu dan temperatur hidrolisa 2 jam dan 103oC, konsentrasi katalis 9%, dengan konsentrasi furfural 4,10 mg/ml dan konsentrasi asam asetat 2,62 mmol/ml.

  13. German Light-Water-Reactor Safety-Research Program

    International Nuclear Information System (INIS)

    Seipel, H.G.; Lummerzheim, D.; Rittig, D.

    1977-01-01

    The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments

  14. Anaerobic treatment of sulfate-containing wastewater from distilleries

    International Nuclear Information System (INIS)

    Stadlbauer, E.A.; Oey, L.N.; Weber, B.

    1994-01-01

    Bioprocess evaluation of a staged arrangement of a Pulse Driven Loop Reaktor (PDLR) and a Pulsed Anaerobic Filter (PAF) using highly polluted cherry slops as industrial wastewater shows a COD removal efficiency of 80-90% at loading rates of 8-4 kg COD/(M 3 .d). Contamination of cherry slops by sulfate (2 g/l) and copper (150-200 mg/l) reduces COD degradation to 40-50 percent. A pulsed anaerobic baffled reactor was envisaged as a corrective tool to improve mineralisation in the presence of sulfate-rich substrates by confining sulfate reducing bacteria to the first 4 chambers of the reactor. Phasing slightly improves COD degradation yield, but is not sufficient for stable process performance. Consequently, the use of lactic acid in stead of sulfuric acid in cherry-fermentation was suggested as a preventive method to avoid sulphide-induced digester failure. (orig.) [de

  15. Corn silage from corn treated with foliar fungicide and performance of Holstein cows.

    Science.gov (United States)

    Haerr, K J; Lopes, N M; Pereira, M N; Fellows, G M; Cardoso, F C

    2015-12-01

    Foliar fungicide application to corn plants is used in corn aimed for corn silage in the dairy industry, but questions regarding frequency of application and its effect on corn silage quality and feed conversion when fed to dairy cows remain prevalent. The objective of this study was to evaluate the effects of various foliar fungicide applications to corn on dry matter intake (DMI), milk production, and milk composition when fed to dairy cows. Sixty-four Holstein cows with parity 2.5±1.5, 653±80kg of body weight, and 161±51d in milk were blocked and randomly assigned to 1 of 4 corn silage treatments (total mixed ration with 35% of the dry matter as corn silage). Treatments were as follows: control (CON), corn silage with no applications of foliar fungicide; treatment 1 (1X), corn silage from corn that received 1 application of pyraclostrobin (PYR) foliar fungicide (Headline; BASF Corp.) at corn vegetative stage 5; treatment 2 (2X), corn silage from corn that received the same application as 1X plus another application of a mixture of PYR and metconazole (Headline AMP; BASF Corp.) at corn reproductive stage 1 ("silking"); and treatment 3 (3X), corn silage from corn that received the same applications as 2X as well as a third application of PYR and metconazole at reproductive stage 3 ("milky kernel"). Corn was harvested at about 32% dry matter and 3/4 milk line stage of kernel development and ensiled for 200d. Treatments were fed to cows for 5wk, with the last week being used for statistical inferences. Week -1 was used as a covariate in the statistical analysis. Dry matter intake tended to be lower for cows fed corn silage treated with fungicide than CON (23.8, 23.0, 19.5, and 21.3kg for CON, 1X, 2X, and 3X, respectively). A linear treatment effect for DMI was observed, with DMI decreasing as foliar fungicide applications increased. Treatments CON, 1X, 2X, and 3X did not differ for milk yield (34.5, 34.5, 34.2, and 34.4kg/d, respectively); however, a trend for

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-15

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

  17. Control and Experimental Characterization of a Methanol Reformer for a 350 W High Temperature Polymer Electrolyte Membrane Fuel Cell system

    DEFF Research Database (Denmark)

    Andreasen, Søren Juhl; Kær, Søren Knudsen; Jensen, Hans-Christian Becker

    , i.e. cathode and anode gas flows and temperature by using mass flow controllers and controlled heaters. Using this system the methanol reformer is characterized in its different operating points, both steady-state but also dynamically. Methanol steam reforming is a well known process, and provides...... and burner and the behaviour of the CO concentration of the reformate gas....... the high temperature waste gas from a cathode air cooled 45 cell HTPEM fuel cell stack. The MEAs used are BASF P2100 which use phosphoric acid doped polybenzimidazole type membranes; an MEA with high CO tolerance and no complex humidity requirements. The methanol reformer used is integrated into a compact...

  18. Use of new silica fillers as additives for polymers used in packaging of fruit

    Directory of Open Access Journals (Sweden)

    Romina Arreche

    2012-01-01

    Full Text Available The objective of this work was to synthesize nanosilicas with different degree of hydrophobicity by the sol-gel method, using tetraethyl orthosilicate as a precursor. For this purpose, 3-aminopropyl triethoxysilane (APS and 1,1,1,3,3,3 - hexamethyldisilazane (HMDS, were added during synthesis as modifiers. A commercial biopolymer (Hexamoll Dinch, BASF intended for packaging of apples, was added to the new nanosilicas. The materials obtained were characterized by X-ray diffraction, scanning electron microscopy, transmission electron microscopy, potentiometric titration, porosity, specific surface area and hydrophobicity/hydrophilicity by wetting test. Colorimetry was used to evaluate change in apple pulp color after contact with the different silicas.

  19. Research nuclear reactor RA - Annual report 1992; Istrazivacki nuklearni reaktor RA - Izvestaj za 1992. godinu

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-12-01

    Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Drugi prilog (B) je rad Z. Vukadina 'Recurrence formulas for evaluating expansion series of depletion functions' objavljen u casopisu Kerntechnik, 1991. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  20. Reproduction of the RA reactor fuel element fabrication; Reprodukcija izrade gorivnog elementa za reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    This document includes the following nine reports: Final report on task 08/12 - testing the Ra reactor fuel element; design concept for fabrication of RA reactor fuel element; investigation of the microstructure of the Ra reactor fuel element; Final report on task 08/13 producing binary alloys with Al, Mo, Zr, Nb and B additions; fabrication of U-Al alloy; final report on tasks 08/14 and 08/16; final report on task 08/32 diffusion bond between the fuel and the cladding of the Ra reactor fuel element; Final report on task 08/33, fabrication of the RA reactor fuel element cladding; and final report on task 08/36, diffusion of solid state metals. Ovaj rad sadrzi devet priloga: 1. Zavrsni izvestaj o podzadatku 08/12, ispitivanje elementa goriva reaktora RA; 2. Koncepcija izrade gorivnog elementa reaktora RA; 3. Ispitivanje mikrostrukture gorivnog elementa reaktora RA; 4. Zavrsni izvestaj o podzadatku 08/13, dobijanje binarnih legura urana sa legirajucim komponentama Al, Mo, Zr, Nb i B; 5. Dobijanje legure U-Al; 6. Zavrsni izvestaj o podzadacima 08/14 i 08/16; 7. Zavrsni izvestaj o podzadatku 08/32, difuziona veza goriva i kosuljice gorivnog elementa reaktora RA; 8. Zavrsni izvestaj o podzadatku 08/33, izrada kosuljice gorivnog elementa reaktora RA; 9. Zavrsni izvestaj o podzadatku 08/36, difuzija kod metala u cvrstom stanju.

  1. The development of quality assurance program in Reactor TRIGA PUSPATI (RTP)

    International Nuclear Information System (INIS)

    Rosli Darmawan; Mohd Rizal Mamat; Mohamad Zaid Mohamad; Mohd Ridzuan Abdul Mutalib

    2007-01-01

    One of the trivial issues in the operation of Nuclear Reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing has always bring about general public fear on anything related to nuclear. IAEA has always emphasized on the assurance of nuclear safety for all nuclear installations and activities. According to the IAEA safety guides, all research reactors are required to implement quality assurance programs to ensure the conduct of operations are in accordance with the safety standards required. This paper discusses the activities carried out toward the establishment of Quality Assurance Program for Reaktor TRIGA PUSPATI (RTP). (Author)

  2. Design Of Pump Monitoring Of Primary Cooling System

    International Nuclear Information System (INIS)

    Indrakoesoema, Koes; Sujarwono

    2000-01-01

    Monitoring of 3 primary cooling pumps done visually by operator on the spot. The operator must be check oil in a sight glass, oil leakage during pump operation and water leakage. If reaktor power increase about more than 3 MW, the radiation exposure also increase in the primary cell and that's way the operator can not check the pumps. To continuing monitor all pump without delay, one system has been added I.e Closed Circuit Television (CCTV). This system using 3 video camera to monitor 3 pumps and connected to one receiver video monitor by coaxial cable located in Main Control Room. The sequence monitoring can be done by sequential switcher

  3. Influence of Polycarboxylate Superplasticizers on Rheological Properties of Cement Slurries Used in Drilling Technologies / Wpływ Superplastyfikatorów Z Grupy Polikarboksylanów Na Właściwości Reologiczne Zaczynów Cementowych Stosowanych W Technologiach Wiertniczych

    Science.gov (United States)

    Stryczek, Stanisław; Wiśniowski, Rafał; Gonet, Andrzej; Złotkowski, Albert; Ziaja, Jan

    2013-09-01

    Sealing slurries, mainly the cement-based ones, are concentrated dispersive systems, containing solid particles of considerably developed specific surface. Rheologically, such systems are very complex. This also stems from the fact that the rheological properties have a significant effect on: • additives and admixtures modifying technological properties of fresh and set slurries, • chemically complex mechanism of hydration in a slurry in a function of time. Special attention should paid to plasticizing (plasticizers PL) and liquefying (traditional and new- -generation superplasticizers SP) admixtures affecting the modification and optimization of rheological properties of fresh cement slurries as far as providing efficiency of sealing of casing pipes is concerned. Laboratory analyses were focused on proving the following thesis: properly selected type of superplasticizer [by BASF Polska Sp.z o.o. (The Chemical Company) - Admixtures for Concrete Division] advantageously affects the rheological parameters of sealing slurry based on metallurgical cement CEM III /A 32,5. The following variables were used in the analyses: • type of superplasticizer, • type of batch fluid. The laboratory experiments were made on superplasticizers produced by BASF: • SKY 501, • SKY 503, • SKY 591, • ACE 430, • Glenium 115. The superplasticizer concentration in the slurry was 0.5 wt% (as compared with mass of dry cement). Water to cement ratio for the analyzed sealing slurries was equal to 0.5. The sealing slurries were made of metallurgical cement CEM III/A 32,5 N-LH/HSR/N Lafarge Cement S.A. in Małogoszcz. Zaczyny uszczelniające, a zwłaszcza typu cementowego, są skoncentrowanymi układami dyspersyjnymi, zawierającymi cząstki stałe o znacznie rozwiniętej powierzchni właściwej. Układy takie pod względem reologicznym należą do niezwykle złożonych. Wynika to między innymi z faktu, że na właściwości reologiczne w sposób istotny wpływają: • dodatki i

  4. Continuous Digital Light Processing (cDLP): Highly Accurate Additive Manufacturing of Tissue Engineered Bone Scaffolds.

    Science.gov (United States)

    Dean, David; Jonathan, Wallace; Siblani, Ali; Wang, Martha O; Kim, Kyobum; Mikos, Antonios G; Fisher, John P

    2012-03-01

    Highly accurate rendering of the external and internal geometry of bone tissue engineering scaffolds effects fit at the defect site, loading of internal pore spaces with cells, bioreactor-delivered nutrient and growth factor circulation, and scaffold resorption. It may be necessary to render resorbable polymer scaffolds with 50 μm or less accuracy to achieve these goals. This level of accuracy is available using Continuous Digital Light processing (cDLP) which utilizes a DLP(®) (Texas Instruments, Dallas, TX) chip. One such additive manufacturing device is the envisionTEC (Ferndale, MI) Perfactory(®). To use cDLP we integrate a photo-crosslinkable polymer, a photo-initiator, and a biocompatible dye. The dye attenuates light, thereby limiting the depth of polymerization. In this study we fabricated scaffolds using the well-studied resorbable polymer, poly(propylene fumarate) (PPF), titanium dioxide (TiO(2)) as a dye, Irgacure(®) 819 (BASF [Ciba], Florham Park, NJ) as an initiator, and diethyl fumarate as a solvent to control viscosity.

  5. Neutron Diffractometer; Neutronski difraktometar

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-12-15

    RA nuclear reactor is considered as a relatively strong neutron source producing the thermal neutron flux of about 3x10{sup 13} n/cm{sup 2} sec when operating at nominal power of 6.5 MW. Neutron diffraction method is applied in the field of solid state physics, material science, crystallography, magnetism, nuclear physic. Neutron diffractometer at the RA reactor consists of: system for obtaining collimated neutron beam from the horizontal experimental channel neutron monochromator; goniometer and electronic equipment for measurements and collecting the the measurement data. Nuklearni reaktor RA koji pri radu na snazi od 6,5 MW ima fluks termalnih neutrona oko 3x10{sup 13} n/cm{sup 2} sec predstavlja relativno jak izvor neutrona. Tehnika difrakcije neutrona primenjuje se u istrazivanjima fizike crvstog stanja, strukture materijala, kristalografije, magnetizma, nuklearne fizike. Neutronski difraktometar na reaktoru RA sastoji se od sistema za dobijanje kolimisanog snopa neutrona kroz horizontalni kanal reaktora; neutroskog monohromatora; goniometra i elektronskih uredjaja za merenja i registrovanje rezultata. Ovaj izvestaj sadrzi detaljan opis i seme neutronskog difraktometra sa pratecom opremom i elektronskim komponentama.

  6. PENGOLAHAN LIMBAH CAIR INDUSTRI FARMASI FORMULASI DENGAN METODE ANAEROB-AEROB DAN ANAEROB-KOAGULASI

    Directory of Open Access Journals (Sweden)

    Farida Crisnaningtyas

    2016-05-01

    Full Text Available Studi ini membahas mengenai pengolahan limbah cair industri farmasi dalam skala laboratorium dengan menggunakan konsep anaerob-kimia-fisika dan anaerob-aerob. Proses anaerob dilakukan dengan menggunakan reaktor Upflow Anaerobic Sludge Bed reactor (UASBr pada kisaran OLR (Organic Loading Rate 0,5 – 2 kg COD/m3hari, yang didahului dengan proses aklimatisasi menggunakan substrat gula. Proses anaerob mampu memberikan efisiensi penurunan COD hingga 74%. Keluaran dari proses anaerob diolah lebih lanjut dengan menggunakan dua opsi proses: (1 fisika-kimia, dan (2 aerob. Koagulan alumunium sulfat dan flokulan kationik memberikan efisiensi penurunan COD tertinggi (73% pada kecepatan putaran masing-masing 100 rpm dan 40 rpm. Uji coba aerob dilakukan pada kisaran MLSS antara 4000-5000 mg/L dan mampu memberikan efisiensi penurunan COD hingga 97%. Hasil uji coba menunjukkan bahwa efisiensi penurunan COD total yang dapat dicapai dengan menggunakan teknologi anaerob-aerob adalah 97%, sedangkan kombinasi anaerob-koagulasi-flokulasi hanya mampu menurunkan COD total sebesar 72,53%. Berdasarkan hasil tersebut, kombinasi proses anaerob-aerob merupakan teknologi yang potensial untuk diaplikasikan dalam sistem pengolahan limbah cair industri farmasi. 

  7. PENGARUH NILAI BAKAR TERHADAP INTEGRITAS KELONGSONG ELEMEN BAKAR TRIGA 2000

    Directory of Open Access Journals (Sweden)

    K.A. Sudjatmi

    2015-04-01

    Full Text Available Bentuk elemen bakar reaktor TRIGA Bandung adalah silinder padat yang merupakan campuran homogen paduan uranium dan zirkonium hidrida. Pada saat reaktor beroperasi, suhu elemen bakar akan bertambah, akibatnya akan menaikan tekanan gas-gas yang ada di dalam kelongsong elemen bakar. Tekanan gas yang timbul dalam kelongsong elemen bakar merupakan penjumlahan tiga komponen tekanan yaitu tekanan akibat udara yang terperangkap antara kelongsong dengan bahan bakar, tekanan oleh gas hasil fisi yang terbentuk dari elemen bakar dan tekanan yang berasal dari pemisahan hidrogen dari paduan zirkonium hidrida. Gas hasil fisi yang terbentuk oleh bahan bakar sebanding dengan besarnya fraksi bakar oleh setiap elemen bakar dalam teras reaktor. Semakin besar fraksi bakar elemen bakar, semakin besar gas gas hasil fisi yang dihasilkannya, akibatnya semakin besar tekanan di dalam kelongsong yang disebabkan oleh gas gas hasil fisi tersebut. Perhitungan jumlah gas-gas hasil fisi dalam kelongsong yang merupakan fungsi dari nilai bakar dilakukan dengan menggunakan program ORIGEN-2. Program ORIGEN-2 adalah kode komputer yang banyak digunakan untuk menghitung hasil fisi, peluruhan dan pengolahan bahan radioaktif. Tampang lintang, presentase timbulnya hasil fisi, data peluruhan, dan data lainnya yang diperlukan disediakan dalam pustaka data selama eksekusi program. Dari hasil perhitungan dapat disimpulkan bahwa tekanan gas yang diakibatkan oleh gas hasil fisi adalah 4,13 10-3 psi dan tekanan gas yang diakibatkan udara yang terjebak di dalam kelongsong adalah 56,6 psi, yang mengakibatkan tegangan pada kelongsong sebesar 2080 psi dan nilai ini jauh lebih kecil dari setengah tegangan luluh bahan kelongsong sebesar 12.000 psi pada temperatur 750 oC atau sekitar 40.000 psi pada temperatur 138 oC. Akhirnya dapat disimpulkan bahwa dilihat dari sisi nilai bakar, maka elemen bakar layak digunakan sampai mencapai nilai bakar maksimum. Kata kunci : TRIGA, nilai bakar, elemen bakar

  8. Start-up and Performance Characteristics of a Trickle Bed Reaktor Degrading Toluene

    Czech Academy of Sciences Publication Activity Database

    Misiaczek, O.; Paca, J.; Halecký, M.; Gerrard, A. M.; Sobotka, Miroslav; Soccol, C. R.

    2007-01-01

    Roč. 50, č. 5 (2007), s. 871-877 ISSN 1516-8913 Grant - others:GA ČR(CZ) GA104/05/0194 Institutional research plan: CEZ:AV0Z50200510 Source of funding: V - iné verejné zdroje Keywords : biotrickling filter * constructed mixed population * toluene Subject RIV: EE - Microbiology, Virology Impact factor: 0.349, year: 2007

  9. Eco-efficiency analysis of techniques for disposal of urban solid waste

    International Nuclear Information System (INIS)

    Dmitrijevas, Cibele

    2010-01-01

    Municipal solid waste is one of the major problems of modern society. In this sense it is necessary to discuss solutions to the fate of waste generated daily, increasingly in larger amounts, being imperative to advance the search for alternatives, not only in search of new technologies and solutions, as well as the improvement of methodologies currently employed to solve this relevant issue, especially in large urban centers. This paper presents the results of a comparative economic-environmental assessment performed by a method developed by BASF, two potential technologies: landfill and incineration with energy recovery. To facilitate the work, the information used were both real data - landfill and incinerator - Essencis Solucoes Ambientais S.A., (assuming some assumptions) and the use of secondary data, using the study of Arena et al., 2003. This ecoefficiency analysis tool covers the methodology of Life Cycle Assessment (LCA), which is a technique to evaluate the inputs and outputs of matter and energy and the potential environmental impacts associated with all stages of resource extraction and their transformations , and the use and final disposal of the product. The data in the environmental assessment are presented according to major categories, using a weighting method developed by BASF and understand the consumption of natural resources, consumption of energy resources, air emissions, water and soil, potential for human toxicity, accidents work, occupational diseases and land use. Economic evaluation in this work took into account the costs involved in operation and maintenance of disposal techniques or treatment of waste. The comparative study found the treatment or disposal of 7.324109 billion kilograms of waste. As a result, the array of eco-efficiency indicates that the incinerator is the alternative that stands out, considering the environmental and economic profile, within the assumptions made in this study and taking into account which is a

  10. A retrospective cohort study of shift work and risk of cancer-specific mortality in German male chemical workers.

    Science.gov (United States)

    Yong, Mei; Nasterlack, Michael; Messerer, Peter; Oberlinner, Christoph; Lang, Stefan

    2014-02-01

    Human evidence of carcinogenicity concerning shift work is inconsistent. In a previous study, we observed no elevated risk of total mortality in shift workers followed up until the end of 2006. The present study aimed to investigate cancer-specific mortality, relative to shift work. The cohort consisted of male production workers (14,038 shift work and 17,105 day work), employed at BASF Ludwigshafen for at least 1 year between 1995 and 2005. Vital status was followed from 2000 to 2009. Cause-specific mortality was obtained from death certificates. Exposure to shift work was measured both as a dichotomous and continuous variable. While lifetime job history was not available, job duration in the company was derived from personal data, which was then categorized at the quartiles. Cox proportional hazard model was used to adjust for potential confounders, in which job duration was treated as a time-dependent covariate. Between 2000 and 2009, there were 513 and 549 deaths among rotating shift and day work employees, respectively. Risks of total and cancer-specific mortalities were marginally lower among shift workers when taking age at entry and job level into consideration and were statistically significantly lower when cigarette smoking, alcohol intake, job duration, and chronic disease prevalence at entry to follow-up were included as explanatory factors. With respect to mortality risks in relation to exposure duration, no increased risks were found in any of the exposure groups after full adjustment and there was no apparent trend suggesting an exposure-response relation with duration of shift work. The present analysis extends and confirms our previous finding of no excess risk of mortality associated with work in the shift system employed at BASF Ludwigshafen. More specifically, there is also no indication of an increased risk of mortality due to cancer.

  11. Eco-efficiency analysis of techniques for disposal of urban solid waste; Analise de ecoeficiencia de tecnicas para tratamento e disposicao de residuos solidos urbanos

    Energy Technology Data Exchange (ETDEWEB)

    Dmitrijevas, Cibele

    2010-07-01

    Municipal solid waste is one of the major problems of modern society. In this sense it is necessary to discuss solutions to the fate of waste generated daily, increasingly in larger amounts, being imperative to advance the search for alternatives, not only in search of new technologies and solutions, as well as the improvement of methodologies currently employed to solve this relevant issue, especially in large urban centers. This paper presents the results of a comparative economic-environmental assessment performed by a method developed by BASF, two potential technologies: landfill and incineration with energy recovery. To facilitate the work, the information used were both real data - landfill and incinerator - Essencis Solucoes Ambientais S.A., (assuming some assumptions) and the use of secondary data, using the study of Arena et al., 2003. This ecoefficiency analysis tool covers the methodology of Life Cycle Assessment (LCA), which is a technique to evaluate the inputs and outputs of matter and energy and the potential environmental impacts associated with all stages of resource extraction and their transformations , and the use and final disposal of the product. The data in the environmental assessment are presented according to major categories, using a weighting method developed by BASF and understand the consumption of natural resources, consumption of energy resources, air emissions, water and soil, potential for human toxicity, accidents work, occupational diseases and land use. Economic evaluation in this work took into account the costs involved in operation and maintenance of disposal techniques or treatment of waste. The comparative study found the treatment or disposal of 7.324109 billion kilograms of waste. As a result, the array of eco-efficiency indicates that the incinerator is the alternative that stands out, considering the environmental and economic profile, within the assumptions made in this study and taking into account which is a

  12. Innovation policy of European chemical companies with special focus on large companies

    Directory of Open Access Journals (Sweden)

    Supriyo Das

    2015-07-01

    Full Text Available According to Arora et alii (1998, the chemical industry is one of the largest and most R&D-intensive manufacturing sectors in all the advanced economies, and its innovative patterns and productivity growth processes can have profound impacts on economic growth as a whole. The European chemical industry supplies virtually all sectors of the economy and accounts for 17.8% of the total sales of chemicals in the world. This paper gives an overview of the European chemical industry and the changing scenario of the world chemical industry by focusing on the top fifteen chemical companies in Europe. It describes the current problems this industry is facing in Europe especially after the economic crisis and shows that the region and the top companies are investing in R&D to bring about innovation and overcome the current challenges. It shows that R&D spending in absolute terms has hardly changed over the years and that the industry is still globally the largest investor in R&D activities. In terms of R&D, BASF has made the greatest investment followed by Bayer and Syngenta, while R&D intensity is highest for Syngenta and Bayer. BASF and Bayer have made most patent applications and have also had the highest number of patents granted. The quality of research in most chemical companies is very high and most of the large European companies make their first patent application in Europe rather than elsewhere. All the large chemical companies use Merger & Acquisition (M&A to gain access to innovation. Industry-academia collaboration is one way to generate innovation in the chemical industry in Europe. Chemical clusters and the geographical distribution of chemical companies play a significant role in generating innovation.

  13. Determinação da redução da resistência à tração em corpos de prova com Weld Line

    OpenAIRE

    Bom,R.P.; Kalin,A.F.

    2008-01-01

    Neste trabalho objetivou-se determinar a redução da resistência à tração de corpos de prova com linhas de solda. Os corpos de prova ASTM foram moldados pelo processo de injeção com diferentes temperaturas de plastificação (180 ºC a 280 ºC). O material utilizado foi o polímero termoplástico Polystyrol 158 K da Basf. Este estudo relaciona as linhas de solda em produtos moldados por injeção com a redução da resistência mecânica devido a fragilização na região da linha de solda. Para o desenvolvi...

  14. Avoided emissions. Enterprises assess their solutions for the climate

    International Nuclear Information System (INIS)

    Colas, Julien

    2017-09-01

    In its first part, this publication gives an overview of the issues of avoided emissions: reasons for their calculation, risks to be understood and anticipated, relationships between avoided emissions and enterprises, avoided emissions in the enterprise climate strategy, and available calculation methods. The second part describes the methodology and process of calculation of avoided emissions: project initiation, method selection, reference solution selection, scenario elaboration, definition of the scope of calculation, taking the whole value chain into account, result consolidation, communication. A synthesis of recommendations is provided. Within the text, this publication proposes presentations of actions undertaken by several French companies or French subsidiaries like Air France, BASF, EDF, Michelin, Paprec, RTE, Saint-Gobain, SNCF, Suez, Total, Veolia, and others

  15. Effectiveness factors for a commercial steam reforming (Ni) catalyst and for a calcined dolomite used downstream biomass gasifiers

    Energy Technology Data Exchange (ETDEWEB)

    Corella, J; Narvaez, I; Orio, A [Madrid Univ. (Spain). Dept. of Chem. Eng.

    1997-12-31

    A commercial steam reforming catalyst from BASF, the G1-25 S one, and a calcined dolomite, Norte-1, from Cantabria-Spain, have been used, once crushed and sieved to different particle fractions between 1.0 and 4.0 mm. The materials have been tested downstream small pilot biomass gasifiers, bubbling fluidized bed type, gasifying with air and with steam. The Thiele modulus and the effectiveness factor have been calculated at temperatures of 750-850 deg C. It is experimentally shown that diffusion control plays an important part when particle size is larger than ca. 0.5 mm. This has to be taken into account when comparing the quality of the solids for tar elimination. (author) (5 refs.)

  16. Effectiveness factors for a commercial steam reforming (Ni) catalyst and for a calcined dolomite used downstream biomass gasifiers

    Energy Technology Data Exchange (ETDEWEB)

    Corella, J.; Narvaez, I.; Orio, A. [Madrid Univ. (Spain). Dept. of Chem. Eng.

    1996-12-31

    A commercial steam reforming catalyst from BASF, the G1-25 S one, and a calcined dolomite, Norte-1, from Cantabria-Spain, have been used, once crushed and sieved to different particle fractions between 1.0 and 4.0 mm. The materials have been tested downstream small pilot biomass gasifiers, bubbling fluidized bed type, gasifying with air and with steam. The Thiele modulus and the effectiveness factor have been calculated at temperatures of 750-850 deg C. It is experimentally shown that diffusion control plays an important part when particle size is larger than ca. 0.5 mm. This has to be taken into account when comparing the quality of the solids for tar elimination. (author) (5 refs.)

  17. Core-shell rhodium sulfide catalyst for hydrogen evolution reaction / hydrogen oxidation reaction in hydrogen-bromine reversible fuel cell

    Science.gov (United States)

    Li, Yuanchao; Nguyen, Trung Van

    2018-04-01

    Synthesis and characterization of high electrochemical active surface area (ECSA) core-shell RhxSy catalysts for hydrogen evolution oxidation (HER)/hydrogen oxidation reaction (HOR) in H2-Br2 fuel cell are discussed. Catalysts with RhxSy as shell and different percentages (5%, 10%, and 20%) of platinum on carbon as core materials are synthesized. Cyclic voltammetry is used to evaluate the Pt-equivalent mass specific ECSA and durability of these catalysts. Transmission electron microscopy (TEM), X-ray Photoelectron spectroscopy (XPS) and Energy-dispersive X-ray spectroscopy (EDX) techniques are utilized to characterize the bulk and surface compositions and to confirm the core-shell structure of the catalysts, respectively. Cycling test and polarization curve measurements in the H2-Br2 fuel cell are used to assess the catalyst stability and performance in a fuel cell. The results show that the catalysts with core-shell structure have higher mass specific ECSA (50 m2 gm-Rh-1) compared to a commercial catalyst (RhxSy/C catalyst from BASF, 6.9 m2 gm-Rh-1). It also shows better HOR/HER performance in the fuel cell. Compared to the platinum catalyst, the core-shell catalysts show more stable performance in the fuel cell cycling test.

  18. Professional Nuclear Materials Management; Gestion Industrielle des Matieres Nucleaires; Obrashchenie s yadernymi materialami na professional'nom urovne; Administracion Eficiente de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Forcella, A. A.; O' Leary, W. J. [Allis-Chalmers Manufacturing Company, Bethesda, MD (United States)

    1966-02-15

    manipulacion y su transporte resulten economicos y sea facil sustituirlos. La programacion de las operaciones de fabricacion debera reducir al mfnimo las perdidas de ingresos debidas a un almacenamiento improductivo excesivamente largo de materiales de costo elevado. Para la etapa de su empleo en el reactor, sera necesario un programa adecuado de redistribucion de los elementos combustibles a fin de lograr el grado maximo de combustion del material fisionable. Ademas, habra que reducir en la medida de lo posible los paros improductivos del reactor debidos a la redistribucion del combustible, a las inspecciones, etc. Cuando el combustible haya llegado a un grado predeterminado de agotamiento, el administrador tendra que disponer la forma mas economica de regeneracion de los materiales fisionables y de recuperacion de los subproductos. La administracion de materiales nucleares es por consiguiente un factor esencial para la reduccion de los costos del ciclo del combustible y para lograr que el costo unitario de la energia producida resulte economicamente interesante. (author) [Russian] Daets ja opisanie ob{sup e}ma rabot na tipichnom jenergetichesko m reaktore v SShA. Poskol'ku jetot reaktor finansiruetsja chastnym kapitalom, odna iz osnovnyh objazannostej operatora sostoit v obespechenii sohrannosti kapitalovlozhenij i poluchenii opredelennoj pribyli. Vvidu bol'shoj sebestoimosti jadernyh materialov neobhodimo postojanno obespechivat' nadlezhashhuju bezopasnost' i uchet s cel'ju svedenija k minimumu poter', ne svjazannyh s obespe- cheniem bezopasnosti i ucheta jadernyh materialov. Neobhodimo vse tshhatel'no produmyvat' i planirovat' zaranee, chtoby izbegat' nenuzhnyh zatrat i rashodovanija kapitala ili snizhe- nija razmerov pribyli v rjade oblastej. Pojetomu administrator, vedajushhij jadernymi materialami, dolzhen zaranee uchityvat' vse nepredvidennye obstojatel'stva i osushhestvljat' postojannyj kontrol' nad otklonenijami ot standartov pri planirovanii vo vremja a

  19. Experimental Characterization of the Poisoning Effects of Methanol-Based Reformate Impurities on a PBI-Based High Temperature PEM Fuel Cell

    Directory of Open Access Journals (Sweden)

    Samuel Simon Araya

    2012-10-01

    Full Text Available In this work the effects of reformate gas impurities on a H3PO4-doped polybenzimidazole (PBI membrane-based high temperature proton exchange membrane fuel cell (HT-PEMFC are studied. A unit cell assembly with a BASF Celtec®-P2100 high temperature membrane electrode assembly (MEA of 45 cm2 active surface area is investigated by means of impedance spectroscopy. The concentrations in the anode feed gas of all impurities, unconverted methanol-water vapor mixture, CO and CO2 were varied along with current density according to a multilevel factorial design of experiments. Results show that all the impurities degrade the performance, with CO being the most degrading agent and CO2 the least. The factorial analysis shows that there is interdependence among the effects of the different factors considered. This interdependence suggests, for example, that tolerances to concentrations of CO above 2% may be compromised by the presence in the anode feed of CO2. Methanol has a poisoning effect on the fuel cell at all the tested feed ratios, and the performance drop is found to be proportional to the amount of methanol in feed gas. The effects are more pronounced when other impurities are also present in the feed gas, especially at higher methanol concentrations.

  20. KARAKTERISASI DAN AKTIVITAS KATALITIK BERBAGAI VARIASI KOMPOSISI KATALIS Ni DAN ZnBr2 DALAM Γ-Al2O3 UNTUK ISOMERISASI DAN HIDROGENASI (R-(+-SITRONELAL

    Directory of Open Access Journals (Sweden)

    ED Iftitah

    2014-06-01

    Full Text Available Pengaruh sifat dan karakter berbagai variasi komposisi katalis Ni dan ZnBr2 yang terimpregnasi dalam γ-Al2O3 terhadap aktivitas dan selektivitasnya untuk reaksi isomerisasi dan hidrogenasi (R-(+-Sitronelal telah dilakukan. Dalam penelitian ini, terdapat tiga jenis variasi komposisi Ni dan ZnBr2 dalam γ-Al2O3, yaitu: A1=Ni/ZnBr2/γ-Al2O3 (3:2, A2=Ni/ZnBr2/γ-Al2O3 (1:1 dan A3=Ni/ZnBr2/γ-Al2O3 (2:3. Katalis dikarakterisasi menggunakan X-ray diffraction (XRD, Brunauer-Emmett-Teller (BET surface area, dan SEM-EELS. Luas area permukaan spesifik dan porositasnya ditentukan berdasarkan adsorption-desorption gas nitrogen pada 77 K. Distribusi dan volume pori ditentukan dengan desorption isotherm pada P/Po ≥ 0,3. Hasil yang didapat menunjukkan bahwa terdapat hubungan antara karakter dan sifat katalis dengan aktivitas katalitiknya terhadap produk isomerisasi dan hidrogenasi (R-(+-Sitronelal. Uji aktivitas dilakukan dalam sebuah reaktor mini dengan 0,5 g katalis dan 3 mL (R-(+-Sitronelal menggunakan atmosfir gas N2 dan/atau H2 dalam waktu 5 dan 24 jam masing-masing pada suhu 90 dan 120 °C. Komposisi katalis, pemilihan jenis atmosfir gas dan suhu sangat berpengaruh terhadap aktivitas dan selektivitas pembentukan produk isomerisasi dan hidrogenasi. Konversi (R-(+-Sitronelal tertinggi ditunjukkan oleh katalis A3=Ni/ZnBr2/γ-Al2O3 (2:3 dengan kondisi reaksi selama 5 jam (4 jam N2 + 1 jam H2 pada suhu 90 °C dan 24 jam (4 jam N2 + 20 jam H2 pada suhu 120 °C. The influence of catalyst properties and characteristics of Ni and ZnBr2 catalysts impregnated in γ-Al2O3 on the activity and selectivity of (R-(+-Citronellal isomerisation and hydrogenation has been done. In this study, there were three sets of Ni and ZnBr2 in γ-Al2O3 with various composition, they were A1=Ni/ZnBr2/γ-Al2O3 (3:2, A2=Ni/ZnBr2/γ-Al2O3 (1:1, A3=Ni/ZnBr2/γ-Al2O3 (2:3. The catalysts were characterized using X-ray diffraction (XRD, Brunauer-Emmett-Teller (BET surface area and SEM

  1. SiC nanocrystals as Pt catalyst supports for fuel cell applications

    DEFF Research Database (Denmark)

    Dhiman, Rajnish; Morgen, Per; Skou, E.M.

    2013-01-01

    A robust catalyst support is pivotal to Proton Exchange Membrane Fuel Cells (PEMFCs) to overcome challenges such as catalyst support corrosion, low catalyst utilization and overall capital cost. SiC is a promising candidate material which could be applied as a catalyst support in PEMFCs. Si...... on the nanocrystals of SiC-SPR and SiC-NS by the polyol method. The SiC substrates are subjected to an acid treatment to introduce the surface groups, which help to anchor the Pt nano-catalysts. These SiC based catalysts have been found to have a higher electrochemical activity than commercially available Vulcan...... based catalysts (BASF & HISPEC). These promising results signal a new era of SiC based catalysts for fuel cell applications....

  2. PEMBUATAN KALSIUM KARBONAT DARI BITTERN DAN GAS KARBON DIOKSIDA SECARA KONTINYU

    Directory of Open Access Journals (Sweden)

    Soemargono Soemargono

    2012-01-01

    Full Text Available Kalsium karbonat  yang  digunakan  dalam  industri- industri cat, karet, dan  kertas  harus  mempunyai  mutu yang  tinggi, terutama  kemurnian  dan kehalusannya.Untuk itu, Indonesia masih  mendatangkan  kalsium  karbonat murni dari luar negeri dalam jumlah yang cukup besar. Bittern merupakan bahan buangan industri garam yang disebut juga air tua, mengandung senyawa kalsium. Karbon dioksida biasanya berasal dari hasil pembakaran yang masuk ke udara. Kandungannya di udara kecil, tetapi berpotensi sebagai pencemar. Dengan mereaksikan kalsium yang terkandung dalam bittern dengan gas CO2 akan terbentuk CaCO3 dalam suasana basa. Pembentukan kalsium karbonat dilakukan dengan proses kontinyu dalam reaktor kolom bersekat miring. Dari hasil penelitian diperoleh bahwa pengendapan magnesium dengan larutan ammonia menyebabkan kandungan kalsium ikut terdegradasi. Hasil terbaik yang diperoleh dicapai pada kondisi pH awal, kecepatan alir gas CO2, kecepatan alir cairan, dan suhu masing-masing pada 8,7; 2265 mL/menit; 10 mL/menit; dan 303 K, dengan konversi sebesar 38,40%. Produk berupa CaCO3, yang diperoleh mempunyai kemurnian sebesar 21,34%.

  3. Perhitungan Kebutuhan Cooling Tower Pada Rancang Bangun Untai Uji Sistem Kendali Reaktor Riset

    OpenAIRE

    Awwaluddin, Muhammad; Santosa, Puji; Suwardiyono, Suwardiyono

    2012-01-01

    CALCULATION OF THE NEED FOR COOLING TOWER ON DESIGN OF STRAND TEST RESEARCH REACTOR CONTROL SYSTEM. Cooling tower on the strand test engineering research reactor control system functioning as a heat transfer medium from the heat exchanger to air. To get the transfer of heat or cooling is maximal then the determination of cooling tower needs to be precise. Cooling tower is expected to accept and release heat at 1.191 kw from the heat exchanger. To support these needs will require the calculati...

  4. MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR

    Directory of Open Access Journals (Sweden)

    Suwardi Suwardi

    2015-03-01

    Full Text Available MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR*. The first short fuel pin containing natural UO2 pellet in Zry4 cladding has been prepared at the CNFT (Center for Nuclear Fuel Technology then a ramp test will be performed. The present work is part of designing first irradiation experiments in the PRTF (Power Ramp Test Facility of RSG-GAS 30 MW reactor. The thermal mechanic of the pin during irradiation has simulated. The geometry variation of pellet and cladding is modeled by taking into account different phenomena such as thermal expansion, densification, swelling by fission product, thermal creep and radiation growth. The cladding variation is modeled by thermal expansion, thermal and irradiation creeps. The material properties are modeled by MATPRO and standard numerical parameter of TRANSURANUS code. Results of irradiation simulation with 9 kW/m LHR indicates that pellet-clad contacts onset from 0.090 mm initial gaps after 806 d, when pellet radius expansion attain 0.015 mm while inner cladding creep-down 0.075 mm. A newer computation data show that the maximum measured LHR of n-UO2 pin in the PRTF 12.4 kW/m. The next simulation will be done with a higher LHR, up to ~ 25 kW/m. MODEL SIMULASI VARIASI GEOMETRI DAN STRESS-STRAIN DARI PROTOTIP BAHAN BAKAR PIN BATAN SELAMA UJI IRADIASI DI REAKTOR RSG-GAS. Pusat Teknologi Bahan Bakar Nuklir (PTBBN telah menyiapkan tangkai (pin bahan bakar pendek perdana yang berisi pelet UO2 alam dalam kelongsong paduan zircaloy untuk dilakukan uji iradiasi daya naik. Penelitian ini merupakan bagian dari perancangan percobaan iradiasi pertama di PRTF (Power Ramp Test Fasility yang terpasang di reaktor serbaguna RSG-GAS berdaya 30 MW. Telah dilakukan pemodelan dan simulasi kinerja termal mekanikal pin selama iradiasi. Variasi geometri pelet dan kelongsong selama pengujian dimodelkan dengan memperhatikan fenomena ekspansi termal

  5. The role of FRET in solar concentrator efficiency and color tunability

    Energy Technology Data Exchange (ETDEWEB)

    Balaban, Benjamin, E-mail: bbalaban@ucsc.edu; Doshay, Sage; Osborn, Melissa; Rodriguez, Yvonne; Carter, Sue A., E-mail: sacarter@ucsc.edu

    2014-02-15

    We demonstrate concentration-dependent Förster-type energy transfer in a luminescent solar concentrator (LSC) material containing two high quantum yield laser dyes in a PMMA matrix. FRET heterotransfer is shown to be approximately 50% efficient in the regime of 2×10{sup −3}molal acceptor dye by weight in the host polymer. The two dyes used have been well studied for solar concentrator applications: BASF's Lumogen Red 305, and Exciton Chemical Company's DCM both demonstrate desirable stability, quantum yield, and complementary absorption spectra. We demonstrate how multiple-dye LSC devices employing FRET increase the absorption of air mass 1.5 solar irradiance without affecting the self-absorption properties of the film. Color tunability may be achieved through the addition of additional absorbers while minimizing the impact on waveguide efficiency. -- Highlights: • Förster Resonance Energy Transfer is demonstrated in a two-dye luminescent solar concentrator. • Donor-acceptor pair distance is related to the dye concentration in PMMA. • FRET's benefit to waveguide transport losses and color tunability is discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-15

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

  7. Shielding design of highly activated sample storage at reactor TRIGA PUSPATI

    International Nuclear Information System (INIS)

    Naim Syauqi Hamzah; Julia Abdul Karim; Mohamad Hairie Rabir; Muhd Husamuddin Abdul Khalil; Mohd Amin Sharifuldin Salleh

    2010-01-01

    Radiation protection has always been one of the most important things considered in Reaktor Triga PUSPATI (RTP) management. Currently, demands on sample activation were increased from variety of applicant in different research field area. Radiological hazard may occur if the samples evaluation done were misjudge or miscalculated. At present, there is no appropriate storage for highly activated samples. For that purpose, special irradiated samples storage box should be provided in order to segregate highly activated samples that produce high dose level and typical activated samples that produce lower dose level (1 - 2 mR/ hr). In this study, thickness required by common shielding material such as lead and concrete to reduce highly activated radiotracer sample (potassium bromide) with initial exposure dose of 5 R/ hr to background level (0.05 mR/ hr) were determined. Analyses were done using several methods including conventional shielding equation, half value layer calculation and Micro shield computer code. Design of new irradiated samples storage box for RTP that capable to contain high level gamma radioactivity were then proposed. (author)

  8. Heat and fuel coupled operation of a high temperature polymer electrolyte fuel cell with a heat exchanger methanol steam reformer

    Science.gov (United States)

    Schuller, G.; Vázquez, F. Vidal; Waiblinger, W.; Auvinen, S.; Ribeirinha, P.

    2017-04-01

    In this work a methanol steam reforming (MSR) reactor has been operated thermally coupled to a high temperature polymer electrolyte fuel cell stack (HT-PEMFC) utilizing its waste heat. The operating temperature of the coupled system was 180 °C which is significantly lower than the conventional operating temperature of the MSR process which is around 250 °C. A newly designed heat exchanger reformer has been developed by VTT (Technical Research Center of Finland LTD) and was equipped with commercially available CuO/ZnO/Al2O3 (BASF RP-60) catalyst. The liquid cooled, 165 cm2, 12-cell stack used for the measurements was supplied by Serenergy A/S. The off-heat from the electrochemical fuel cell reaction was transferred to the reforming reactor using triethylene glycol (TEG) as heat transfer fluid. The system was operated up to 0.4 A cm-2 generating an electrical power output of 427 Wel. A total stack waste heat utilization of 86.4% was achieved. It has been shown that it is possible to transfer sufficient heat from the fuel cell stack to the liquid circuit in order to provide the needed amount for vaporizing and reforming of the methanol-water-mixture. Furthermore a set of recommendations is given for future system design considerations.

  9. Effect of microencapsulated phase change material in sandwich panels

    Energy Technology Data Exchange (ETDEWEB)

    Castellon, Cecilia; Medrano, Marc; Roca, Joan; Cabeza, Luisa F. [GREA Innovacio Concurrent, Edifici CREA, Universitat de Lleida, Pere de Cabrera s/n, 25001 Lleida (Spain); Navarro, Maria E.; Fernandez, Ana I. [Departamento de Ciencias de los Materiales e Ingenieria Metalurgica, Universitat de Barcelona, Marti i Franques 1, 08028 Barcelona (Spain); Lazaro, Ana; Zalba, Belen [Instituto de Investigacion en Ingenieria de Aragon, I3A, Grupo de Ingenieria Termica y Sistemas Energeticos (GITSE), Dpto. Ingenieria Mecanica, Area de Maquinas y Motores Termicos, Universidad de Zaragoza, Campus Politecnico Rio Ebro, Edificio ' ' Agustin de Betancourt,' ' Maria de Luna s/n, 50018 Zaragoza (Spain)

    2010-10-15

    Sandwich panels are a good option as building materials, as they offer excellent characteristics in a modular system. The goal of this study was to demonstrate the feasibility of using the microencapsulated PCM (Micronal BASF) in sandwich panels to increase their thermal inertia and to reduce the energy demand of the final buildings. In this paper, to manufacture the sandwich panel with microencapsulated PCM three different methods were tested. In case 1, the PCM was added mixing the microencapsulated PCM with one of the components of the polyurethane. In the other two cases, the PCM was added either a step before (case 2) or a step after (case 3) to the addition of the polyurethane to the metal sheets. The results show that in case 1 the effect of PCM was overlapped by a possible increase in thermal conductivity, but an increase of thermal inertia was found in case 3. In case 2, different results were obtained due to the poor distribution of the PCM. Some samples showed the effect of the PCM (higher thermal inertia), and other samples results were similar to the conventional sandwich panel. In both cases (2 and 3), it is required to industrialize the process to improve the results. (author)

  10. KONVERSI KATALITIK MINYAK SAWIT UNTUK MENGHASILKAN BIOFUEL MENGGUNAKAN SILIKA ALUMINA DAN HZSM-5 SINTESIS

    Directory of Open Access Journals (Sweden)

    Nurjannah Nurjannah

    2012-02-01

    Full Text Available Terbatasnya sumber energi fosil menyebabkan perlunya pengembangan energi terbarukan yang berasal dari alam dan dapat diperbaharui. Penggunaan bahan bakar minyak bumi, baik dari penggunaan berupa alat transportasi maupun dari penggunaan oleh industri sangat mencemari lingkungan karena tingkat polusi yang ditimbulkan sangat tinggi sehingga perlu mencari bahan bakar alternatif pengganti bahan bakar gasoline, solar, dan kerosene dari minyak nabati. Penelitian dilakukan dalam dua tahapan yaitu sintesa katalis dan proses katalitik cracking. Silika alumina disintesa menggunakan metode Latourette dan HZSM-5 disintesa menggunakan metode Plank. Hasil sintesa dikarakterisasi dengan Penyerapan Spektroskopi Atomis (AAS menunjukkan bahwa silika alumina dan HZSM-5 mempunyai Si/Al 198 dan 243. Luas permukaan  silika alumina dan HZSM-5 diperoleh dari analisa Brunauer Emmet Teller (BET yaitu 149,91-213,35 m2.g-1 dan ukuran pori rata-rata adalah 13oA. Perengkahan katalitik dilakukan dalam suatu mikroreaktor fixed bed pada temperatur 350-500°C dan laju alir gas N2 100-160 ml.min-1 selama 120 min. Hasil perengkahan dianalisa dengan metode gas kromatografi. Hasil yang diperoleh untuk katalis HZSM-5 fraksi gasoline dengan yield tertinggi 28,87%, kerosene 16,70%, dan diesel 12,20%  pada suhu reaktor 4500C dan laju gas N2 100 ml/menit.

  11. Nuclear fuel in water reactors: Manufacturing technology, operational experience and development objectives in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Holzer, R.; Knoedler, D.

    1977-01-01

    The nuclear fuel industry in the Federal Republic of Germany comprises the full range of manufacturing capabilities for pressurized-, boiling- and heavy-water reactor technology. The existing manufacturing companies are Reaktor-Brennelement Union (RBU) and Alkem. RBU makes natural and enriched UO 2 -fuel assemblies, starting with powder preparation. Facilities to produce UO 2 -gadolinia and UO 2 -ThO 2 fuel are also available. Alkem manufactures mixed-oxide UO 2 /PuO 2 fuel and fuel rods. Zircaloy cladding tubes are produced by Nuklearrohr-Gesellschaft (NRG) and Mannesmannroehren-Werke (MRW). Construction of a new fuel manufacturing plant has been announced by Exxon. Supplementary to quality control, an integrated quality assurance system has been established between the reactor vendor's fuel design and engineering division and the existing manufacturing companies for fuel and tubing. Operating experience with LWR and HWR fuel dates back to 1964/65 and has shown good performance. Possible reasons for a small fraction of defective rods could be identified quickly by a fast feedback system incorporating close co-operation between Kraftwerk Union (KWU) and the utilities. KWU combines fuel development, hot-cell and pool-side service facilities as well as fuel technology linked to manufacturing. The responsibility of KWU for core and fuel design, which enabled an integral optimization, was also an important reason for the successful operation and design flexibility. (author)

  12. PCM Concrete. [Phase Change Materials

    Energy Technology Data Exchange (ETDEWEB)

    Juul Andersen, T. [Danish Technological Institute, Taastrup (Denmark); Poulsen, H.-H. [BASF A/S, Roedekro (Denmark); Passov, F. [Spaencom A/S, Hedehusene (Denmark); Heiselberg, P. [Aalborg Univ..Aalborg (Denmark)

    2013-04-01

    PCM-Concrete was a research and development project launched in 2009 and finished in 2012. The project, which was funded by The Danish National Advanced Technology Foundation, had a total budget of 1.7 million Euros and included 4 partners: Danish Technological Institute (project manager), Aalborg University, BASF A/S and Spaencom A/S. The overall vision of the project was to reduce energy consumption for heating and cooling in buildings by developing high-performance concrete structures microencapsulated Phase Change Materials (PCM). The PCM used in the project was Micronal produced by BASF A/S. Micronal is small capsules with an acrylic shell and inside a wax with a melting point at approx. 23 deg. C equal to a comfortable indoor temperature. During the melting process thermal energy is transferred to chemical reaction (melting/solidification) depending on PCM being heated up or cooled down. Adding Micronal to concrete would theoretically increase the thermal mass of the concrete and improve the diurnal heat capacity which is the amount of energy that can be stored and released during 24 hours. Nevertheless, it is a relatively new technology that has not received much attention, yet. In the PCM-Concrete project 5 main investigations were carried out: 1) Development of concrete mix design with PCM. 2) Investigation of thermal properties of the PCM concrete: thermal conductivity, specific heat capacity, density. 3) Up-scaling the research to industrial production of PCM-concrete structures. 4) Testing energy efficiency in full scale. 5) Confronting aesthetic and acoustic barriers to full exploitation of the potential of PCM-concrete structures. The results from the test program showed: 1) That the diurnal heat storage capacity is higher for all 4 hollow core decks with tiles attached compared to the reference hollow core deck. 2) The hollow core decks with concrete tiles without PCM performs slightly better than the tiles with PCM. 3) That is was impossible to

  13. Investigations of co-combustion of plastics in a coal dust furnace; Untersuchungen zur Mitverbrennung von Kunststoffen in einer Kohlestaubfeuerung

    Energy Technology Data Exchange (ETDEWEB)

    Gerhardt, T; Spliethoff, H; Hein, K R.G. [Stuttgart Univ. (Germany). Inst. fuer Verfahrenstechnik und Dampfkesselwesen (IVD); Christill, M; Kicherer, A; Seifert, H [BASF AG, Verfahrenstechnik-ZET/EH-L544, Ludwigshafen am Rhein (Germany)

    1997-12-31

    In a cooperation project of the Institute of Process Engineering and Power Plant TEchnology (IVD) at the University of Stuttgart and the BASF AG, investigations of co-combustion of plastic material in a coal dust furnace were carried out. The central question of the research work was the ignition and burnout of the particles in dependence of the residence time in the hot part of the furnace. Particle sizes were varied with the aim to define the largest possible particle size in order to minimize the cost of fuel preparation by grinding. On the other hand, tests were made with pure materials and synthetic mixtures of these in order to characterize the influence of different types of plastic. The investigations showed that plastics are suited as fuels for coal dust furnaces, and that the cost of fuel preparation can be reduced to an acceptable level. With polyethylene, which is difficult to ignite, an upper particle size limit of 1.25 to 1.5 mm was reached in the IVD test stand. In industrial applications with a different burner arrangement, even better results may be expected. (orig/AKB) [Deutsch] In einer Zusammenarbeit zwischen dem Institut fuer Verfahrenstechnik und Dampfkesselwesen (IVD) der Universitaet Stuttgart und der BASF AG wurden Versuche zur Coverbrennung von Kunststoffen in einer Kohlenstaubfeuerung durchgefuehrt. Im Mittelpunkt der Untersuchungen standen Zuendung und Abbrand der Kunststoffpartikel in Abhaengigkeit von der Verweilzeit im heissen Bereich der Brennkanner. Variiert wurden hierzu zum einen die Partikelgroessen mit dem Ziel, den Aufbereitungsaufwand durch Zerkleinerung zu minimieren. Zur Charakterisierung der Einfluesse verschiedener Kunststoffarten wurden die Versuche mit unterschiedlichen Reinkunststoffen und synthetischen Mischungen durchgefuehrt. Die Versuche zeigen, dass sich Kunststoffe mit vertretbarem Mahlaufwand in der Staubfeuerung einsetzen lassen. Am Beispiel des Polyethylen, eines der thermogravimetrischen Analyse nach relativ

  14. Investigations of co-combustion of plastics in a coal dust furnace; Untersuchungen zur Mitverbrennung von Kunststoffen in einer Kohlestaubfeuerung

    Energy Technology Data Exchange (ETDEWEB)

    Gerhardt, T.; Spliethoff, H.; Hein, K.R.G. [Stuttgart Univ. (Germany). Inst. fuer Verfahrenstechnik und Dampfkesselwesen (IVD); Christill, M.; Kicherer, A.; Seifert, H. [BASF AG, Verfahrenstechnik-ZET/EH-L544, Ludwigshafen am Rhein (Germany)

    1996-12-31

    In a cooperation project of the Institute of Process Engineering and Power Plant TEchnology (IVD) at the University of Stuttgart and the BASF AG, investigations of co-combustion of plastic material in a coal dust furnace were carried out. The central question of the research work was the ignition and burnout of the particles in dependence of the residence time in the hot part of the furnace. Particle sizes were varied with the aim to define the largest possible particle size in order to minimize the cost of fuel preparation by grinding. On the other hand, tests were made with pure materials and synthetic mixtures of these in order to characterize the influence of different types of plastic. The investigations showed that plastics are suited as fuels for coal dust furnaces, and that the cost of fuel preparation can be reduced to an acceptable level. With polyethylene, which is difficult to ignite, an upper particle size limit of 1.25 to 1.5 mm was reached in the IVD test stand. In industrial applications with a different burner arrangement, even better results may be expected. (orig/AKB) [Deutsch] In einer Zusammenarbeit zwischen dem Institut fuer Verfahrenstechnik und Dampfkesselwesen (IVD) der Universitaet Stuttgart und der BASF AG wurden Versuche zur Coverbrennung von Kunststoffen in einer Kohlenstaubfeuerung durchgefuehrt. Im Mittelpunkt der Untersuchungen standen Zuendung und Abbrand der Kunststoffpartikel in Abhaengigkeit von der Verweilzeit im heissen Bereich der Brennkanner. Variiert wurden hierzu zum einen die Partikelgroessen mit dem Ziel, den Aufbereitungsaufwand durch Zerkleinerung zu minimieren. Zur Charakterisierung der Einfluesse verschiedener Kunststoffarten wurden die Versuche mit unterschiedlichen Reinkunststoffen und synthetischen Mischungen durchgefuehrt. Die Versuche zeigen, dass sich Kunststoffe mit vertretbarem Mahlaufwand in der Staubfeuerung einsetzen lassen. Am Beispiel des Polyethylen, eines der thermogravimetrischen Analyse nach relativ

  15. KETAHANAN KOROSI PADUAN Al-Mg 5052 DI DALAM AIR PENDINGIN NETRAL MENGANDUNG KLORIDA

    Directory of Open Access Journals (Sweden)

    Dicky Tri Jatmiko

    2015-07-01

    Full Text Available KETAHANAN KOROSI PADUAN Al-Mg 5052 DI DALAM AIR PENDINGIN NETRAL MENGANDUNG KLORIDA. Paduan Al-Mg 5052 adalah material yang biasa digunakan untuk kelongsong elemen bakar nuklir karena serapan fluks netronnya rendah dan tahan korosi di dalam air demineralisasi pada kondisi operasi reaktor. Makalah ini difokuskan untuk mengetahui ketahanan korosi paduan Al-Mg 5052 di dalam air dengan pH netral dan mengandung klorida sebagai pengganti air demineralisasi pendingin primer Reaktor Serba Guna GA Siwabessy (RSG-GAS. Penelitian mencakup pengukuran laju korosi menggunakan metode Tafel, prediksi mekanisme korosi menggunakan metode voltametri siklik dan analisa produk korosi dengan metode difraksi sinar X. Percobaan dilakukan dengan variasi temperatur 30°C, 35°C, 40°C, dan 45°C, serta variasi konsentrasi larutan natrium  klorida 0,05 M, 0,25 M, dan 0,5 M. Hasil penelitian ini menunjukkan bahwa paduan Al-Mg 5052 terkorosi dengan kategori “dapat diabaikan” hingga “sedang” dalam larutan natrium klorida menjadi produk yang larut dalam air pada satu tahap reaksi oksidasi irreversible.   CORROSION RESISTANCE OF Al-Mg ALLOY 5052 IN CHLORIDE CONTAINING NEUTRAL COOLING WATER. Al-Mg alloy 5052 is a material used as nuclear fuel element cladding due to its low neutron flux absorption and high corrosion resistance in demineralized water. This research is focused to know of the corrosion resistance of Al-Mg alloy 5052 in chloride containing neutral water used as demineralized primary cooling water substitute in GA Siwabessy Multi Purpose Reactor (RSG-GAS. This research covers the corrosion rate measurement using the Tafel method, corrosion process prediction using cyclic voltammetry method and corrosion product analysis using X-Ray Diffraction method. The experiments are carried out at temperature variation of 30°C, 35°C, 40°C and 45°C, as well as sodium chloride concentration of 0.05 M, 0.25 M and 0.5 M. The research results show that Al-Mg alloy 5052

  16. Commissioning Experience from the Agesta Nuclear Power Plant; Experience acquise lors des essais de mise en service de la centrale nucleaire d'Agesta; Opyt po vvedeniyu v ehkspluatatsiyu yadernoj ehnergeticheskoj ustanovki Agesta; Experiencia adquirida con la puesta en marcha de la central nucleoelectrica de Agesta

    Energy Technology Data Exchange (ETDEWEB)

    Rydell, N. [Aagesta Kraftvarmewerk, Farsta (Sweden)

    1963-10-15

    The Agesta Nuclear Power Plant is a pressurized heavy water reactor of the pressure vessel type, fuelled with natural uranium. It was commissioned with light water from December 1962 to May 1963. Observations of a more general interest were made during this commissioning essentially on the following topics; (a) cleanliness of primary circuit (b) valve operation (c) pressurization of the primary circuit (d) water leakage (e) refuelling machinery (f) containment testing. (author) [French] Il s'agit d'un reacteur a uranium naturel et a eau lourde pressurisee, du type a caisson sous pression. Les essais de mise en service ont ete faits avec de l'eau ordinaire, de decembre 1962 a mai 1963. La mise en service a permis de faire des observations d'interet general sur les sujets suivants: a) non-contamination du circuit primaire; b) fonctionnement des vannes; c) maintien sous pression du circuit primaire; d) fuites d'eau; e) appareils de chargement du combustible; f) essais d'isolement. (author) [Spanish] La central nucleoelectrica de Agesta posee un reactor de agua pesada del tipo de recipiente de presion, con combustible de uranio natural. Se mantuvo en funcionamiento con agua ligera entre diciembre de 1962 y mayo de 1963. Durante esta prueba, se efectuaron observaciones de interes mas general, relacionadas esencialmente con las siguientes cuestiones: a) limpieza del circuito primario; b) funcionamiento de las valvulas; c) presion del circuito primario; d) perdidas de agua; e) dosposiciones de reposicion del Combustible; f) ensayos de confinamiento. (author) [Russian] Yadernaya ehnergeticheskaya ustanovka Agesta predstavlyaet soboj tyazhelovodnyj reaktor pod davleniem, ispol'zuyushchij prirodnyj uran v kachestve topliva. Reaktor byl vveden v ehkspluatatsiyu na obychnoj vode v period s dekabrya 1962 goda po maj 1963 goda. Zamechaniya bolee obshchego kharaktera byli sdelany vo vremya ehkspluatatsii v osnovnom po sledukhshchim temam: a) chistota pervichnogo kontura; b

  17. Scientific Opinion on the substantiation of a health claim related to an equimolar mixture of the CLA isomers c9,t11 and t10,c12 (marketed as Clarinol® and Tonalin®) and “contributes to a reduction in body fat mass” pursuant to Article 13(5) of Regulation

    DEFF Research Database (Denmark)

    Tetens, Inge

    2015-01-01

    Following an application from BASF SE and Stepan Lipid Nutrition, submitted for the authorisation of a health claim pursuant to Article 13(5) of Regulation (EC) No 1924/2006 via the Competent Authority of the Netherlands, the EFSA Panel on Dietetic Products, Nutrition and Allergies (NDA) was asked...... to deliver an opinion on the scientific substantiation of a health claim related to an equimolar mixture (marketed under the trade names Clarinol® and Tonalin®) of the two conjugated linoleic acid (CLA) isomers c9,t11 and t10,c12. The Panel considers that the food is sufficiently characterised. The claimed...... of the CLA isomers c9,t11 and t10,c12, marketed under the trade names of Clarinol® and Tonalin®, and a beneficial physiological effect....

  18. Use of surfactants in cleaning paraffin from oil wells

    Energy Technology Data Exchange (ETDEWEB)

    Liebold, G; Rehberg, W

    1969-05-01

    The use of surfactants is described especially oxethylated alkylphenols, in the cleaning of oil wells from paraffin. Aqueous 1 or 10% solutions of the surfactant were injected into the well through the annulus, partially in combination with demulsifiers (for example Separol-brands of BASF). Injection was accomplished continuously or in intervals; in the beginning of 50 ppm surfactant, afterward 15 to 30 ppm as related to the wet crude was necessary. Efficiency of the treatment could be proved by the decrease of pressure in the pipes, the loosening of paraffin shells, and considerably prolonged operation periods in wells which otherwise would have come to a standstill. In quite a number of wells, treatment with hot oil and electric heating could be completely replaced by injection of surfactants. (11 refs.)

  19. Platinum Group Metal Recycling Technology Development - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence Shore

    2009-08-19

    BASF Catalysts LLC, formerly Engelhard Corporation, has completed a project to recover Pt from PEM fuel cell membrane electrode assemblies. The project, which began in 2003, has met the project objective of an environmentally-friendly, cost-effective method for recovery of platinum without release of hydrogen fluoride. This has been achieved using a combination of milling, dispersion and acid leaching. 99% recovery of Pt was achieved, and this high yield can be scaled up using one vessel for a single leach and rinse. Leaching was been successfully achieved using a 10% solids level, double the original target. At this solids content, the reagent and utility costs represent ~0.35% of the Pt value of a lot, using very conservative assumptions. The main cost of the process is capital depreciation, followed by labor.

  20. Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

    Science.gov (United States)

    Karim, Julia Abdul

    2008-05-01

    The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained.

  1. Core Calculation of 1 MWatt PUSPATI TRIGA Reactor (RTP) using Monte Carlo MVP Code System

    International Nuclear Information System (INIS)

    Karim, Julia Abdul

    2008-01-01

    The Monte Carlo MVP code system was adopted for the Reaktor TRIGA PUSAPTI (RTP) core calculation. The code was developed by a group of researcher of Japan Atomic Energy Agency (JAEA) first in 1994. MVP is a general multi-purpose Monte Carlo code for neutron and photon transport calculation and able to estimate an accurate simulation problems. The code calculation is based on the continuous energy method. This code is capable of adopting an accurate physics model, geometry description and variance reduction technique faster than conventional method as compared to the conventional scalar method. This code could achieve higher computational speed by several factors on the vector super-computer. In this calculation, RTP core was modeled as close as possible to the real core and results of keff flux, fission densities and others were obtained

  2. Determination of bedrock depth by using microtremor array survey at the RDE Site Serpong

    International Nuclear Information System (INIS)

    Hadi Suntoko; Sriyana

    2016-01-01

    Based on the Strategic Spatial Planning (RTRW) of Tangerang Selatan 2011-2031, PUSPIPTEK Serpong has been appointed as high technology zone, therefore this area is selected as the site for Experimental Power Reactor (Reaktor Daya Eksperimental, RDE). In order to assure safety, site evaluation from several aspects have to be performed, one of which is seismological aspect. Refer to BAPETEN Chairman Regulation No. 8 year 2013, site evaluation should cover the assessment of subsurface geological condition of the site. The objective of this study is to acquire information regarding the subsurface geological condition particularly the bedrock depth of the RDE site area. Method used in this study is micro tremor array (MA). The result shows that RDE site has a bedrock type of Bojongmanik Formation at a depth of 391 meter from the surface. (author)

  3. Fuel element transfer cask modelling using MCNP technique

    International Nuclear Information System (INIS)

    Rosli Darmawan

    2009-01-01

    Full text: After operating for more than 25 years, some of the Reaktor TRIGA PUSPATI (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement. (author)

  4. Fuel Element Transfer Cask Modelling Using MCNP Technique

    International Nuclear Information System (INIS)

    Darmawan, Rosli; Topah, Budiman Naim

    2010-01-01

    After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.

  5. The Ellweiler uranium plant - a demolition and recycling project

    International Nuclear Information System (INIS)

    Mika, S.; Rohr, T.; Seehars, R.; Feser, A.

    1999-01-01

    The uranium plant at Ellweiler, district of Birkenfeld, was used for the production and storage of uranium concentrates. The owner of the Ellweiler uranium plant (UAE), Gewerkschaft Brunhilde GmbH, ceased processing uranium ore and recycling in 1989 and has been in liquidation since September 1991. The State of Rhineland-Palatinate, had safety measures adopted in a first step, getting the plant into a safe state by former plant personnel. The entire plant was demolished in a second step. The contract for demolishing the former uranium plant was awarded to ABB Reaktor as the general contractor in August 1996. Demolition work was carried out between April 1997 and May 1999. A total of approx. 7900 Mg of material was disposed of. At present, recultivation measures are being carried out. (orig.) [de

  6. Preparation and Characterization of Microencapsulated Phase Change Materials for Use in Building Applications

    Directory of Open Access Journals (Sweden)

    Jessica Giro-Paloma

    2015-12-01

    Full Text Available A method for preparing and characterizing microencapsulated phase change materials (MPCM was developed. A comparison with a commercial MPCM is also presented. Both MPCM contained paraffin wax as PCM with acrylic shell. The melting temperature of the PCM was around 21 °C, suitable for building applications. The M-2 (our laboratory made sample and Micronal® DS 5008 X (BASF samples were characterized using SEM, DSC, nano-indentation technique, and Gas Chromatography/Mass spectrometry (GC-MS. Both samples presented a 6 μm average size and a spherical shape. Thermal energy storage (TES capacities were 111.73 J·g−1 and 99.3 J·g−1 for M-2 and Micronal® DS 5008 X, respectively. Mechanical characterization of the samples was performed by nano-indentation technique in order to determine the elastic modulus (E, load at maximum displacement (Pm, and displacement at maximum load (hm, concluding that M-2 presented slightly better mechanical properties. Finally, an important parameter for considering use in buildings is the release of volatile organic compounds (VOC’s. This characteristic was studied at 65 °C by CG-MS. Both samples showed VOC’s emission after 10 min of heating, however peaks intensity of VOC’s generated from M-2 microcapsules showed a lower concentration than Micronal® DS 5008 X.

  7. Enhanced activity and interfacial durability study of ultra low Pt based electrocatalysts prepared by ion beam assisted deposition (IBAD) method

    International Nuclear Information System (INIS)

    Ramaswamy, N.; Arruda, T.M.; Wen, W.; Hakim, N.; Saha, M.; Gulla, A.; Mukerjee, S.

    2009-01-01

    Ultra low loading noble metal (0.04-0.12 mg Pt /cm 2 ) based electrodes were obtained by direct metallization of non-catalyzed gas diffusion layers via dual ion beam assisted deposition (IBAD) method. Fuel cell performance results reported earlier indicate significant improvements in terms of mass specific power density of 0.297 g Pt /kW with 250 A thick IBAD deposit (0.04 mg Pt /cm 2 for a total MEA loading of 0.08 mg Pt /cm 2 ) at 0.65 V in contrast to the state of the art power density of 1.18 g Pt /kW using 1 mg Pt(MEA) /cm 2 at 0.65 V. In this article we report the peroxide radical initiated attack of the membrane electrode assembly utilizing IBAD electrodes in comparison to commercially available E-TEK (now BASF Fuel Cell GmbH) electrodes and find the pathway of membrane degradation as well. A novel segmented fuel cell is used for this purpose to relate membrane degradation to peroxide generation at the electrode/electrolyte interface by means of systematic pre and post analyses of the membrane are presented. Also, we present the results of in situ X-ray absorption spectroscopy (XAS) experiments to elucidate the structure/property relationships of these electrodes that lead to superior performance in terms of gravimetric power density obtained during fuel cell operation.

  8. Preparation and Characterization of Microencapsulated Phase Change Materials for Use in Building Applications.

    Science.gov (United States)

    Giro-Paloma, Jessica; Al-Shannaq, Refat; Fernández, Ana Inés; Farid, Mohammed M

    2015-12-26

    A method for preparing and characterizing microencapsulated phase change materials (MPCM) was developed. A comparison with a commercial MPCM is also presented. Both MPCM contained paraffin wax as PCM with acrylic shell. The melting temperature of the PCM was around 21 °C, suitable for building applications. The M-2 (our laboratory made sample) and Micronal ® DS 5008 X (BASF) samples were characterized using SEM, DSC, nano-indentation technique, and Gas Chromatography/Mass spectrometry (GC-MS). Both samples presented a 6 μm average size and a spherical shape. Thermal energy storage (TES) capacities were 111.73 J·g -1 and 99.3 J·g -1 for M-2 and Micronal ® DS 5008 X, respectively. Mechanical characterization of the samples was performed by nano-indentation technique in order to determine the elastic modulus ( E ), load at maximum displacement ( P m ), and displacement at maximum load ( h m ), concluding that M-2 presented slightly better mechanical properties. Finally, an important parameter for considering use in buildings is the release of volatile organic compounds (VOC's). This characteristic was studied at 65 °C by CG-MS. Both samples showed VOC's emission after 10 min of heating, however peaks intensity of VOC's generated from M-2 microcapsules showed a lower concentration than Micronal ® DS 5008 X.

  9. Change of I-V characteristics of SiC diodes upon reactor irradiation; Modification des caracteristiques I-V de jonctions p-n au SiC du fait d'une irradiation dans un reacteur; Izmeneniya kharakteristik I-V vyrashchennogo v SiC perekhoda tipa p-n posle oblucheniya ego v reaktore; Modificaciones que sufren por irradiacion en un reactor las caracteristicas I-V de uniones p-n en SiC

    Energy Technology Data Exchange (ETDEWEB)

    Heerschap, M; De Coninck, R [Solid State Physics Dept., SCK-CEN, Mol (Belgium)

    1962-04-15

    distintas procedencias. Las uniones se obtuvieron en el horno de Lely. Midieron las caracteristicas directa e inversa durante la irradiacion, y despues de esta, hasta la temperatura de 150{sup o}C. Se estan realizando mediciones hasta 500{sup o}C. Han encontrado que uno de los tipos de diodo es resistente a los neutrones del BR-1 hasta un flujo integrado de 10{sup 15} neutrones/cm{sup 2}, mientras que el otro soporta hasta 10{sup 17} neutrones/cm{sup 2}. La memoria indica los cambios de las caracteristicas, asi como los resultados de algunos experimentos de recocido. (author) [Russian] V poiskakh poluprovodnikov, kotorye mogli by byt' ispol'zovany v reaktorakh s vysokoj plotnost'yu nejtronnogo potoka dlya izmereniya raspredeleniya potokov, my obluchali v bel'gijskom reaktore BR-1 perekhody tipa p-n v SiC. Byli oblucheny dva tipa diodov SiC razlichnogo proiskhozhdeniya. EHti perekhody vyrashchivayutsya v pechi Loli. Izmeneniya pryamoj i obratnoj kharakteristik byli izmereny posle i vo vremya oblucheniya vplot' do temperatury 150{sup o}C; v nastoyashchee vremya proizvodyatsya izmereniya vplot' do temperatury 500{sup o}C. Bylo ustanovleno, chto odin tip dioda vyderzhivaet nejtronnoe obluchenie reaktora BR-1 vplot' do integrirovannogo potoka 10{sup 15} nejtronov na kv. sm, togda kak drugoj tip vyderzhivaet obluchenie vplot' do potoka 10{sup 17} nejtronov na kv. sm. Dayutsya izmeneniya kharakteristik, a takzhe rezul'taty nekotorykh ehksperimentov otzhiga. (author)

  10. UNJUK KERJA REAKTOR PLASMA DIELECTRIC BARRIER DISCHARGE UNTUK PRODUKSI BIODIESEL DARI MINYAK KELAPA SAWIT

    Directory of Open Access Journals (Sweden)

    Ardian Dwi Yudhistira

    2013-10-01

    Full Text Available Biodiesel is one of alternative renewable energy source to substitute diesel fuel. Various biodiesel productionprocesses through transesterification reaction with a variety of catalysts have been developed by previousresearcher. This process still has the disadvantage of a long reaction time, and high energy need. DielectricBarrier Discharge (DBD plasma electro-catalysis may become a solution to overcome the drawbacks in theconventional transesterification process. This process only needs a short time reaction and low energy process.The purpose of this study was to assess the performance of DBD plasma rector in making biodiesel such as: theeffect of high voltage electric value, electrodes gap, mole ratio of methanol / oil, and reaction time. TheResearch method was using GC-MS (Gas Cromatography-Mass Spectrofotometry and FTIR (FourierTransform Infrared Spectrofotometry and then it will be analysed the change of chemical bond betweenreactant and product. So, the reaction mechanism can be predicted. Biodiesel is produced using methanol andpalm oil as reactants and DBD plasma used as reactor in batch system. Then, reactants contacted by highvoltage electric. From the results of this research can be concluded that the reaction mechanism occurs in theprocess is the reaction mechanism of cracking, the higher of electric voltage and the longer of reaction time leadto increasing of product yield. The more of mole ratio of methanol / oil and widening the gap between theelectrodes lead to decreased product yield. From this research, product yield maksimum is 89,8% in the variableof rasio mol metanol/palm oil 3:1, voltage 10 kV, electrode gap 1,5 cm, and reaction time 30 seconds.

  11. Nový úkol hybridních reaktorů – likvidace jaderného odpadu

    Czech Academy of Sciences Publication Activity Database

    Řípa, Milan

    2009-01-01

    Roč. 57, č. 11 (2009), s. 24-a33 ISSN 0040-1064 Institutional research plan: CEZ:AV0Z20430508 Keywords : fusion * ITER * hybrid * nuclear waste * LIFE * FFTS * CFNS * SXD * FDF Subject RIV: BL - Plasma and Gas Discharge Physics

  12. Research reactor 'A' 6.5/10 MW; Istrazivacki reaktor 'A' 6,5/10 MW

    Energy Technology Data Exchange (ETDEWEB)

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

    1961-07-01

    This booklet includes a short description of the RA research reactor with basic properties of its components: control and safety system, heavy water system, technical water cooling system, heavy water distillation system, cover gas system, dosimetry control system, power supply system. It is used for fundamental research in reactor and nuclear physics, isotope production, materials testing.

  13. Status of the calibration and alignment framework at the Belle II experiment

    Science.gov (United States)

    Dossett, D.; Sevior, M.; Ritter, M.; Kuhr, T.; Bilka, T.; Yaschenko, S.; Belle Software Group, II

    2017-10-01

    The Belle II detector at the Super KEKB e+e-collider plans to take first collision data in 2018. The monetary and CPU time costs associated with storing and processing the data mean that it is crucial for the detector components at Belle II to be calibrated quickly and accurately. A fast and accurate calibration system would allow the high level trigger to increase the efficiency of event selection, and can give users analysis-quality reconstruction promptly. A flexible framework to automate the fast production of calibration constants is being developed in the Belle II Analysis Software Framework (basf2). Detector experts only need to create two components from C++ base classes in order to use the automation system. The first collects data from Belle II event data files and outputs much smaller files to pass to the second component. This runs the main calibration algorithm to produce calibration constants ready for upload into the conditions database. A Python framework coordinates the input files, order of processing, and submission of jobs. Splitting the operation into collection and algorithm processing stages allows the framework to optionally parallelize the collection stage on a batch system.

  14. Vinclozolin: a case study on the identification of endocrine active substances in the past and a future perspective.

    Science.gov (United States)

    van Ravenzwaay, Bennard; Kolle, Susanne N; Ramirez, Tzutzuy; Kamp, Hennicke G

    2013-12-16

    In the late 1980s vinclozolin was tested for prenatal developmental toxicity in rats for registration purposes in USA. At 1000mg/kgbw, 95% of all fetuses were female upon visual inspection (ano-genital distance determination). Anti-androgenic effects (AA) were also noted in a subsequent 2-generation study. These findings triggered mechanistic investigations at BASF and at US-EPA. Results published by the latter were the starting point of the endocrine disruption (ED) discussion in the 1990s. AA effects of vinclozolin are mediated by two metabolites, which have an antagonistic effect on the androgen receptor. Currently, determination of ED has become a major end-point in toxicology testing and the US-EPA has set up an elaborated testing paradigm to fulfill this requirement. Future screening for ED can be improved making use of new technologies. ED modes of action can be determined by three alternative (3R) methods. Steroid synthesis in H295R cells (1), androgen-receptor binding in modified yeast (2) and metabolomics (3). Using vinclozolin as a case study, results indicate: (1) an effect on steroid synthesis in vitro, (2) an antagonistic effect on the androgen receptor and (3) that the metabolome profile of vinclozolin is similar to that of other receptor mediated anti-androgens (e.g. flutamide). Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

  15. Control and experimental characterization of a methanol reformer for a 350 W high temperature polymer electrolyte membrane fuel cell system

    DEFF Research Database (Denmark)

    Andreasen, Søren Juhl; Kær, Søren Knudsen; Sahlin, Simon Lennart

    2013-01-01

    is the water and methanol mixture fuel flow and the burner fuel/air ratio and combined flow. An experimental setup is presented capable of testing the methanol reformer used in the Serenergy H3 350 Mobile Battery Charger; a high temperature polymer electrolyte membrane (HTPEM) fuel cell system......This work presents a control strategy for controlling the methanol reformer temperature of a 350 W high temperature polymer electrolyte membrane fuel cell system, by using a cascade control structure for reliable system operation. The primary states affecting the methanol catalyst bed temperature....... The experimental system consists of a fuel evaporator utilizing the high temperature waste gas from the cathode air cooled 45 cell HTPEM fuel cell stack. The fuel cells used are BASF P1000 MEAs which use phosphoric acid doped polybenzimidazole membranes. The resulting reformate gas output of the reformer system...

  16. CRITICALITY ANALYSIS OF URANIUM STORAGE FACILITY WITH FORMATION RACKS

    Directory of Open Access Journals (Sweden)

    Sri Kuntjoro

    2017-03-01

    ANALISIS KRITIKALITAS DI FASILITAS PENYIMPANAN BAHAN URANIUM DENGAN FORMASI PENGATURAN RAK. Bahan uranium dibutuhkan untuk produksi bahan bakar reaktor penelitian dan radioisotop. Bahan uranium sebelum digunakan terlebih dahulu disimpan pada fasilitas penyimpanan. Salah satu prasyarat fasilitas penyimpanan bahan uranium adalah fasilitas tersebut harus dalam kondisi sub-kritis. Bila kondisi kritis terjadi mengakibatkan proses fissi pada bahan uranium tidak terkendali, sehingga akan menimbulkan suhu yang sangat tinggi. Tujuan dari penelitian ini adalah untuk menganalisa kondisi kritikalitas dari fasilitas penyimpanan bahan uranium yang berada di PT. INUKI (Persero untuk menjamin fasilitas tersebut dalam kondisi sub-kritis. Analisis kritikalitas dilakukan menggunakan program MCNP-5 untuk mengetahui tingkat kritikalitas dari tiga fasilitas penyimpanan bahan uranium untuk kondisi awal dan kondisi setelah ditambahkan rak penyimpanan. Untuk fasilitas penyimpanan 1 dan 2 dibuat tiga skenario pengaturan container pada rak penyimpanan, sedangkan pada fasilitas penyimpanan 3 dilakukan 1 skenario.  Hasil ini menunjukkan seluruh fasilitas penyimpanan pada kondisi awal dan setelah ditambah rak penyimpanan dalam kondisi sub-kritis (k-eff<1. Hasil tersebut selanjutnya dipergunakan sebagai dasar untuk menyusun manejemen pengelolaan bahan uranium. Selain itu juga digunakan sebagai dasar untuk pembuatan ijin dari badan pengawas (BAPETEN. Kata Kunci : kritikalitas, fasilitas penyimpanan berbahan uranium,  k-eff

  17. Imobilisasi TiO2 ke dalam Resin Penukar Kation dan Aplikasinya sebagai Fotokatalis dalam Proses Fotoreduksi Ion Hg2+

    Directory of Open Access Journals (Sweden)

    Rosyid Ridho

    2017-03-01

    Full Text Available Abstrak Dalam rangka mengembangkan bahan fotokatalitis TiO2 pada penelitian ini telah dilakukan preparasi fotokatalis TiO2-Resin yang disertai dengan karakterisasi dan uji aktivitas untuk proses fotoreduksi ion Hg(II. Preparasi imobilisasi ini dilakukan dengan metode pertukaran ion yang di ikuti dengan kalsinasi pada suhu tertentu. Pada preparasi telah dipelajari pengaruh konsentrasi Titanium Isopropoksida sebagai sumber ion Ti(IV terhadap TiO2-Resin yang dikarakterisasi dengan menggunakan Difraksi Sinar X (XRD dan Thermografimetri (TGA. Pada proses fotoreduksi ion Hg(II dipelajari pengaruh massa fotokatalis, kadar TiO2 yang terimobilisasi ke dalam resin, konsentrasi Ion Hg(II, dan pengaruh pH. Proses fotoreduksi dilakukan dalam suatu reaktor tertutup yang dilengkapi dengan lampu UV, yaitu dengan cara menyinari campuran yang terdiri dari larutan ion Hg(II dan serbuk fotokatalis TiO2-Resin, disertai dengan pengadukan selama waktu tertentu. Hasil fotoreduksi dihitung berdasarkan selisih antara konsentrasi ion Hg(II awal dengan ion Hg(II yang tak tereduksi. Penentuan konsentrasi ion Hg(II yang tak tereduksi dilakukan dengan menggunakan Spektrofotometer Serapan Atom (SSA teknik pembangkitan uap dingin atau Cold Vapor Atomic Absorption Spectrophotometry(CV-AAS. Hasil preparasi menunjukkan semakin tinggi konsentrasi Titanium Isopropoksida yang ditambahkan pada resin semakin tinggi juga kadar TiO2 yang terbentuk pada TiO2-Resin. Hasil uji fotokatalis menunjukkan bahwa penggunaan fotokatalis TiO¬2-Resin dapat meningkatkan hasil fotoreduksi ion Hg(II yang peningkatannya lebih tinggi dibandingkan TiO2 serbuk. Penambahan fotokatalis dengan massa yang semakin besar menambah efektivitas fotoreduksi terhadap ion Hg(II yang semakin besar, namun jika ditambahkan massa fotokatalis yang lebih tinggi lagi akan menurunkan efektivitas fotoreduksi terhadap ion Hg(II. Kenaikan konsentrasi Hg(II menyebabkan efektivitas fotoreduksi semakin rendah. Pada pH 1-4 terjadi

  18. Activities of the Service for maintenance of the RA reactor electronic equipment in 1979 - Report - Annex IV; Prilog IV Rad sluzbe za odrzavanje elektronske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-12-15

    Within the organizational structure of the RA reactor staff, the Service for instrumentation maintenance has the following tasks: maintenance of the existing electronic equipment; participating in experiments planning and preparation of electronic equipment; purchasing new equipment, spare parts and components; construction of new equipment for internal needs; implementation of new equipment. Basic instrumentation of the reactor facility includes: control and protection system, and dosimetry system. [Serbo-Croat] U okviru organizacione seme OOUR nuklearni reaktor RA sluzba za odrzavanje instrumentacije postrojenja ima sledece zadatke: odrzavanje postojece elektronske opreme; ucesce u planiranju eksperimenata i priprema elektronske opreme; nabavka nove opreme, rezervnih delova i komponenti; rad na izradi elektronske opreme i uredjaja za sopstvene potrebe i izrada projekata u domenu reaktorske opreme i ucesce u ugradnji nove opreme. Osnovna instrumentacija postrojenja obuhvata: sistem za upravljanje i zastitu, sistem za tehnolosku kontrolu i sistem za dozimetrijsku kontrolu.

  19. Pengaruh Jenis Bahan pada Proses Pirolisis Sampah Organik menjadi Bio-Oil sebagai Sumber Energi Terbarukan

    Directory of Open Access Journals (Sweden)

    M. Sigit Cahyono

    2013-06-01

    Full Text Available Sampah organik merupakan potensi sumber energi yang melimpah di Indonesia. Sampah organik berupa daun dan ranting kering bisa dikonversi menjadi bahan bakar berupa bio-oil melalui proses fast pirolisis. Tujuan dari penelitian ini adalah untuk mengetahui pengaruh jenis bahan terhadap rendemen dan nilai kalor bio-oil yang dihasilkan dari proses pirolisis sampah organik. Bahan baku berupa daun dan ranting kering campuran tanaman angsana, mahoni dan mangga dengan komposisi daun bervariasi 0%, 50%, dan 100%, dipotong-potong dengan ukuran maksimal 10 cm. Kemudian bahan baku tersebut dipanaskan di dalam reaktor pirolisis pada suhu 500 C selama 1 jam. Hasil penelitian menunjukkan bahwa nilai kalor tertinggi (5175,35 J/g dan rendemen tertinggi (24,5% didapatkan pada bio-oil yang dihasilkan dari pirolisis ranting 100%. Kata kunci: Sampah Organik, Bio-oil, Pirolisis, Rendemen, Nilai Kalor

  20. MASYARAKAT MADURA DAN RENCANA PEMBANGUNAN PLTN; PERSPEKTIF TEOLOGI

    Directory of Open Access Journals (Sweden)

    Abd. A'la

    2012-05-01

    Full Text Available Abd A’la   (Staf pengajar pada program Pascasarjana IAIN Sunan Ampel dan Asiten Direktur Bidang Akademik pada lembaga yang sama       Abstrak : Setiap pemanfaatan energi selalu memiliki resiko environmental. Resiko dalam dunia ilmu dapat ditolelir jika hal itu telah terkalkulasikan sehingga merupakan caculable risk. Sementara untuk energi nuklir, sampai saat ini, belum dapat dilakukan terutama terkait dengan teknologi pengamannya sehingga Fitjof Capra menyebutnya sebagai rasionalitas yang tidak bertanggung jawab. Masyarakat Madura merupakan komunitas Sunny dan dalam merespon setiap perkembangan selalu berjangkar pada prinsip-prinsip Sunny yang dicirikan dengan kehati-hatian dan moderasi. Terkait dengan rencana PLTN madura, masalah data tentang kebutuhan hal itu harus segera diperoleh untuk menjawab perlu tidaknya PLTN di Madura. Kekhwatiran bahwa kebutuan itu hanya merupakan rekayasa perusahaan reaktor nuklir patut di pertimbangkan karena memang sangat beralasan Kata Kunci : masyarakat madura, nuklir, PLTN

  1. ANALISA THERMOGRAVIMETRY PADA PIROLISIS LIMBAH PERTANIAN

    Directory of Open Access Journals (Sweden)

    Bagus Setiawan

    2016-01-01

    Full Text Available Penelitian ini bertujuan untuk menemukan karakterisasi degradasi termal dari limbah pertanian untuk dijadikan suatu bahan bakar padat alternatif. Penelitian diawali dengan tahap pengumpulan bahan yang dilanjutkan penyeragaman ukuran sampel uji hingga berukuran 20 mesh. Setelah itu masing-masing sampel dikeringkan hingga kadar air maksimal 12 %. Sebelum Sampel seberat 20 gram diuji pirolisis dengan menempatkan sampel dalam reaktor yang telah dialiri nitrogen dengan laju 100 ml/menit. Sampel diuji dengan kondisi heating rate 15 oC/menit, temperatur akhir 600 oC dan holding time 10 menit. Data yang didapat berupa penurunan massa dan perubahan temperatur dicatat dalam laptop dengan menggunakan software RS-Key, Ms Excel dan Adam.NET Utility. Dari penelitian yang telah dilakukan, maka dapat disimpulkan campuran serbuk gergaji dan jerami memiliki temperatur pirolisis paling rendah, sementara campuran sekam padi dan kulit singkong memiliki massa arang paling banyak.

  2. Measurements with a Pulsed and Modulated Source in a Reactor; Mesures au Moyen d'une Source Pulsee et Modulee dans un Reacteur; Izmereniya v reaktore s pomoshch'yu impul'snogo i moduliruemogo is tochnika; Mediciones Efectuadas en Reactor con una Fuente Pulsada y Modulada

    Energy Technology Data Exchange (ETDEWEB)

    Rotter, W. [Centre d' Etude de l' Energie Nucleaire, Mol (Belgium)

    1965-10-15

    analizador multicanal. Como el flujo del generador es perfectamente sinusoidal, la respuesta del reactor puede integrarse en cada cuarto de perfodo, puesto que el circuito de medicion esta gobernado por el generador; por consiguiente, el tiempo de medicion es minimo. Los datos registrados sobre cinta perforada se analizan con ayuda de una calculadora numerica. (author) [Russian] Generator, vyhod nejtronov kotorogo izmenjaetsja v zavisimosti ot funkcii kakogo-to vremeni, byl razrabotan v issledovatel'skih laboratorijah Filipsa. Ego prakticheskaja pol'za v oblasti fiziki reaktorov byla prodemonstrirovana na serii izmerenij, provedennyh v reaktore BR-O 2 v podkriticheskom sostojanii. Horoshaja ustojchivost', vozmozhnost' proizvodit' rezkie izmenenija intensivnosti nejtronnogo potoka, impul'sirovat' vyhod ili modulirovat' ego sinusoidal'no, - vse jeto delaet takoj generator ochen' gibkim. On pozvoljaet ustanavlivat' reaktivnost' ({rho} = {Delta}k/{beta}) i vremja zhizni nejtronov ( Script-Small-L /{beta}) po razlichnym nezavisimym metodam. Tochnoe sravnenie jetih metodov vozmozhno, poskol'ku poslednie mogut byt' ispol'zovany bez izmenenija uslovij izmerenija. Ustanovleno: 1) {rho} na osnove zapazdyvajushhih nejtronov putem mgnovennogo umen'shenija vyhoda nejtronov; 2) {rho} na osnove mgnovennyh nejtronov putem ispol'zovanija impul'sov nejtronov; 3) Script-Small-L /{beta} putem soedinenija 1) i 2) dlja 0,5 $ < {rho} < 2 $ ; 4) Script-Small-L /{beta} na osnove peredatochnoj funkcii reaktora dlja moduliruemogo istochnika. Obsuzhdajutsja peredatochnye funkcii dlja oscilljatora reaktivnosti i dlja sinusoidal'no moduliruemogo istochnika. Pokazano, chto izmerenie Script-Small-L /{beta} vozmozhno dlja 0,1 $< {rho} < $ s uchetom primenenija moduliruemogo istochnika. Tot zhe metod takzhe daet reaktivnost' s pomoshh'ju otnoshenija mgnovennyh nejtronov k zapazdyvajushhim nejtronam dlja optimal'noj chastoty, prichem na praktike jeto proishodit nezavisimo ot dannyh, otnosjashhihsja k

  3. RA research reactor - properties and experimental capabilities; Istrazivacki reaktor RA - Tehnicke karakteristike i eksploatacione mogucnosti

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-15

    The brief survey of the Reactor RA exploitation experience, as well as the reactor equipment state, after 18 years of operation is presented. The results of efforts spent on reactor characteristics improvement in order to ensure safe and reliable reactor operation for next 15-20 years, are described. Prikazani su fragmenti iz eksploatacije reaktora kao i stanje opreme, posle 18 godina rada. Na kraju je dat prikaz sta je preduzeto i sta se preduzima da se poboljsaju karakteristike i poveca sigurnost i bezbednost rada za sledecih 15-20 godina.

  4. Spectroscopy of organic semiconductors from first principles

    Science.gov (United States)

    Sharifzadeh, Sahar; Biller, Ariel; Kronik, Leeor; Neaton, Jeffery

    2011-03-01

    Advances in organic optoelectronic materials rely on an accurate understanding their spectroscopy, motivating the development of predictive theoretical methods that accurately describe the excited states of organic semiconductors. In this work, we use density functional theory and many-body perturbation theory (GW/BSE) to compute the electronic and optical properties of two well-studied organic semiconductors, pentacene and PTCDA. We carefully compare our calculations of the bulk density of states with available photoemission spectra, accounting for the role of finite temperature and surface effects in experiment, and examining the influence of our main approximations -- e.g. the GW starting point and the application of the generalized plasmon-pole model -- on the predicted electronic structure. Moreover, our predictions for the nature of the exciton and its binding energy are discussed and compared against optical absorption data. We acknowledge DOE, NSF, and BASF for financial support and NERSC for computational resources.

  5. From conditioning shampoo to nanomechanics and haptics of human hair.

    Science.gov (United States)

    Wood, Claudia; Sugiharto, Albert Budiman; Max, Eva; Fery, Andreas

    2011-01-01

    Shampoo treatment and hair conditioning have a direct impact on our wellbeing via properties like combability and haptic perception of hair. Therefore, systematic investigations leading to quality improvement of hair care products are of major interest. The aim of our work is a better understanding of complex testing and the correlation with quantitative parameters. The motivation for the development of physical testing methods for hair feel relates to the fact that an ingredient supplier like BASF can only find new, so far not yet toxicologically approved chemistries for hair cosmetics, if an in-vitro method exists.In this work, the effects of different shampoo treatments with conditioning polymers are investigated. The employed physical test method, dry friction measurements and AFM observe friction phenomena on a macroscopic as well as on a nanoscale directly on hair. They are an approach to complement sensoric evaluation with an objective in-vitro method.

  6. Effect of dietary Astaxanthin sources supplementation on muscle pigmentation and lipid peroxidation in rainbow trout (Oncorhynchus mykiss

    Directory of Open Access Journals (Sweden)

    Marco Saroglia

    2010-01-01

    Full Text Available Astaxanthin is one of the major carotenoids in aquatic animals including salmonid fishes and is the preferred pigments added to salmon feed. It’s also a powerful antioxidant compared to other carotenoids and that may confer numerous health benefits. The aim of the present experi- ment was to investigate the effect of Astaxanthin deposition on the lipids peroxidation by studying the Malondialdeide (MDA level in muscle of rainbow trout (Oncorhynchus mykiss. The Astaxanthin concentrations in fish fed with a commercial sources as Lucantin®Pink (BASF Ludwigshafen, Ger- many reached values to 5.76±0.18x10-3 mg/g after 50 days feeding, while the MDA concentration de- creased from 1.56x103 to 0.45x103 ng/g. The correlation between MDA and Astaxanthin concentrations decreased linearly and confirmed the antioxidant properties of the pigment by reducing the lipids peroxidation.

  7. Design and Control of High Temperature PEM Fuel Cell System

    DEFF Research Database (Denmark)

    Andreasen, Søren Juhl

    E-cient fuel cell systems have started to appear in many dierent commercial applications and large scale production facilities are already operating to supply fuel cells to support an ever growing market. Fuel cells are typically considered to replace leadacid batteries in applications where...... to conventional PEM fuel cells, that use liquid water as a proton conductor and thus operate at temperatures below 100oC. The HTPEM fuel cell membrane in focus in this work is the BASF Celtec-P polybenzimidazole (PBI) membrane that uses phosphoric acid as a proton conductor. The absence of water in the fuel cells...... enables the use of designing cathode air cooled stacks greatly simplifying the fuel cell system and lowering the parasitic losses. Furthermore, the fuel impurity tolerance is signicantly improved because of the higher temperatures, and much higher concentrations of CO can be endured without performance...

  8. Thin-film composite materials as a dielectric layer for flexible metal-insulator-metal capacitors.

    Science.gov (United States)

    Tiwari, Jitendra N; Meena, Jagan Singh; Wu, Chung-Shu; Tiwari, Rajanish N; Chu, Min-Ching; Chang, Feng-Chih; Ko, Fu-Hsiang

    2010-09-24

    A new organic-organic nanoscale composite thin-film (NCTF) dielectric has been synthesized by solution deposition of 1-bromoadamantane and triblock copolymer (Pluronic P123, BASF, EO20-PO70-EO20), in which the precursor solution has been achieved with organic additives. We have used a sol-gel process to make a metal-insulator-metal capacitor (MIM) comprising a nanoscale (10 nm-thick) thin-film on a flexible polyimide (PI) substrate at room temperature. Scanning electron microscope and atomic force microscope revealed that the deposited NCTFs were crack-free, uniform, highly resistant to moisture absorption, and well adhered on the Au-Cr/PI. The electrical properties of 1-bromoadamantane-P123 NCTF were characterized by dielectric constant, capacitance, and leakage current measurements. The 1-bromoadamantane-P123 NCTF on the PI substrate showed a low leakage current density of 5.5 x 10(-11) A cm(-2) and good capacitance of 2.4 fF at 1 MHz. In addition, the calculated dielectric constant of 1-bromoadamantane-P123 NCTF was 1.9, making them suitable candidates for use in future flexible electronic devices as a stable intermetal dielectric. The electrical insulating properties of 1-bromoadamantane-P123 NCTF have been improved due to the optimized dipole moments of the van der Waals interactions.

  9. Preliminary studi on neutronic aspect of a conceptual design of the Kartini reactor base ADS facility

    International Nuclear Information System (INIS)

    Tegas Sutondo

    2012-01-01

    A preliminary study on neutronic aspect of a conceptual design of ADS facility with the basis of Kartini Reaktor, has been performed. The study was intended to see the feasibility from neutronic point of view of Kartini reactor, to be used as a small scale of NPP’s waste transmutation experimental facility. A SRAC code was used as the basis of calculations. The results indicate that the presence of minor actinides (MA) will give a positive reactivity, which tends to increase with the increase of MA concentrations. Based on the defined criteria of subcriticality and by considering the core power distributions and the level of reactivity contribution of MA element, it is concluded that Kartini reactor is potential enough to be used as an ADS experimental facility, mainly for MA concentration between 30 to 50 % of the assumed mixture of C-MA matrix. (author)

  10. ILK statement on the consequences of the Chernobyl accident. Taking stock after twenty years

    International Nuclear Information System (INIS)

    2006-01-01

    The Chernobyl reactor accident was the consequence of a reactor design which was not inherently safe, and of a lack of 'safety culture'. The RBMK-type reactor (a Russian graphite-moderated light water reactor design: reaktor bolshoi moshnosty kanalny=high-power channel reactor) had not been designed to a satisfactory safety level, and the operating staff were not informed on the weak spots in plant design. The combination of these factors caused the worst nuclear accident, completely destroying the reactor. The consequences may be seen as the product of two severe accidents superimposed upon each other: the explosion of the reactor, and core melt-down associated with an intense, persistent fire of the graphite moderator. The Statement contains analyses of these points: Release, Propagation and Deposition of Radioactive Materials; Protective Measures; Impact on the Environment and Agriculture; Assessment of Radiation Exposure; Health Impact; Psychological and Societal Impacts; Potential Residual Risks. (orig.)

  11. Investigation of corrosion of materials of the irradiation device in the RA reactor; Ispitivanje korozije materijala uredjaja za ozracivanje na reaktoru RA

    Energy Technology Data Exchange (ETDEWEB)

    Zaric, M; Mance, A; Vlajic, M [Institute of Nuclear Sciences Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    Devices for sample irradiation in the vertical RA reactor channels will be made of aluminium alloys. According to the regulations concerned with introducing materials into the RA reactor core, corrosion characterisation of these materials is an obligation. Corrosion properties of four aluminium alloys were investigated both in contact with stainless steel and without it. First part of this report deals with the corrosion testing of aluminium alloys in water by gravimetric and electrochemical methods. Bi-distilled water at temperatures less than 100 deg C was used. Second part is related to aluminium alloys corrosion in carbon dioxide gas under experimental conditions. The second part of research was initiated by the design of the head of the independent CO{sub 2} loop for samples cooling. [Serbo-Croat] Uredjaji za ozracivanje u vertikalnim kanalima reaktora RA, bice napravljeni od legura aluminjuma. Prema propisima o unosenju materijala u RA reaktor materijali se moraju prethodno ispitati i sa stanovista korozije. Ispitivane su korozione pojave na cetiri aluminjumske legure sa i bez kontakta sa nerdjajucim celikom. Prvi deo ovog rada tretira pitanje korozije legura aluminijuma u vodi gravimetrijskim i elektrohemijskim metodama. Koriscena je bidestilovana voda na temperaturi do 100 deg C. Drugi deo se odnosi na ispitivanje ponasanja legura aluminijuma u gasovitom ugljen dioksidu pod uslovima eksperimenta. Drugi deo istrazivanja izvrsen je za potrebe izgradnje glave petlje nezavisnog kola za hladjenje uzoraka gasovitim CO{sub 2}.

  12. Measuring the B± → [D0 → f] K± branching ratio

    International Nuclear Information System (INIS)

    Limosani, A.

    2000-01-01

    Full text: The poster will detail the endeavour to measure the branching ratio for the charged B meson decay to neutral D and charged K meson, where D decays to a non-CP eigenstate i.e. B± → [D 0 /D 0 → f] K ± . The specific mode 'f' will be the doubly Cabibbo suppressed decay D 0 → K + π - . This measurement coupled with auxiliary information about D decays can be used to determine angle Φ 3 of the Unitarity triangle2. This triangle represents one of the unitary relations of the CKM matrix. The elements that contribute to this relation are directly related to the phenomena of CP Violation in B decays. The degree of violation observed will provide a good test of the minimal standard model and the proposed extensions. The poster will show the results of simulation studies conducted with QQ98 event generator, GSIM Monte Carlo of the BELLE detector response, and my own analysis code written as a module in BASF (Belle user Analysis Simulation Framework). The BELLE experiment is currently running at the KEK-B factory in Tsukuba, Japan. These studies should place a lower limit on the number of charged B events, needed to observe the nominated decay with the BELLE detector

  13. The utilization of stone ash on cellular lightweight concrete

    Science.gov (United States)

    Karolina, R.; Sianipar, Y. G. C.

    2018-02-01

    Lightweight concrete brick is a brick which made of cement, sand, water, and foam as the basic composition. This brick are divided into 2, based on the foam used such as AAC (Autoclave Aerated Concrete) that use aluminium paste and CLC(Cellular Lightweight Concrete) that use foaming agent from BASF as its foaming material. In this trial, the lightweight brick that are ging to be use are the CLC with foaming agent as its foaming material with the mixture of stone ash that are produced by the Stone Crusher with spesific gravity 2666 kg/m3 as their partly sand substitution . In this research, the stone ash variant that are used are 10%, 15%, and 20% from the amount of sand that planned before. After casting, the result of the 10% will receive a reduction of compressive strength while an increasing in absorption as 25.07% and 39.005% and the 15% variant will recieve a reduction of compressive strength as much as 65.8% and a reduction of absorption as much as 17.441% and the 20% variant will recieve a reduction of compressive strength as much as 67.4% while an increasing of absorption as much as 17.956%.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-12-15

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

  15. Oxygen reduction and methanol oxidation behaviour of SiC based Pt nanocatalysts for proton exchange membrane fuel cells

    DEFF Research Database (Denmark)

    Dhiman, Rajnish; Stamatin, Serban Nicolae; Andersen, Shuang Ma

    2013-01-01

    for carbon based commercial catalyst, when HClO4 is used as electrolyte. The Pt (110) & Pt (111) facets are shown to have higher electrochemical activities than Pt (100) facets. To the best of our knowledge, methanol oxidation studies and the comparison of peak deconvolutions of the H desorption region in CV...... and methanol oxidation reactions of SiC supported catalysts and measured them against commercially available carbon based catalysts. The deconvolution of the hydrogen desorption signals in CV cycles shows a higher contribution of Pt (110) & Pt (111) peaks compared to Pt (100) for SiC based supports than...... cyclic studies are here reported for the first time for SiC based catalysts. The reaction kinetics for the oxygen reduction and for methanol oxidation with Pt/SiC are observed to be similar to the carbon based catalysts. The SiC based catalyst shows a higher specific surface activity than BASF (Pt...

  16. Ohio incinerator given the go-ahead

    International Nuclear Information System (INIS)

    Kemezis, P.

    1992-01-01

    A federal judge has denied a request for an injunction against the startup of the long-stalled Waste Technologies Industries (WTI) commercial hazardous waste incinerator in East Liverpool, OH. The $140-million plant, owned by a US subsidiary of Swiss engineering group Von Roll Ltd. (Zuerich), will go through a startup stage and a seven-day trial burn during the next two months, according to WTI. In testimony in federal court in Huntington, WV, WTI had said it was losing $115,000/day in fixed costs because of the plant's startup delay. The company also said that long-term contracts with Chemical Waste Management (CWM; Oak Brook, IL), Du Pont (Wilmington, DE), and BASF Corp. (Parsippany, NJ) to use plant services could be jeopardized by the delay. WTI is believed to have 10-year service contracts with the three companies and also will use CWM to dispose of the ash from the incinerator

  17. Parní generátor reaktoru ESFR

    OpenAIRE

    Bátěk, David

    2012-01-01

    Tato diplomová práce se zabývá parním generátorem pro reaktory ESFR (Evropský Rychlý Sodíkem Chlazený Reaktor), jenž je vyhříván tekutým sodíkem. V úvodních kapitolách jsou teoretické informace o parametrech ESFR a porovnání s výměníky tepla v jaderných elektrárnách pracujících na stejném principu (sodík jako chladivo). Následuje návrhová část, kam patří úvod do problematiky výpočtu, volba materiálu a koncepce výměníku a samotná výpočtová část, která zahrnuje tepelný, hydraulický a pevnostní ...

  18. Structural analysis of aircraft impact on a nuclear powered ship

    International Nuclear Information System (INIS)

    Dietrich, R.

    1976-01-01

    As part of a general safety analysis, the reliability against structural damage due to an aircraft crash on a nuclear powered ship is evaluated. This structural analysis is an aid in safety design. It is assumed that a Phantom military jet-fighter hits a nuclear powered ship. The total reaction force due to such an aircraft impact on a rigid barrier is specified in the guidelines of the Reaktor-Sicherheitskommission (German Safety Advisory Committee) for pressurized water reactors. This paper investigates the aircraft impact on the collision barrier at the side of the ship. The aircraft impact on top of the reactor hatchway is investigated by another analysis. It appears that the most unfavorable angle of impact is always normal to the surface of the collision barrier. Consequently, only normal impact will be considered here. For the specific case of an aircraft striking a nuclear powered ship, the following two effects are considered: Local penetration and dynamic response of the structure. (Auth.)

  19. PENGELOLAAN LIMBAH PETERNAKAN SAPI UNTUK MENINGKATKAN KAPASITAS PRODUKSI PADA KELOMPOK TERNAK PATRA SUTERA

    Directory of Open Access Journals (Sweden)

    Danang Dwi Saputro

    2014-02-01

    Full Text Available Kelompok ternak Patra Sutera di Desa Ledok Kecamatan Sambong Kabupaten Blora yang berdiri pada tahun 2013 telah mempunyai sapi 8 ekor yang berada di kandang komunal yang dikelola oleh 6 anggota kelompok. Dalam satu hari setiap ekor sapi dapat menghasilkan limbah padat sebanyak 20-30 kg dan limbah cair sebanyak 100-150 liter yang selama ini belum dikelola dengan baik. Limbah dari kegiatan ternak belum terolah dengan baik dan dibuang ke lingkungan sehingga menimbulkan dampak negatif bagi kesehatan masyarakat sekitar kandang. Salah satu cara untuk mengatasi kondisi ini adalah dengan memberikan pelatihan keterampilan atau pendampingan bagaimanakah teknik pembuatan pupuk organic dan reaktor biogas sederhana, mengoperasikan, serta memanfaatkan gas yang dihasilkan. Dalam kegiatan ini akan diberikan pelatihan keterampilan bagaimana cara mengolah limbah ternah untuk dijadikan pupuk dan pestisida organik,serta pengelolaan biodigester. Dari kegiatan ini Anggota kelompok ternak Patra Sutera mendapat pengetahuan dan mengolah limbah kotoran ternak (padat dan cair yang keliar dari biodigester menjadi pupuk yang lebih bermanfaat.

  20. Thermal-Hydraulic Experiment To Test The Stable Operation Of A PIUS Type Reactor

    International Nuclear Information System (INIS)

    Irianto, Djoko; Kanji, T.; Kukita, Y.

    1996-01-01

    An advanced type of reaktor concept as the Process Inherent Ultimate Safety (PIUS) reactor was based on intrinsically passive safety considerations. The stable operation of a PIUS type reactor is based on the automation of circulation pump speed. An automatic circulation pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed the PIUS-type reactor. In principle this control system maintains the fluid temperature at the axial center of the lower density lock at average of the fluid temperatures below and above the lower density lock. This control system will prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments using atmospheric pressure thermal-hydraulic test loop which simulated the PIUS principle. The experiments such as: start-up and power ramping tests for normal operation simulation and loss of feedwater test for an accident condition simulation, carried out in JAERI

  1. Slovak brown coals as a feedstock for the active coke production

    Directory of Open Access Journals (Sweden)

    Sobolewski Aleksander

    1998-09-01

    Full Text Available V èlánku sa venuje pozornos možnostiam výroby aktívneho koksu zo slovenského hnedého uhlia Bane Cíge¾. Príprava aktívneho koksu bola uskutoènená v laboratórnych podmienkach a v poloprevádzke. Surové uhlie sa podrobilo vysokoteplotnej pyrolýze v retorte s pevným roštom, v klasickej rotaènej peci, ako aj vo fluidnom reaktore. Následne boli urèované adsorpèné charakteristiky získaného aktívneho koksu, ktoré sa porovnávali s charakteristikami komerène vyrábaného koksu. V príspevku sa taktiež diskutujú možnosti aplikácie pripraveného aktívneho koksu v technológiách ochrany životného prostredia.

  2. Outlook on to fuel cycle perspectives at WWER-440

    International Nuclear Information System (INIS)

    Stech, S.; Bajgl, J.

    2005-01-01

    Current internal fuel cycle in NPP Dukovany 4x440 MWe is shortly characterized with new types of fuel assemblies and advanced fuel cycles which have been introduced in the last years. The modernization activities accomplished until now might be extrapolated to the further period in fuel design - mechanic, thermal-hydraulic and neutronic respectively - with additional increase in fuel enrichments and burnups on the way to the 6-year cycle. Reaktor power up rating together with Unit thermal efficiency improvements could bring an increase in the electric output to the value nearly 500 MWe. The reasons are given for long-term cooperation with Fuel Supplier and Plant Designer in the area of fuel cycle as well as in Unit Design Basis. All innovations mentioned in the article including future fuel and fuel cycle changes might be a quite realistic perspective at the end of the first decade of the new century (Authors)

  3. RB Research nuclear reactor, 30 years of operation; Istrazivacki nuclearni reaktor RB, povodom 30 godina rada

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-06-15

    Paper describes utilization, modifications and changes of construction and control-safety systems done at the RB reactor during 30 years of operation. Experiments performed at the reactor are summarized, new reactor equipment is described and the future plans are shown. Rad prikazuje eksploataciju reaktora RB tokom 30 godina rada, modifikacije i izmene u konstruktivnim i upravljacko-sigurnosnim sistemima. Sumirani su eksperimenti izvedeni na njemu, prikazana je nova oprema i planovi za buduci rad.

  4. Nuclear RB research reactor. Thirty years of anniversary; Istrazhivacki nuklearni reaktor RB. Povodom 30 godina rada

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M; Stefanovic, D [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1988-07-01

    Nuclear research reactor RB in the Nuclear Engineering Laboratory - NET at the 'Boris Kidric' Institute of Nuclear Sciences in Vinca is the first reactor system built in Yugoslavia in 1958. This year is the thirtieth anniversary of the RB reactor operation, which has survived a series of modifications trying to follow a contemporary nuclear research directions. This report describes its basic technical characteristics and experimental possibilities. Especially, the modifications in the last 25 years are underlined, the experiences gained, and new plans for the future are presented. (author)

  5. German safety engineering in comparison to the Chernobyl reactor; Deutsche Sicherheitstechnik im Vergleich zum Tschernobyl-Reaktor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-04-15

    In Germany the Russian RBMK would not have been licensed, since the safety standards in Germany were superior to those in the former USSR. The most significant differences - the containment, the control rod system, the void coefficient and the emergency cooling system are shortly summarized. The consequences for the population are cumulative environmental radiation exposure are reported using the official data of IAEA, WHO and UNDP.

  6. Fabrication and Testing of Prototype APM-Clad UO{sub 2} Fuel Elements; Fabrication et essai de prototypes de cartouches de combustible en bioxyde d'uranium gaine d'aluminium (APM); Izgotovlenie i ispytanie prototipa toplivnykh ehlementov na osnove UO{sub 2} s obolochkoj iz alyuminiya metodom poroshkovoj metallurgii; Elaboracion y ensayo de elementos combustibles prototipo de UO{sub 2} con revestimiento de aluminio sinterizado

    Energy Technology Data Exchange (ETDEWEB)

    Ballif, III, J. L.; Friske, W. H.; Gordon, R. B. [Atomics International, Canoga Park, California (United States)

    1963-11-15

    los elementos combustibles se extrajeron del reactor a raiz de problemas suscitados por el instrumental utilizado para los ensayos. Los tres elementos restantes continuaban en el reactor. Todos los resultados de los experimentos realizados hasta la fecha parecen indicar que el sistema de combustible PMA-UO{sub 2} permitira alcanzar los objetivos fijados para el programa relativo al reactor POPR. (author) [Russian] V podderzhku Programmy prototipov organicheskikh ehnergoreaktorov (POPR) moshchnost'yu 50 mgvt (ehl.) byla provedena obshirnaya rabota po razrabotke poroshkovoj metallurgiej alyuminievykh materialov (APM) v kachestve obolochek dlya topliva iz UO{sub 2} . Kak chast' ehtoj raboty byli issledovany ehvteticheskoe soedinenie, svarke v styk oplavleniem i kholodnaya svarka. Kolduehlla pod davleniem kak metody dlya soedineniya stykov pri sborke toplivnykh ehlementov. Vibratsionnoe uplotnenie izuchalos' kak sredstvo zapolneniya trubok APM dvuokis'yu urana. Opyty vne reaktora provodilis' dlya.ogo, chtoby poluchit' informatsiyu o svomestimosti APM - UO{sub 2} . Ehta rabota pokazala, chto pri sushchestvuyushchikh usloviyakh ehvteticheskoe soedinenie yavlyaetsya naibolee podkhodyashchim sposobom dlya soedineniya stykov; vibratsionnoe uplotnenie davalo plotnost' topliva v predelakh ot 80 do 88% teoreticheskoj plotnosti, i ne nablyudalos' vzaimodejstvie APM -UO{sub 2} v diapazone ehkspluatatsionnykh temperatur POPR (temperatura poverkhnosti razdela toplivo - obolochka maksimum 850{sup o}F). V rezul'tate ehtoj raboty bylo izgotovleno 5 prototipov UO{sub 2}-APM toplivnykh ehlementov s tsel'yu ispytaniya na opytnom reaktore s organicheskim zamedlitelem. Kazhdyj ehlement sostoyal iz 24 ili 25 toplivnykh sterzhnej v obolochke iz APM i sgruppirovannykh v sistemu 5 x 5 v stal'noj korobke, pokrytoj nikelem, ili toplivnoj korobke ieh APM. Dlya togo, chtoby uvelichit' poverkhnost' ehlementa i tem samym znachitel'no uluchshit' teploperedachu, izgotovlennaya ehkstruziej obolochka ieh

  7. A CONCEPTUAL DESIGN OF NEUTRON COLLIMATOR IN THE THERMAL COLUMN OF KARTINI RESEARCH REACTOR FOR IN VITRO AND IN VIVO TEST OF BORON NEUTRON CAPTURE THERAPY

    Directory of Open Access Journals (Sweden)

    Nina Fauziah

    2015-03-01

    Full Text Available Studies were carried out to design a collimator which results in epithermal neutron beam for IN VITRO and IN VIVO of Boron Neutron Capture Therapy (BNCT at the Kartini research reactor by means of Monte Carlo N-Particle (MCNP codes. Reactor within 100 kW of thermal power was used as the neutron source. The design criteria were based on recommendation from the International Atomic Energy Agency (IAEA. All materials used were varied in size, according to the value of mean free path for each material. MCNP simulations indicated that by using 5 cm thick of Ni as collimator wall, 60 cm thick of Al as moderator, 15 cm thick of 60Ni as filter, 2 cm thick of Bi as γ-ray shielding, 3 cm thick of 6Li2CO3-polyethylene as beam delimiter, with 1 to 5 cm varied aperture size, epithermal neutron beam with maximum flux of 7.65 x 108 n.cm-2.s-1 could be produced. The beam has minimum fast neutron and γ-ray components of, respectively, 1.76 x 10-13 Gy.cm2.n-1 and 1.32 x 10-13 Gy.cm2.n-1, minimum thermal neutron per epithermal neutron ratio of 0.008, and maximum directionality of 0.73. It did not fully pass the IAEA’s criteria, since the epithermal neutron flux was below the recommended value, 1.0 x 109 n.cm-2.s-1. Nonetheless, it was still usable with epithermal neutron flux exceeding 5.0 x 108 n.cm-2.s-1. When it was assumed that the graphite inside the thermal column was not discharged but only the part which was going to be replaced by the collimator, the performance of the collimator became better within the positive effect from the surrounding graphite that the beam resulted passed all criteria with epithermal neutron flux up to 1.68 x 109 n.cm-2.s-1. Keywords: design, collimator, epithermal neutron beam, BNCT, MCNP, criteria   Telah dilakukan penelitian tentang desain kolimator yang menghasilkan radiasi netron epitermal untuk uji in vitro dan in vivo pada Boron Neutron Capture Therapy (BNCT di Reaktor Riset Kartini dengan menggunakan program Monte

  8. Slow Neutron Spectrometers at the Swedish Reactors; Spectrometres a Neutrons Lents des Reacteurs Suedois; 0421 041f 0415 041a 0422 0420 041e 041c 0415 0422 0420 042b 041c 0415 0414 041b 0415 041d 041d 042b 0425 041d 0415 0419 0422 0420 041e 041d 041e 0412 041d 0410 0428 0412 0415 0414 0421 041a 0418 0425 0420 0415 0410 041a 0422 041e 0420 0410 0425 ; Espectrometros para Neutrones Lentos en los Reactores de Suecia

    Energy Technology Data Exchange (ETDEWEB)

    Dahlborg, U.; Skoeld, K. [AB Atomenergi, Stockholm (Sweden); Larsson, K. -E. [Royal Institute of Technology, Stockholm (Sweden)

    1965-06-15

    efecto combinado de un filtro de Be y un selector con una curva de transmision estrecha. En este espectrometro, lo mismo que en el de Estocolmo, el selector se coloca delante de la muestra para poder registrar simultaneamente datos a diferentes angulos de observacion. En el reactor R2 se encuentra tambien instalado un espectrometro triaxial de cristal. Los autores describen diversas caracteristicas de los instrumentos, tales como las intensidades y los poderes de resolucion alcanzados, e indican en que medida se adaptan a ciertas determinaciones. Demuestran con datos numericos que un aumento relativamente pequeno del poder de resolucion ocasiona una elevada perdida de intensidad. Cuando se comparan los reactores RI y R2 como fuentes neutronicas para experimentos en el orificio de haz, es interesante observar que, si bien el flujo neutronico del reactor R2 es 100 veces mayor, el rendimiento en neutrones es unas 10 veces menor. El fenomeno se debe a la estrechez de los orificios de haz y a los filtros que son necesarios para reducir los flujos gamma y de neutrones rapidos. Como ilustracion, la memoria discute brevemente datos de dispersion en H{sub 2}O obtenidos con los diversos instrumentos. La comparacion demuestra que, para experimentos con el orificio de haz, el reactor de agua pesada presenta ventajas innegables. (author) [Russian] V nastojashhee vremja na dvuh shvedskih issledovatel'skih reaktorah K1 v Stokgol'me i R2 v Studsvike, imejutsja vozmozhnosti dlja ispol'zovanija chetyreh razlichnyh spektrometrov nejtronov v opytah po neuprugomu rassejaniju nejtronov. V Stokgol'me na tjazhelovodnom reaktore R1 moshhnost'ju 600-kvt odnovremenno ispol'zujutsja dva spektrometra po vremeni proleta s medlenno dejstvujushhim preryvatelem. Na odnom reaktore my postojanno ispol'zuem berillievyj fil'tr v kachestve monohromatora, v to vremja kak na drugom reaktore mozhno ispol'zovat' libo berillievyj fil'tr, libo kristallicheskij monohromator. Obnaruzheno, chto pri izmerenijah

  9. The NEA benchmark study of the accident at the Fukushima Daiichi NPP

    International Nuclear Information System (INIS)

    Koganeya, Toshiyuki

    2015-01-01

    In November 2012, the NEA, under the aegis of the Committee on the Safety of Nuclear Installations (CSNI), initiated a joint research project called the Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF). Objectives of this project include supporting Fukushima Daiichi decommissioning by analysing accident progression and the current status of the reactors, such as fuel debris distribution in the reactor pressure vessels and primary containment vessels in preparation for fuel debris removal. A second objective of the project is to improve SA (severe analysis) codes through comparisons with data from the Fukushima reactors. So as to enhance communication between analysts and those involved in decommissioning activities, participants in the project have been discussing the remaining uncertainties in relation to understanding the accident and the data needs from the viewpoint of the analysts. Since the accident sequences at the Fukushima Daiichi site include a wide range of phenomena, a phased approach is being applied in this benchmark exercise while awaiting more detailed information on debris examination and other factors. This article provides an overview of the project (scope, input data and boundary conditions, participants (from eight countries), analytical approach - common case and best estimate case) as well as an outline of the project's next phase (BASF phase 2) that begins in June 2015

  10. An Interactive and Comprehensive Working Environment for High-Energy Physics Software with Python and Jupyter Notebooks

    Science.gov (United States)

    Braun, N.; Hauth, T.; Pulvermacher, C.; Ritter, M.

    2017-10-01

    Today’s analyses for high-energy physics (HEP) experiments involve processing a large amount of data with highly specialized algorithms. The contemporary workflow from recorded data to final results is based on the execution of small scripts - often written in Python or ROOT macros which call complex compiled algorithms in the background - to perform fitting procedures and generate plots. During recent years interactive programming environments, such as Jupyter, became popular. Jupyter allows to develop Python-based applications, so-called notebooks, which bundle code, documentation and results, e.g. plots. Advantages over classical script-based approaches is the feature to recompute only parts of the analysis code, which allows for fast and iterative development, and a web-based user frontend, which can be hosted centrally and only requires a browser on the user side. In our novel approach, Python and Jupyter are tightly integrated into the Belle II Analysis Software Framework (basf2), currently being developed for the Belle II experiment in Japan. This allows to develop code in Jupyter notebooks for every aspect of the event simulation, reconstruction and analysis chain. These interactive notebooks can be hosted as a centralized web service via jupyterhub with docker and used by all scientists of the Belle II Collaboration. Because of its generality and encapsulation, the setup can easily be scaled to large installations.

  11. Preparation of PtRu/C and PtSn/C electrocatalysts using electron beam irradiation for direct and ethanol fuel cell

    International Nuclear Information System (INIS)

    Silva, Dionisio Furtunato da

    2009-01-01

    PtRu/C and PtSn/C electrocatalysts were prepared using electron beam irradiation. The metal ions were dissolved in water/2-propanol and water/ethylene glycol solutions and the carbon support was added. The resulting mixtures were irradiated under stirring. The effect of water/ethylene glycol and water/2-propanol (v/v) ratio, Pt:Ru and Pt:Sn atomic ratios, the irradiation time and dose rate were studied. The obtained materials were characterized by Energy dispersive analysis of X-rays (EDX), X-ray diffraction (XRD), cyclic voltammetry (CV) and Moessbauer spectroscopy. The electro-oxidation of methanol and ethanol were studied by cyclic voltammetry and chronoamperometry using the thin porous coating technique. The electrocatalysts were also tested on the Direct Methanol and Ethanol Fuel Cells. PtRu/C electrocatalysts prepared in water/ethylene glycol showed Pt:Ru atomic ratios different from the nominal ones. The results suggested that part of the Ru(III) ions were not reduced. The obtained materials showed the face-centered cubic (fcc) structure of Pt and Pt alloys with crystallite sizes of 2-3 nm. PtRu/C electrocatalysts prepared in water/2-propanol showed Pt:Ru atomic ratios similar to the nominal ones. The obtained materials also showed the fcc structure of platinum and platinum alloys with crystallite sizes of 3-4 nm. PtSn/C electrocatalysts prepared in water/ethylene glycol and water/2-propanol showed Pt:Sn atomic ratios similar to the nominal ones. The obtained materials showed the platinum (fcc) phase with crystallite sizes in the range of 2 - 4 nm and a SnO 2 (cassiterite) phase. The obtained PtRu/C and PtSn/C electrocatalysts showed similar or superior performance for methanol and ethanol electro-oxidation compared to commercial PtRu/C (E-TEK) and PtSn/C (BASF) electrocatalysts. (author)

  12. Radioactivity of spent TRIGA fuel

    International Nuclear Information System (INIS)

    Usang, M. D.; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P.

    2015-01-01

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive

  13. Radioactivity of spent TRIGA fuel

    Energy Technology Data Exchange (ETDEWEB)

    Usang, M. D., E-mail: mark-dennis@nuclearmalaysia.gov.my; Nabil, A. R. A.; Alfred, S. L.; Hamzah, N. S.; Abi, M. J. B.; Rawi, M. Z. M.; Abu, M. P. [Reactor Department, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2015-04-29

    Some of the oldest TRIGA fuel in the Malaysian Reaktor TRIGA PUSPATI (RTP) is approaching the limit of its end of life with burn-up of around 20%. Hence it is prudent for us to start planning on the replacement of the fuel in the reactor and other derivative activities associated with it. In this regard, we need to understand all of the risk associated with such operation and one of them is to predict the radioactivity of the fuel, so as to estimate the safety of our working conditions. The radioactivity of several fuels are measured and compared with simulation results to confirm the burnup levels of the selected fuels. The radioactivity measurement are conducted inside the water tank to reduce the risk of exposure and in this case the detector wrapped in plastics are lowered under water. In nuclear power plant, the general practice was to continuously burn the fuel. In research reactor, most operations are based on the immediate needs of the reactor and our RTP for example operate periodically. By integrating the burnup contribution for each core configuration, we simplify the simulation of burn up for each core configuration. Our results for two (2) fuel however indicates that the dose from simulation underestimate the actual dose from our measurements. Several postulates are investigated but the underlying reason remain inconclusive.

  14. Základy fúzní energetiky II - Základní fyzika fúzních reaktorů

    Czech Academy of Sciences Publication Activity Database

    Entler, Slavomír; Mlynář, Jan; Dostál, V.

    Srpen (2016), č. článku 14538. ISSN 1801-4399 Institutional support: RVO:61389021 Keywords : Nuclear fusion * fusion reactors * plasma Subject RIV: JF - Nuclear Energetics http://energetika.tzb-info.cz/elektroenergetika/14538-zaklady-fuzni-energetiky-ii-zakladni-fyzika-fuznich-reaktoru

  15. Overview of the carbon products consortium (CPC)

    Energy Technology Data Exchange (ETDEWEB)

    Irwin, C.L. [West Virginia Univ., Morgantown, WV (United States)

    1996-08-01

    The Carbon Products Consortium (CPC) is an industry, university, government cooperative research team which has evolved over the past seven years to produce and evaluate coal-derived feedstocks for carbon products. The members of the Carbon Products Consortium are UCAR Carbon Company, Koppers Industries, CONOCO, Aluminum Company of America, AMOCO Polymers, and West Virginia University. The Carbon and Insulation Materials Technology Group at Oak Ridge National Laboratory, Fiber Materials Inc., and BASF Corporation are affiliates of the CPC. The initial work on coal-derived nuclear graphites was supported by a grant to WVU, UCAR Carbon, and ORNL from the U.S. DOE New Production Reactor program. More recently, the CPC program has been supported through the Fossil Energy Materials program and through PETC`s Liquefaction program. The coal processing technologies involve hydrogenation, extraction by solvents such as N-methyl pyrolidone and toluene, material blending, and calcination. The breadth of carbon science expertise and manufacturing capability available in the CPC enables it to address virtually all research and development issues of importance to the carbon products industry.

  16. Early stage fuel cell funding

    International Nuclear Information System (INIS)

    Bergeron, C.

    2004-01-01

    'Full text:' Early stage venture funding requires an in depth understanding of both current and future markets as well as the key technical hurdles that need to be overcome for new technology to commercialize into successful products for mass markets. As the leading fuel cell and hydrogen investor, Chrysalix continuously reviews global trends and new technologies, evaluates them with industry leaders worldwide and tries to match them up with the best possible management teams when selecting its early stage investments. Chrysalix Energy Limited Partnership is an early-stage venture capital firm focusing on fuel cell and related fueling technology companies and is a private equity joint venture between Ballard Power Systems, BASF Venture Capital, The BOC Group, The Boeing Company, Duke Energy, Mitsubishi Corporation and Shell Hydrogen. Operating independently, Chrysalix offers a unique value proposition to its clients throughout the business planning, start-up and operations phases of development. Chrysalix provides early-stage funding to new companies as well as management assistance, technological knowledge, organized networking with industry players and experience in the management of intellectual property. (author)

  17. Trend of the strategy of European and American chemical industry in the restructuring; Obei kagaku sangyo no saihen ni miru senryaku no doko

    Energy Technology Data Exchange (ETDEWEB)

    Niimi, M.; Yamabe, T.

    1999-12-01

    The business of life science is the cover products which connect directly with life such as medical supplies, functional food, nutriments, agricultural chemicals or seeds. The wave of the reorganization of enterprises in the life science field also spread to the integration of the medicine specialty enterprises, and new association trees mainly on medical supplies such as Novartis in Switzerland, Zeneca, Astra Zeneca and Glaxo Wellcome in England were born. Many major chemistry manufacturers are also agricultural chemical manufacturers. Though agricultural chemicals were being shifted to one which being effective at the low use owing to the environmental problems, with the advance of the popularization of gene recombination crops, sales decreased on the agricultural chemical business more, and participation and restructuring to the seed business were accelerated. In this paper, the outline of business restructuring and strengthening the basic strategy in the main chemistry enterprises in Europe and the U.S.A. are described. As a trend of the restructuring, some examples on Du Pont, Dow chemical, Monsanto, ICI, Akzo Nobel, Novartis, Shell Chemicals, BASF, Hoechst and Bayer are introduced. (NEDO)

  18. PERANCANGAN PEMBANGKIT LISTRIK TENAGA SAMPAH ORGANIK ZERO WASTE DI KABUPATEN TEGAL (STUDI KASUS DI TPA PENUJAH KABUPATEN TEGAL

    Directory of Open Access Journals (Sweden)

    Abdul Muiz Liddinillah Sanfiyan

    2017-12-01

    Full Text Available Permasalahan sistem pengolahan sampah yang ada di Kabupaten Tegal adalah masih menggunakan sistem Open Dumping. Berdasarkan data yang diperoleh dari Badan Pusat Statistik (BPS Kabupaten Tegal pada tahun 2016, komposisi sampah organik adalah yang terbesar kedua setelah sampah plastik dan sangat berpotensi mengalami penambahan setiap tahunnya. Tujuan dari penelitian ini adalah untuk membuat perancangan pembangkit listrik tenaga sampah organik zero waste di Kabupaten Tegal, dengan studi kasus di Tempat Pembuangan Akhir (TPA sampah Penujah. Objek dalam penelitian ini adalah sistem pengolahan sampah organik yang ada di Kabupaten Tegal dengan menggunakan sistem pengolahan sampah zero waste. Sistem pengolahan sampah organik zero waste adalah sistem pengolahan sampah yang tidak menghasilkan sampah kembali. Jadi, diharapkan jumlah sampah organik akan berkurang secara bertahap. Sampah organik dapat dirubah menjadi biogas melalui proses fermentasi yang dibantu oleh bakteri secara anaerob di dalam reaktor biodigester. Biogas tersebut ditampung di dalam tempat penampungan untuk kemudian didistribusikan ke dalam genset biogas sebagai bahan bakar pembangkit listrik. Sisa pengolahan biogas dapat dirubah menjadi pupuk cair dan pupuk kompos yang bernilai ekonomis.

  19. Remerschen nuclear power station with BBR pressurized water reactor

    International Nuclear Information System (INIS)

    Hoffmann, J.P.

    1975-01-01

    On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

  20. Data base formation for important components of reactor TRIGA MARK II

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, R; Mavko, B; Kozuh, M [Inst. Jozef Stefan, Ljubljana (Slovenia)

    1992-07-01

    The paper represents specific data base formation for reactor TRIGA MARK II in Podgorica. Reactor operation data from year 1985 to 1990 were collected. Two groups of collected data were formed. The first group includes components data and the second group covers data of reactor scrams. Time related and demand related models were used for data evaluation. Parameters were estimated by classical method. Similar data bases are useful everywhere where components unavailabilities may have severe drawback. (author) [Slovenian] V referatu smo prikazali raziskavo, v okviru katere smo za raziskovalni reaktor TRIGA MARK II v Podgorici izoblikovali specificno bazo podatkov. Zbrali smo podatke obratovanja reaktorja od leta 1985 do 1990. Rezultate raziskave dogodkov smo razdelili v dve glavni skupini. V prvo spadajo obratovalni podatki o komponentah, v drugo skupino pa spadajo zagoni oz. zaustavitve reaktorja. Podatke smo ovrednotili z modelom v casovnem prostoru in z modelom na zahtevo. Parametre modelov smo dolocili s klasicno metodo. Opisane baze podatkov so uporabne povsod, kjer so lahko posledice nezanesljivega delovanja sistemov velike. [author].

  1. Investigations of coal ignition in a short-range flame burner using optical measuring systems; Untersuchungen zur Kohlezuendung am Flachflammenbrenner unter Verwendung optischer Messtechnik

    Energy Technology Data Exchange (ETDEWEB)

    Hackert, G.; Kremer, H.; Wirtz, S. [Bochum Univ. (Germany). Lehrstuhl fuer Energieanlagentechnik

    1999-09-01

    The short-range flame burner and the KOALA reactor of DMT are experimental facilities for realistic simulation of coal conversion processes at high temperatures and pressures in atmospheric conditions. The TOSCA system enable measurements of temperatures, sizes, shapes and velocities of the fuel particles, which serve as a basis for a three-dimensional simulation model of coal combustion. In the future, further parameter studies will deepen the present knowledge of coal dust combustion under pressure and enable optimisation of the numerical models for simulation of industrial-scale systems for coal dust combustion under pressure. [Deutsch] Mit dem Flachflammenbrenner und dem KOALA-Reaktor der DMT stehen Versuchsapparaturen zur Verfuegung, mit deren Hilfe die Kohleumwandlungsprozesse bei hohen Temperaturen unter Druck und unter atmosphaerischen Bedingungen realistisch wiedergegeben werden. Das TOSCA-System erlaubt dabei die Bestimmung von Temperaturen, Groessen, Formen und Geschwindigkeiten der Brennstoffpartikel. Diese Daten liefern die Grundlage fuer die Erstellung eines dreidimensionalen Simulationsmodells zur Modellierung der Kohleverbrennung. In Zukunft werden weitere Parameterstudien das Verstaendnis der Kohlenstaubdruckverbrennung vertiefen und ein Optimierung der numerischen Modelle ermoeglichen, so dass die Simulation grosstechnischer Kohlenstaubdruckverbrennungsanlagen realisiert werden kann. (orig.)

  2. Pirolisis Campuran Sampah Plastik Polistirena Dengan Sampah Plastik Berlapisan Aluminium Foil (Multilayer

    Directory of Open Access Journals (Sweden)

    Yebi Yuriandala

    2016-04-01

    Full Text Available Sampah plastik yang dulunya merupakan masalah lingkungan, saat ini dapat diubah menjadi bahan bakar alternatif dengan menggunakan proses daur ulang yang memanfaatkan energi panas yaitu pirolisis. Analisis yang digunakan dalam penelitian ini adalah analisis terhadap minyak (liquid yang dihasilkan dari pirolisis sampah plastik Polistitren (PS, plastik berlapisan aluminium foil (kemasan/ multilayer (AL dan campuran plastik tersebut. Penelitian ini dilakukan untuk mendapatkan kuantitas produk dan senyawa kimia yang dihasilkan dari pirolisis sampah plastic PS, kemasan dan campuran keduanya. Penelitian dilakukan dengan menempatkan 50 gram PS (PS, 50 gram plastik berlapisan aluminium foil (AL (multi layer,dan PS dengan campuran 10%, 20%, 30%, 40% AL didalam reaktor pirolisis yang terbuat dari stainless steel berbentuk silinder dengan volume 0,96 m3 dengan temperatur akhir 450oC. hasil penelitian menunjukkan bahwa semakin banyak penambahan Plastik berlapisan aluminium foil maka semakin cepat naiknya temperatur mencapai titik optimum yang ditetapkan (450oC. Sedangkan senyawa kimia yang dihasilkan pada pirolisis yang mengandung PS sebagian besar berupa senyawa aromatic, sedangkan pada pirolisis AL sebagian besar berupa senyawa olefin.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-03-15

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

  4. STUDY ON DISCHARGE HEAT UTILIZATION OF 250 MWe PCMSR TURBINE SYSTEM FOR DESALINATION USING MODIFIED MED

    Directory of Open Access Journals (Sweden)

    Andang Widiharto

    2015-03-01

    Full Text Available PCMSR (Passive Compact Molten Salt Reactor is one type of Advanced Nuclear Reactors. The PCMSR has benefit charasteristics of very efficient fuel use, high safety charecteristic as well as high thermodinamics efficiency. This is due to its breeding capability, inherently safe characteristic and totally passive safety system. The PCMSR design consists of three module, i.e. reactor module, turbine module and fuel management module. Analysis in performed by parametric calculation of the turbine system to calculate the turbine system efficiency and the hat available for desalination. After that the mass and energi balance of desalination process are calculated to calculate the amount of distillate produced and the amount of feed sea water needed. The turbine module is designed to be operated at maximum temperature cycle of 1373 K (1200 0C and minimum temperature cycle of 333 K (60 0K. The parametric calculation shows that the optimum turbine pressure ratio is 4.3 that gives the conversion efficiency of 56 % for 4 stages turbine and 4 stages compressor and equiped with recuperator. In this optimum condition, the 250 MWe PCMSR turbine system produces 196 MWth of waste heat with the temperature of cooling fluid in the range from 327 K (54 0C to 368 K (92 0C. This waste heat can be utilized for desalination. By using MMED desalination system, this waste heat can be used to produce fresh water (distillate from sea water feed. The amount of the destillate produced is 48663 ton per day by using 15 distillation effects. The performance ratio value is 2.8727 kg/MJ by using 15 distillation effects. Keywords: PCMSR, discharged heat, MMED desalination   PCMSR (Passive Compact Molten Salt Reactor merupakan salah satu tipe dari Reaktor Nuklir Maju. PCMSR memiliki keuntungan berupa penggunaan bahan bakar yang sangat efisisien, sifat keselamatan tinggi dan sekaligus efisiensi termodinamika yang tinggi. Hal ini disebabkan oleh kemampuan pembiakan bahan bakar, sifat

  5. THERMAL NEUTRON FLUX MAPPING ON A TARGET CAPSULE AT RABBIT FACILITY OF RSG-GAS REACTOR FOR USE IN k0-INAA

    Directory of Open Access Journals (Sweden)

    Sutisna Sutisna

    2015-03-01

    Full Text Available Instrumental neutron activation analysis based on the k0 method (k0-INAA requires the availability of the accurate reactor parameter data, in particular a thermal neutron flux that interact with a targets inside the target capsule. This research aims to determine and map the thermal neutron flux inside the capsule and irradiation channels used for the elemental quantification using the k0-AANI. Mapping of the thermal neutron flux (фth on two type of irradiation capsule have been done for RS01 and RS02 facilities of RSG-GAS reactor. Thermal neutron flux determined using Al-0,1%Au alloy through 197Au(n,g 198Au nuclear reaction, while the flux mapping done using statistics R. Thermal neutron flux are calculated using k0-IAEA software provided by IAEA. The results showed the average thermal neutron flux is (5.6±0.3×10+13 n.cm-2.s-1; (5.6±0.4×10+13 n.cm-2.s-1; (5.2±0.4×10+13 n.cm-2.s-1 and (5.3±0.4×10+13 n.cm-2.s-1 for Polyethylene capsule of 1st , 2nd, 3rd and 4th layer respectively. In the case of Aluminum capsule, the thermal neutron flux was lower compared to that on Polyethylene capsule. There were (3.0±0.2×10+13 n.cm-2.s-1; (2.8±0.1×10+13 n.cm-2.s-1; (3.2±0.3×10+13 n.cm-2.s-1 for 1st, 2nd and 3rd layers respectively. For each layer in the capsule, the thermal neutron flux is not uniform and it was no degradation flux in the axial direction, both for polyethylene and aluminum capsules. Contour map of eight layer on polyethylene capsule and six layers on aluminum capsule for RS01 and RS02 irradiation channels had a similar pattern with a small diversity for all type of the irradiation capsule. Keywords: thermal neutron, flux, capsule, NAA   Analisis aktivasi neutron instrumental berbasis metode k0 (k0-AANI memerlukan ketersediaan data parameter reaktor yang akurat, khususnya data fluks neutron termal yang berinteraksi dengan inti sasaran di dalam kapsul target. Penelitian ini bertujuan menentukan dan memetakan fluks neutron termal

  6. Anaerobic degradation of tetrachloroethylene; Anaerober Abbau von Tetrachlorethylen

    Energy Technology Data Exchange (ETDEWEB)

    Diekert, G. [Stuttgart Univ. (Germany). Inst. fuer Mikrobiologie; Scholz-Muramatsu, H. [Stuttgart Univ. (Germany). Inst. fuer Siedlungswasserbau

    1996-12-31

    Dehalospirillum multivorans, a tetrachloroethylene-dechlorinating bacterium, was isolated in activated sludge. This organism is able to grow on a defined medium with hydrogen and tetrachloroethylene (PCE) as its only energy source. The organism was characterised and the physiology of dechlorination was studied. In this process PCE is dechlorinated to cis-1,2-dichloroethene (DCE) via trichloroethene (TCE). A fluidized-bed reactor which reduces PCE to DCE at a high rate (15 nmol/min/mg of protein at 5 {mu}M PCE) was inoculated with the bacterium. Meanwhile a reactor inoculated with D. multivorans and a fully dechlorinating mixed culture has become available which catalyses the complete dechlorination of PCE to ethene at just as high rates. Tetrachloroethene dehalogenase was purified from D. multivorans (unpublished results) and characterised. (orig./SR) [Deutsch] Aus Belebtschlamm wurde ein Tetrachlorethen-dechlorierendes Bakterium, Dehalospirillum multivorans, isoliert. Der Organismus waechst auf definiertem Medium mit Wasserstoff und Tetrachlorethen (PCE) als einziger Energiequelle. Der Organismus wurde charakterisiert und die Physiologie der Dechlorierung wurde untersucht. PCE wird dabei ueber Trichlorethen (TCE) bis zum cis-1,2-Dichlorethen (DCE) dechloriert. Mit diesem Bakterium wurde ein Wirbelschichtreaktor inokuliert, der mit hohen Raten (15 nmol/min/mg Protein bei 5 {mu}M PCE) PCE zu DCE reduziert. Inzwischen steht ein Reaktor zur Verfuegung, der mit D. multivorans und einer voellig dechlorierenden Mischkultur inokuliert wurde und der mit ebenso hohen Raten eine vollstaendige Dechlorierung von PCE bis zum Ethen katalysiert. Aus D. multivorans wurde die Tetrachlorethen-Dehalogenase gereinigt (unveroeffentlichte Ergebnisse) und charakterisiert. (orig./SR)

  7. Anaerobic degradation of tetrachloroethylene; Anaerober Abbau von Tetrachlorethylen

    Energy Technology Data Exchange (ETDEWEB)

    Diekert, G [Stuttgart Univ. (Germany). Inst. fuer Mikrobiologie; Scholz-Muramatsu, H [Stuttgart Univ. (Germany). Inst. fuer Siedlungswasserbau

    1997-12-31

    Dehalospirillum multivorans, a tetrachloroethylene-dechlorinating bacterium, was isolated in activated sludge. This organism is able to grow on a defined medium with hydrogen and tetrachloroethylene (PCE) as its only energy source. The organism was characterised and the physiology of dechlorination was studied. In this process PCE is dechlorinated to cis-1,2-dichloroethene (DCE) via trichloroethene (TCE). A fluidized-bed reactor which reduces PCE to DCE at a high rate (15 nmol/min/mg of protein at 5 {mu}M PCE) was inoculated with the bacterium. Meanwhile a reactor inoculated with D. multivorans and a fully dechlorinating mixed culture has become available which catalyses the complete dechlorination of PCE to ethene at just as high rates. Tetrachloroethene dehalogenase was purified from D. multivorans (unpublished results) and characterised. (orig./SR) [Deutsch] Aus Belebtschlamm wurde ein Tetrachlorethen-dechlorierendes Bakterium, Dehalospirillum multivorans, isoliert. Der Organismus waechst auf definiertem Medium mit Wasserstoff und Tetrachlorethen (PCE) als einziger Energiequelle. Der Organismus wurde charakterisiert und die Physiologie der Dechlorierung wurde untersucht. PCE wird dabei ueber Trichlorethen (TCE) bis zum cis-1,2-Dichlorethen (DCE) dechloriert. Mit diesem Bakterium wurde ein Wirbelschichtreaktor inokuliert, der mit hohen Raten (15 nmol/min/mg Protein bei 5 {mu}M PCE) PCE zu DCE reduziert. Inzwischen steht ein Reaktor zur Verfuegung, der mit D. multivorans und einer voellig dechlorierenden Mischkultur inokuliert wurde und der mit ebenso hohen Raten eine vollstaendige Dechlorierung von PCE bis zum Ethen katalysiert. Aus D. multivorans wurde die Tetrachlorethen-Dehalogenase gereinigt (unveroeffentlichte Ergebnisse) und charakterisiert. (orig./SR)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-01-01

    During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1991, three major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. Renewal of the reactor instrumentation was started but but it is behind the schedule in 1991 because the delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA for political reasons. In 1991 most of the existing RA reactor instrumentation was dismantled, only the part needed for basic measurements when reactor is not operated, was maintained. Training of the existing personnel was done regularly, but lack of financial support prevented employment of new workers that would be needed for operation in shifts and regular maintenance. [Serbo-Croat] U proteklom periodu reaktor RA nije bio u pogonu zato sto je 30. jula Republicki komitet za zdravlje i socijalnu politiku republike Srbije, zabranio njegov rad zbog toga sto reaktor ne poseduje sistem za udesno hladjenje i ne poseduje odgovarajuce filtere u sistemu specijalne ventilacije. Kako bi se ubuduce mogao obezbediti

  9. RB research nuclear reactor, Annual report for 1981; Istrazivacki nuklearni reaktor RB, Izvestaj o radu u 1981. godini

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Sotic, O; Pesic, M; Vranic, S; Zivkovic, B; Bogdanovic, M; Petronijevic, M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1981-07-01

    The annual report for 1981 includes the following: utilization of the RB reactor; accident and incidents analysis; description of the reactor equipment status; dosimetry and radiation protection; RB reactor staff; financial data. Seven Annexes to this report are concerned with: maintenance of the reactor components and equipment, including nuclear fuel, heavy water, reactor vessel, heavy water coolant circuit, experimental platforms, absorption rods; maintenance of the electric power supply system, neutron source equipment, crane; control and maintenance of ventilation and heating systems, gas and comprised gas systems, fire protection system; plan for renewal of the reactor components; contents of the RB reactor safety report; reactor staff; review of measured radiation doses; experimental methods; training of the staff; and financial report.

  10. RB research nuclear reactor, Annual report for 1982; Istrazivacki nuklearni reaktor RB, Izvestaj o radu u 1981. godini

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Zivkovic, B [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1982-12-15

    This report includes data concerned with reactor operation and utilization, status of reactor components and equipment, refurbishment of the equipment, dosimetry and radiation protection, reactor staff, financing. It includes 7 Annexes as follows: Maintenance of reactor equipment in 1982; contents of the RB reactor safety report; review of radiation doses in the reactor building and exposure doses for the reactor staff; utilization of the RB reactor in 1982; and financial data.

  11. Report of the Technology Service - Annex B; Prilog B - Izvestaj o radu tehnoloske sluzbe

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-12-15

    During 1982 the Ra reactor was operated at 2 MW power with the initial core configuration with 80% enriched fuel. The reactor power would be limited until the ventilation system is be repaired and the emergency cooling system built. The limited operation regime during 1982 had twofold application: as regular regime for the users according to their demands and for experiments related to the testing operation at 2 MW power level. The following reactor physics activities were affected by this operational regime: methods for regular operation control (determining power density and burnup distribution, reactivity variation, et,); measurement of utilization parameters (spatial distribution of the neutron flux); analysis of origin and consequences of irregularities during operation (control of heavy water and gas composition by gamma spectrometry, control of fission products, control of the heavy water purification system); safety analyses including future new systems (emergency cooling and ventilation) [Serbo-Croat] Reaktor RA je tokom 1982 godine radio sa pocetnom konfiguracijom jezgra sa 80% obogacenim gorivom na snazi od 2 Mw. Snaga je ogranicena dok se ne izvrsi rekonstrukcija sistema ventilacije i ugradnja sistema za udesno hladjenje. Rezim rada na ogranicenoj snazi koriscen je u 1982. godini dvojako: kao normalni radni rezim za potrebe korisnika i za eksperimenta u okviru probnog rada na snazi 2 MW. Ovim rezimom rada uslovljene su delatnosti u okviru reaktorske fizike na sledece oblasti: metodologija kontrole redovnog radnog rezim (odredjivanje raspodele snage i izgaranja goriva, promene reaktivnosti, itd.), merenje eksploatacionih parametara reaktora (prostorna raspodela neutronskog fluks, i sl,), analiza uzroka i posledica pojava neregularnosti u radu fizickim metodama (kontrola sadrzaja teske vode i gasa gama spektometrijom, kontrola fisionih produkata, kontrola sistema za preciscavanje teske vode), sigurnosne analize ukljucujuci buducu izgradnju novih sistema

  12. Development of High Level Trigger Software for Belle II at SuperKEKB

    International Nuclear Information System (INIS)

    Lee, S; Itoh, R; Katayama, N; Mineo, S

    2011-01-01

    The Belle collaboration has been trying for 10 years to reveal the mystery of the current matter-dominated universe. However, much more statistics is required to search for New Physics through quantum loops in decays of B mesons. In order to increase the experimental sensitivity, the next generation B-factory, SuperKEKB, is planned. The design luminosity of SuperKEKB is 8 x 10 35 cm −2 s −1 a factor 40 above KEKB's peak luminosity. At this high luminosity, the level 1 trigger of the Belle II experiment will stream events of 300 kB size at a 30 kHz rate. To reduce the data flow to a manageable level, a high-level trigger (HLT) is needed, which will be implemented using the full offline reconstruction on a large scale PC farm. There, physics level event selection is performed, reducing the event rate by ∼ 10 to a few kHz. To execute the reconstruction the HLT uses the offline event processing framework basf2, which has parallel processing capabilities used for multi-core processing and PC clusters. The event data handling in the HLT is totally object oriented utilizing ROOT I/O with a new method of object passing over the UNIX socket connection. Also under consideration is the use of the HLT output as well to reduce the pixel detector event size by only saving hits associated with a track, resulting in an additional data reduction of ∼ 100 for the pixel detector. In this contribution, the design and implementation of the Belle II HLT are presented together with a report of preliminary testing results.

  13. Dual Layer Monolith ATR of Pyrolysis Oil for Distributed Synthesis Gas Production

    Energy Technology Data Exchange (ETDEWEB)

    Lawal, Adeniyi [Stevens Institute of Technology, Castle Point Hoboken NJ 07030

    2012-09-29

    We have successfully demonstrated a novel reactor technology, based on BASF dual layer monolith catalyst, for miniaturizing the autothermal reforming of pyrolysis oil to syngas, the second and most critical of the three steps for thermochemically converting biomass waste to liquid transportation fuel. The technology was applied to aged as well as fresh samples of pyrolysis oil derived from five different biomass feedstocks, namely switch-grass, sawdust, hardwood/softwood, golden rod and maple. Optimization of process conditions in conjunction with innovative reactor system design enabled the minimization of carbon deposit and control of the H2/CO ratio of the product gas. A comprehensive techno-economic analysis of the integrated process using in part, experimental data from the project, indicates (1) net energy recovery of 49% accounting for all losses and external energy input, (2) weight of diesel oil produced as a percent of the biomass to be ~14%, and (3) for a demonstration size biomass to Fischer-Tropsch liquid plant of ~ 2000 daily barrels of diesel, the price of the diesel produced is ~$3.30 per gallon, ex. tax. However, the extension of catalyst life is critical to the realization of the projected economics. Catalyst deactivation was observed and the modes of deactivation, both reversible and irreversible were identified. An effective catalyst regeneration strategy was successfully demonstrated for reversible catalyst deactivation while a catalyst preservation strategy was proposed for preventing irreversible catalyst deactivation. Future work should therefore be focused on extending the catalyst life, and a successful demonstration of an extended (> 500 on-stream hours) catalyst life would affirm the commercial viability of the process.

  14. Bellanca building, Yellowknife : building envelope retrofit project

    Energy Technology Data Exchange (ETDEWEB)

    Rajewski, G. [A.D. Williams Engineering Inc., Edmonton, AB (Canada)

    2008-07-01

    The Bellanca building is a ten-story, commercial office building, located in Yellowknife, Northwest Territories. The owner was concerned about annual fuel consumption, relative to other buildings of similar size. Tenants reported cold drafts and some ice build-up had been reported in the past, on the exterior of the cladding. In addition, some water penetration had occurred during rainfall. This presentation provided background information on the Bellanca building and discussed a building envelope retrofit project. A.D. Williams was hired in late 2006 in order to provide an opinion on the present condition of the building envelope. This presentation described the site investigation and presented an interior and exterior review of the building. It also presented a thermographic survey in order to map thermal anomalies and establish trends. Following acceptance of the report on findings, one of five options was selected for further development. This included removal of existing cladding, exterior gypsum wallboard, fiberglass insulation and application of BASF Walltite CT foam, sheathing, rigid insulation, drainage plane and new cladding. The preliminary design was then presented. This paper also described the tender and award of the contract; construction phase; and substantial completion of the project. tabs, figs.

  15. New EN standards for flanges and weld-on fittings now in force. Tricky in the detail, but design of a pipeline entirely in conformity to European codes and standards is possible; Neue EN-Normen fuer Flansche und Schweissfittings in Kraft. Tuecken im Detail, aber die Konstruktion einer Rohrleitung komplett nach Europaeischem Regelwerk wird moeglich

    Energy Technology Data Exchange (ETDEWEB)

    Willauschus, A. [BUHLMANN Rohr-Fittings-Stahlhandel GmbH und Co. KG, Hilden (Germany)

    2008-07-15

    The second edition of EN 1092, Part 1, 'Circular steel flanges', with date of issue November, 2007, the calculation rules of which are now based on the Woelfel-formulae, is now in force. This new edition had become necessary because the June 2002 edition was, indeed, based on EN 1591 as a calculation tool, but only flanges up to DN 600 had been calculated. Rapid establishment of the new EN 1092, Part 1, on the market can be anticipated following this new edition, since the new pipe classes of the chemicals industry, published in PAS 1057, are based on the new EN 1092, Part 1, and BASF has now also become the first major chemicals corporation to convert its flange ordering to this EN standard, starting in early 2008. From 2009 onward, all other major chemicals companies, which drafted PAS 1057 jointly in the 'Pipelines Working Committee' within the 'Process-Engineering Corporation of BDI', will successively follow. The 'Specialist Confederation for Steel Flanges' is also already working on a new flange catalogue based on EN 1092, Part 1. (orig.)

  16. Occupational stress perception and its potential impact on work ability.

    Science.gov (United States)

    Yong, Mei; Nasterlack, Michael; Pluto, Rolf-Peter; Lang, Stefan; Oberlinner, Christoph

    2013-01-01

    To examine perceived stress across employees with different occupational status, to investigate the impact of stress on work ability and to derive conclusions regarding health promotion activities. A comprehensive survey combining questionnaire and medical examination was offered in one division in BASF Ludwigshafen. Among 867 voluntary participants, 653 returned complete questionnaires. The questions were directed at perception of safety at the workplace, self-rated health status, frequency of stress symptoms, unrealistic job demands, time pressure and maladjustment of work life balance. The outcome of interest was self-estimated health measured by the Work Ability Index (WAI). Occupational stressors were perceived differently across occupational status groups. Frontline operators had more health concerns due to workplace conditions, while professional and managerial staff reported higher frequencies of perceived tension, time pressure, and maladjustment of work life balance. After adjustment for occupational status, demographic and lifestyle factors, perceived stress was associated with a modest to strong decline in WAI scores. While perceived occupational stress had an apparent impact on WAI, and WAI has been demonstrated to be predictive of early retirement, more intensive and employee group-specific stress management interventions are being implemented beyond traditional strategies of routine occupational medical surveillance.

  17. Pyraclostrobin wash-off from sugarcane leaves and aerobic dissipation in agricultural soil.

    Science.gov (United States)

    Fulcher, James M; Wayment, Darcey G; White, Paul M; Webber, Charles L

    2014-03-12

    To mitigate damage from the fungal sugarcane pathogen brown rust (Puccinia melanocephala), a Section 18 Emergency Use Label was put in place by the United States Environmental Protection Agency (U.S. EPA) for the application of pyraclostrobin (trade name Headline SC, produced by BASF, Research Triangle Park, NC) on sugarcane in 2008. To assess the dynamics of this fungicide in Louisiana soil, samples (n = 24) from a non-treated field were spiked with pyraclostrobin (3.1 μg g(-1)) and analyzed in laboratory conditions over the course of 63 days using quick, easy, cheap, effective, rugged, and safe (QuEChERS) dispersive solid-phase extraction/high-performance liquid chromatography with ultraviolet-visible detection (dSPE/HPLC-UV). Modeling was performed using Microsoft Excel to predict DTx values. Pyraclostrobin was found to follow biphasic kinetics with DT50 and DT90 values of 60 and 282 days, suggesting that it is moderately persistent to persistent in soils. Wash-off studies on sugarcane indicate that very little fungicide is in the wash-off after 48 h. If applied to sugarcane according to label recommendations, the fungicide should have minimal dissipation from rainfall events.

  18. Novel Fast Pyrolysis/Catalytic Technology for the Production of Stable Upgraded Liquids

    Energy Technology Data Exchange (ETDEWEB)

    Oyama, Ted; Agblevor, Foster; Battaglia, Francine; Klein, Michael

    2013-01-18

    The objective of the proposed research is the demonstration and development of a novel biomass pyrolysis technology for the production of a stable bio-oil. The approach is to carry out catalytic hydrodeoxygenation (HDO) and upgrading together with pyrolysis in a single fluidized bed reactor with a unique two-level design that permits the physical separation of the two processes. The hydrogen required for the HDO will be generated in the catalytic section by the water-gas shift reaction employing recycled CO produced from the pyrolysis reaction itself. Thus, the use of a reactive recycle stream is another innovation in this technology. The catalysts will be designed in collaboration with BASF Catalysts LLC (formerly Engelhard Corporation), a leader in the manufacture of attrition-resistant cracking catalysts. The proposed work will include reactor modeling with state-of-the-art computational fluid dynamics in a supercomputer, and advanced kinetic analysis for optimization of bio-oil production. The stability of the bio-oil will be determined by viscosity, oxygen content, and acidity determinations in real and accelerated measurements. A multi-faceted team has been assembled to handle laboratory demonstration studies and computational analysis for optimization and scaleup.

  19. SOCMA study urges flexibility

    International Nuclear Information System (INIS)

    Kirschner, E.

    1993-01-01

    In implementing the 1990 Pollution Prevention Act, regulators and legislators should hold off on cookie-cutter, numerical goal-based requirements to allow for site and process specific programs, says a study sponsored by the Synthetic Organic Chemicals Manufacturers Association (SOCMA; Washington). Companies should have that flexibility to target their resources toward those activities that reduce pollution cost effectively, says SOCMA environmental quality committee chairman Art Gillen, who is also BASF director of environmental regulatory affairs. The study - conducted by Woodward-Clyde Consultants (Denver) - examines four batch and custom chemical manufacturing films. As in the Clean Air Act, the batch processing of SOCMA-member plants should be considered in new regulations, Gillen says. For example, the study found that most wastes are from shutdowns and cleanouts, and there are frequent charges in waste streams and raw materials. Those characteristics do not lend themselves to annual reduction goals. Also, specific goals could have a wide range of costs: measures to reduce stack air emissions run from $18/lb to $1,106/lb. SOCMA says it will present the study to Congress and the Environmental Protection Agency

  20. Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

    .) upoznavanje eksploatacionih karakteristika reaktora TVRS sa 80% obogacenim gorivom, kao i iskustva u vezi sa koriscenjem tog goriva u reaktoru TVRS u Moskvi; b.) upoznavanje sa elementima sigurnosnih analiza u vezi sa uvodjenjem i kriscenjem tog goriva u reaktoru TVRS kao i c.) razmena gledista o programu prevodjenja reaktora RA na novo 80% obogaceno gorivo. U izvestaju su prikazani rezultati ove posete. Osnovni zakljucci do kojih se doslo jesu: a.) poseta je bila korisna i pored toga sto na neka pitanja nije dobijen odgovor; b.) posle obrade dobijenih informacija, posle sticanja prvih iskustava o koriscenju novog goriva u reaktoru RA kao i posle donosenja definitivnog suda o ravnoteznom rezimu reaktora RA sa novim gorivom, bilo bi veoma korisno da se izvrsi jos jedna poseta Institutu u Moskvi; c.) novo disperziono gorivo je mnogo pouzdanije u eksploataciji od starog 2% obogacenog metalnog goriva (kakvo je sada u reaktoru RA); d.) nije bilo primedbi sa aspekta sigurnosti na nas program prevodjenja (prelazni rezim) reaktora RA na novo gorivo; e.) zatrazice se dopunske informacije o maksimalnom dopustivom stepenu izgaranja 80% obogacenog disperzionog goriva i po potrebi izvrsice se blagovremena revizija predvidjenog optimalnog ravnoteznog rezima izgaranja za reaktor RA (baziranog na maksimalnom izgaranju goriva koje omogucuju parametri reaktora RA); f.) metodologija termickog proracuna gorivnih kanala, koja se primenjuje na reaktor RA ocenjena je kao ekvivalentna postupku koji se primenjuje za proracun kanala reaktora TVRS u Moskvi (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-05-15

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

  2. Methods for measuring nuclear properties of materials, Safety coefficient method and measurement of effective absorption coefficient of graphite by safety coefficient method; Razvijanje metoda merenja nuklearnih karakteristika materijala, Razrada metode koeficijenta opasnosti i merenje efektivnog apsorpcionog preseka grafita metodom koeficijenta opasnosti

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-11-15

    Reactivity of a reactor depends on production, absorption and leaking of neutrons. Change of absorption causes reactivity change, and this fact is used for determining the neutron absorption cross section for the sample inserted in the reactor core. Method for determining the absorption cross section based on reactivity change is called method of safety coefficient. Measurements of neutron absorption cross section for graphite was done in the RA reactor vertical experimental channel VK-5. taking into account the results obtained for five types of graphite this method is considered to be reliable for use. Comparison of nuclear properties of different types of graphite was done as well. Reaktivnost reaktora zavisi od proizvodnje neutrona, apsorpcije i isticanja neutrona. Promena apsorpcije izaziva promene reaktivnosti reaktora pa se ova osobina koristi za odedjivanje neutronskog apsorpcionog preseka uzorka koji se unosi u reaktor. Metoda merenja apsorpcionog preseka na bazi promene reaktivnosti nazvana je metodom koeficijenta opasnosti. Merenje apsorpcionog preseka grafita uradjeno je na reaktoru RA u vertikalnom eksperimentalnom kanalu VK-5. S obzirom na rezultate koji su dobijeni za pet vrsta grafita moze se smatrati da je opravdano koriscenje ove metode. Izvrseno je i poredjenje nuklearnih osobina pomenutih tipova grafita.

  3. Impact Of Secondary-Primary Pumps Operating Sequence On The Electrical Power Supply System

    International Nuclear Information System (INIS)

    Suwoto; Rusdiyanto; Kiswanto

    2001-01-01

    The operating procedure of the reactor cooling system has decided that the primary cooling pump should be operated before secondary cooling pump as known primary-secondary pumps operating sequence. This decision is based on consideration that starting current of the primary pump is higher than secondary pump. Therefore, the primary-secondary pumps operating sequence can avoid the power supply system failure. However, this operating procedure has to take a consequence that in case of primary pump failure, the shutdown time period of the reaktor to be longer caused to re operate the primary pump has required that the running secondary pump should be shutted off. To solve this problem, an impact analysis of the secondary-primary pumps operating sequence on the electric power supply system was carried out to identify the revision possibility of the cooling pump operating procedure. The analysis by discussion of the measuring results of the secondary and primary pump starting current related to another electrical loads has been measured. From discussion it can be concluded that secondary-primary pumps operating sequence has no impact to failure in electric power supply system

  4. Conceptual Design of On-line Based Licensing Review and Assesment System of Nuclear Installations and Nuclear Materials ('PRIBEN')

    International Nuclear Information System (INIS)

    Melani, Ai; Chang, Soon Heung

    2008-01-01

    At the present Indonesia has no nuclear power plant in operation yet, although it is expected that the first nuclear power plant will be operated and commercially available in around the year of 2016 to 2017 in Muria Peninsula. There are only three research reactors, one nuclear fuel fabrication plant for research reactors, and one experimental fuel fabrication plant for nuclear power, one isotope production facility and some other research facilities. All the facility is under Nuclear Energy Regulatory Agency (BAPETEN) controlling through regulation, licensing and inspection. The organizations operation submits licensing application to BAPETEN before utilizing the facility. According to the regulation before BAPETEN give license they perform review and assessment for the utility application. Based on the review and assessment result, BAPETEN may stipulate, reject, delay or terminate the license. In anticipation of expansion of the nuclear program in Indonesia, BAPETEN should have an integrated and updated system for review and asses the licensing application. For this reason, an expert system for the review and asses the licensing application, so-called PRIBEN (Perizinan Reaktor, Instalasi dan Bahan Nuklir/Licensing of Reactor, Nuclear Installations and Nuclear Materials), is developed which runs on the online-based reality environment

  5. Passive device for emergency core cooling of pressurized water reactors. Pasivno ustrojstvo za bezopasnost na vodo-voden atomen reaktor

    Energy Technology Data Exchange (ETDEWEB)

    Sikora, D

    1984-02-28

    The device proposed ensures additional margin of reactor subcriticality in case of post-accident emergency core cooling (ECC), using concentrated solution of chemical absorber and hot water from the secondary circuit. It consists of: a) a differential cylinder with a differential piston in it, with a lid and a seal, connected to a pipeline for secondary coolant; b) a pipeline for the secondary coolant; c) a volume between the lid and the piston for the secondary coolant from the steam generator; d) a discharge pipeline with a check valve of seal type connecting the inner volume of the differential cylinder to the discharge line; and e) a pipeline from the high-pressure volume of the differential cylinder filled with concentrated chemical absorber solution, to one of the main circulation loops. The device permits ECC innovation of the operating non-standard nuclear power plants with PWR type reactors.

  6. Possibilities of using metal uranium fuel in heavy water reactors; Mogucnosti upotrebe metalnog urana kao goriva za teskovodne reaktore

    Energy Technology Data Exchange (ETDEWEB)

    Djuric, B; Mihajlovic, A; Drobnjak, Dj [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1965-11-15

    There are serious economic reasons for using metal uranium in heavy water reactors, because of its high density, i.e. high conversion factor, and low cost of fuel elements production. Most important disadvantages are swelling at high burnup and corrosion risk. Some design concepts and application of improved uranium obtained by alloying are promising for achievement of satisfactory stability of metal uranium under reactor operation conditions. Postoje ozbiljni ekonomski razlozi za primenu metalnog urana u teskovodnim reaktorima, pre svega zbog njegove velike gustine, odnosno visokog konverzionog faktora, i zbog niskih troskova proizvodnje gorivnih elemenata. Glavne prepreke su bubrenje pri velikim stepenima sagorevanja i opasnost od korozije. Postoje veliki izgledi da se primenom odredjenih projektnih koncepcija i upotrebom legiranjem poboljsanog urana postigne zadovoljavajuca stabilnost metalnog urana u uslovima rada reaktora (author)

  7. The effectiveness of stone ash and volcanic ash of mount Sinabung as a filler on the initial strength of self-compacting concrete

    Science.gov (United States)

    Karolina, R.; Muhammad, W.; Saragih, M. D. S. M.; Mustaqa, T.

    2018-02-01

    Self Compacting Concrete is a concrete variant that has a high degree of workability and also has great initial strength, but low water cement factor. It is also self-flowable that can be molded on formwork with a very little or no compacted use of compactors. This concrete, using a variety of aggregate sizes, aggregate portions and superplasticizer admixture to achieve a special viscosity that allows it to flow on its own without the aid of a compactor. Lightweight concrete brick is a type of brick made from cement, sand, water, and developers. Lightweight concrete bricks are divided into 2 based on the developed materials used are AAC (Autoclave Aerated Concrete) using aluminum paste and CLC (Cellular Lightweight Concrete) that use Foaming Agent from BASF as a developer material. In this experiment, the lightweight bricks that will be made are CLC type which uses Foaming Agent as the developer material by mixing the Ash Stone produced by Stone Crusher machine which has the density of 2666 kg / m3 as Partial Pair Substitution. In this study the variation of Ash Stone used is 10%, 15%, and 20% of the planned amount of sand. After doing the tasting the result is obtained for 10% variation. Compressive Strength and Absorption Increase will decrease by 25.07% and 39.005% and Variation of 15% compressive strength will decrease by 65,8% and decrease of absorbtion equal to 17,441% and variation of 20% compressive strength will decreased by 67,4 and absorption increase equal to 17,956%.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

    During 1976 there were significant discrepancies in RA reactor operation in comparison with the operating plan made at the end of 1975. Some discrepancies were planned but not all could be foreseen due to the following reasons: no possibility to estimate the precise schedule of aluminium tubes for fuel channels delivery from the; USSR; no means to estimate precise time for repairs that were never performed or were not done during previous 6 years; inability to estimate the time needed for experiments within the program of transfer to highly enriched fuel (which was successfully finished) since some of these experiments were never done before. Some repairs were not planned since unpredicted failures occurred. Six fuel exchanges were planned, but they were somewhat delayed. Detailed data about the planned and achieved reactor operation are shown in this annex as well as interruptions. There were 12 shorter interruptions and safety shutdowns which was in total for 64 hours. Reactor was operated at nominal power of 6.5 MW. There have been no significant accidents, but two cases could be characterised as accidental according to their occurrence not according to the effects. The first was break of the tube next to the heavy water pump, and the second was contamination of the reactor hall and corridor during preparation of the fuel exchange machine (spill of heavy water). This annex covers the data concerned with utilization of experimental facilities and reactor utilization. [Serbo-Croat] Reaktor RA je u toku 1976. godine radio sa znatnijim odstupanjima od plana rada za 1976. godinu, donetom krajem 1975. godine. Medjutim, ni ova procena mogucih odstupanja nije mogla biti korektna iz sledecih, razloga: nemogucnost da se predvidi tacan rok isporuke cevi od specijalne aluminijumske legure iz SSSR za izradu tehnoloskih kanala, nemogucnost da se predvidi tacno vreme potrebno za remonte kakvi ili nisu radjeni ranije ili su radjeni pre vise od 6 godina pod povoljnijim uslovima

  9. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

  10. Preliminary design of RDE feedwater pump impeller

    International Nuclear Information System (INIS)

    Sri Sudadiyo

    2018-01-01

    Nowadays, pumps are being widely used in the thermal power generation including nuclear power plants. Reaktor Daya Experimental (RDE) is a proposed nuclear reactor concept for the type of nuclear power plant in Indonesia. This RDE has thermal power 10 MW th , and uses a feedwater pump within its steam cycle. The performance of feedwater pump depends on size and geometry of impeller model, such as the number of blades and the blade angle. The purpose of this study is to perform a preliminary design on an impeller of feedwater pump for RDE and to simulate its performance characteristics. The Fortran code is used as an aid in data calculation in order to rapidly compute the blade shape of feedwater pump impeller, particularly for a RDE case. The calculations analyses is solved by utilizing empirical correlations, which are related to size and geometry of a pump impeller model, while performance characteristics analysis is done based on velocity triangle diagram. The effect of leakage, pass through the impeller due to the required clearances between the feedwater pump impeller and the volute channel, is also considered. Comparison between the feedwater pump of HTR-10 and of RDE shows similarity in the trend line of curve shape. These characteristics curves will be very useful for the values prediction of performance of a RDE feedwater pump. Preliminary design of feedwater pump provides the size and geometry of impeller blade model with 5-blades, inlet angle 14.5 degrees, exit angle 25 degrees, inside diameter 81.3 mm, exit diameter 275.2 mm, thickness 4.7 mm, and height 14.1 mm. In addition, the optimal values of performance characteristics were obtained when flow capacity was 4.8 kg/s, fluid head was 29.1 m, shaft mechanical power was 2.64 kW, and efficiency was 52 % at rotational speed 1750 rpm. (author)

  11. Flow Cytometry for rapid characterization of colloidal particles of various types in process waters; Floedescytometri foer snabb karaktaerisering av kolloidala partiklar av olika typ i bakvatten - MPKT 05

    Energy Technology Data Exchange (ETDEWEB)

    Degerth, R.; Holmbom, B. [Aabo Akademi, Turku (Finland)

    1998-12-31

    Since more than ten years Flow Cytometry (FCM) has been used for characterization of blood cells and bacteria and has become indispensable for medical and biological use. FCM is able to count thousands of particles per second and simultaneously determine their the type and size ending up in a statistically significant report within less than a minute. The principle of FCM is based on a light excitation of a `lined up` particle stream and a multi-channel determination of scatter and fluorescence. This rapid technology has so far not been used in a greater extent within process industry, except for counting bacteria in milk and beer. BASF of Germany has developed and patented a single-channel fluorescence counter for determination of resin droplets in the process waters of paper making. The FCM, however, is a far more effective and reliable method, being able not only to detect resin droplets but also bacteria, live or dead, as well as other occurring particles. We know we are able to determine bacteria, we have seen resin and we aim to show that FCM is able to give a comprehensive view of the colloidal contents of process waters in paper mills by exploring means to selectively stain the different types of particles. (orig.) 3 refs. CACTUS Research Programme

  12. Flow Cytometry for rapid characterization of colloidal particles of various types in process waters; Floedescytometri foer snabb karaktaerisering av kolloidala partiklar av olika typ i bakvatten - MPKT 05

    Energy Technology Data Exchange (ETDEWEB)

    Degerth, R; Holmbom, B [Aabo Akademi, Turku (Finland)

    1999-12-31

    Since more than ten years Flow Cytometry (FCM) has been used for characterization of blood cells and bacteria and has become indispensable for medical and biological use. FCM is able to count thousands of particles per second and simultaneously determine their the type and size ending up in a statistically significant report within less than a minute. The principle of FCM is based on a light excitation of a `lined up` particle stream and a multi-channel determination of scatter and fluorescence. This rapid technology has so far not been used in a greater extent within process industry, except for counting bacteria in milk and beer. BASF of Germany has developed and patented a single-channel fluorescence counter for determination of resin droplets in the process waters of paper making. The FCM, however, is a far more effective and reliable method, being able not only to detect resin droplets but also bacteria, live or dead, as well as other occurring particles. We know we are able to determine bacteria, we have seen resin and we aim to show that FCM is able to give a comprehensive view of the colloidal contents of process waters in paper mills by exploring means to selectively stain the different types of particles. (orig.) 3 refs. CACTUS Research Programme

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

    Directory of Open Access Journals (Sweden)

    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

  14. Operational experience gained with the failed fuel rod detection system in nuclear power plants

    International Nuclear Information System (INIS)

    Boehm, H.H.; Forch, H.

    1985-01-01

    Brown Boveri Reaktor GmbH together with Krautkramer Company developed such a FAILED FUEL ROD DETECTION SYSTEM (FFRDS) which allows to located defective fuel rods without dismantling the fuel assembly or pulling of individual rods. Since 1979 the FFRDS is employed successfully in various nuclear power plants in Europe, USA, Japan, and Korea. The short inspection time and the high reliability of the method make the FFRDS a true competitor to the sipping method. In this paper the authors discuss the method and the design of the system, the equipment set-up, its features and the experience gained so far. The system has been performed and automated to such an extent that within a short installation period series of fuel assemblies can be tested with relatively short intervals of time (5 minutes for BWR and 7 minutes for PWR fuel assemblies per side). The ability of the system for deployment under various conditions and the experience gained during the past six years have made this system universally applicable and highly sensitive to the requirements of NDT during outages and for transport of FAs to intermediate storage facilities. Comparison of FFRDS to conventional sipping has indicated in several instances that the FFRDS is superior to the latter technique

  15. Combination of biological treatment of waste air and liquid effluents in small and medium-sized businesses by using spherical carrier media in exchange with each other. Final report; Kombination der biologischen Behandlung von Abluft- und Abwasserreinigung in kleinen und mittleren Unternehmen durch die Verwendung von kugeligen Traegermaterialien im gegenseitigen Austausch. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Kunz, P.M.; Brunk, M.; Bentz, P.; Bach, K.; Marcos del Rio, O.; Stahl, B.; Wolf, C.

    2002-05-08

    A combined system for biological treatment of solvent-contaminated liquid and gaseous effluents was to be constructed. The system was to be mobile for demonstration purposes in industrial processes and was to serve for dimensioning of full-scale systems. The system works by a combined process via exchange of spherical carriers with a growth of micro-organisms. Two pilot systems of the Institut fuer Biologische Verfahrenstechnik, one for liquid and one for gaseous effluents, were combined for this purpose, ensuring exchange of carrier materials between the two units. (orig.) [German] Aufgabe im Rahmen dieses F+E-Vorhabens war es gewesen, eine kombinierte biologische Abluft- und Abwasserreinigungsanlage - speziell fuer loesungsmittelhaltige Abluft und Abwaesser - zu untersuchen. Dazu sollte eine Anlage aufgebaut werden, die auch als Demonstrations- und Versuchsanlage zu Industriebetrieben gebracht und dort zur Dimensionierung von full-scale-Anlage eingesetzt werden kann. Idee fuer dieses Vorhaben war gewesen, die Kombination beider Behandlungssysteme ueber den Austausch von mit Mikroorganismen bewachsenem Traegermaterial herzustellen. Am Institut fuer Biologische Verfahrenstechnik existierte bereits eine Pilotanlage fuer die biologische Abwasserreinigung mit kugeligem Traegermaterial (Vario-Bio-Reaktor) und eine Pilotanlage fuer die biologische Behandlung von Abluft nach dem Trickling-Filter-Prinzip mit ebenfalls kugeligem Traegermaterial. Diese beiden Anlagen sollten miteinander kombiniert und der Austausch des Traegermaterials hergestellt werden. (orig.)

  16. Failed fuel rod detection system and computerized manipulator during outages

    International Nuclear Information System (INIS)

    Boehm, H.H.; Foerch, H.

    1984-01-01

    During regular outages spent fuel assemblies need to be replaced and relocated within the core. Defective fuel rods in particular fuel assemblies have to be removed from further service and before delivery of such faulty fuel assemblies to a reprocessing plant. The system which Brown Boveri Reaktor GmbH and Krautkraemer have developed in the Federal Republic of Germany is capable of directly locating the defective rods in a proper fuel assembly. Inspection times are comparable to those of standard sipping methods, with the advantages of immediately available results and direct identification of the defective fuel rods. During the repair of fuel assemblies this system allows withdrawal of individual defective rods. With the sipping method all the fuel rods of a defective fuel assembly need to be removed and inspected by eddy current testing. During steam generator inspection and repair personnel are exposed to ample radiation. A remotely controlled, computerized manipulator was used to significantly reduce the radiation dose by automating steps in the procedures; at the same time inspection and repair times were reduced. The main features of the manipulator are a rigid component construction of the leg and two arms, and a resolver control for horizontal and vertical motion that enables rapid and accurate access to a desired tube (author)

  17. The effective lifetime and temperature coefficient in a coupled fast-thermal reactor; Temps de vie effectif et coefficient de temperature dans un reacteur a couplage neutrons rapides-neutrons thermiques; Ehffektivnyj srok zhizni i temperaturnyj koehffitsient nejtronov v dvoyakom reaktore na bystrykh i teplovykh nejtronakh; Vida efectiva y coeficiente de temperatura en un reactor con acoplamiento rapido-termico

    Energy Technology Data Exchange (ETDEWEB)

    Haefele, W. [Kernforschungszentrum, Karlsruhe (Germany)

    1962-03-15

    . Teplovoj komponent dejstvuet kak svoego roda zamedlitel' vremeni zhizni nejtronov. Kak i v teorii zapazdyvayushchikh nejtronov, ehffekt zapazdyvaniya ischezaet, esli reaktivnost' dostatochno vysoka, chtoby bystryj komponent stal kritichnym sam po sebe. V issledovanii rassmatrivalsya sparennyj reaktor, v kotorom bystryj komponent podvergaetsya dejstviyu vnezapnogo stupenchatogo skachka reaktivnosti {alpha}{sub 0}. Izza vozrastayushchego urovnya ehnergii temperatura podnimaetsya i nachinayut rabotat' dva temperaturnykh koehffitsienta: temperaturnyj koehffitsient bystrogo komponenta i temperaturnyj koehffitsient teplovogo komponenta. Ehta problema rassmatrivaetsya s odnoj gruppoj zapazdyvayushchikh nejtronov (v obychnom znachenii). Privoditsya formalizm dlya vyrazheniya ehffektivnogo sroka zhizni i temperaturnogo koehffitsienta vo vremya razlichnykh stadij issledovaniya. Dany takie otkloneniya dlya razlichnykh znachenij {alpha}{sub 0}, pri kotorykh dostigaetsya predel kinetiki reaktorov na bystrykh nejtronakh. (author)

  18. Microbial liquefaction of peat for the production of synthetic fuels

    Energy Technology Data Exchange (ETDEWEB)

    Gunasekaran, M.

    1988-01-01

    Objectives of this study were: to evaluate the potential of using various microorganisms to hydrolyse and liquify peat; to determine the optimal conditions for peat hydrolysis and liquefaction; to study the co-metabolizable substances; to separate the compounds present in liquified peat by alumina and silica acid chromatography and capillary gas chromatography; and to identify the compounds in liquified peat by capillary GC-Mass spectrometry. Organisms used in the study include: Coprinus comatus, Coriolus hirsutus, Ganoderma lucidum, Lentinus edodes, Lenzites trabea, Phanerochaete chrysosporium, Pleurotus ostreatus, P. sapidus, Polyporus adjustus, Neurospora sitophila, Rhizophus arrhizus, Bacillus subtilis, Acinetobacter sp. and Alcaligenes sp. The fungi were maintained and cultivated in potato dextrose agar at 30 C. The bacteria were maintained in nutrient agar at 30 C. We have also initiated work on coal solubilization in addition to the studies on peat liquefaction. A relatively new substratum or semi-solid base for culture media called Pluronic F-127, or Polyol (BASF, New Jersey). Objectives of this study were: (1) to study the growth patterns of Candida ML 13 on pluronic as substratum; (2) to determine the rate of microbial coal solubilization on pluronic F-127 amended in different growth media; (3) to separate the mycelial mat of Candida ML 13 from unsolubilized coal particles and solubilized coal products from pluronic F-127; (4) to determine the effects of pH on microbial coal solubilization in pluronic F-127 media; (5) the effect of concentration of pluronic F-127 in media on coal solubilization; and, (6) to study the role of extracellular factors secreted by Candida ML 13 on coal solubilization in pluronic F-127 media. Results are discussed. 4 refs.

  19. Pengaruh Pretreatment Secara Alkalisasi-Resistive Heating terhadap Kandungan Lignoselulosa Jerami Padi

    Directory of Open Access Journals (Sweden)

    Dewi Maya Maharani

    2017-09-01

    pretreatment yang berfungsi untuk mendegradasi ikatan lignin, meningkatkan luas permukaan biomassa dan dekristalisasi selulosa. Tujuan dari penelitian ini adalah mengetahui pengaruh alkalisasi resistive heating pada proses pretreatment jerami padi sebelum dikonversi lebih lanjut menjadi bioetanol dan mengetahui pengaruh suhu pemanasan serta konsentrasi NaOH selama pretreatment terhadap perubahan kandungan lignin, selulosa dan hemiselulosa. Sebelum dilakukan penelitian dilakukan perancangan reaktor resistive heating. Jerami padi ukuran 100 mesh dilarutkan pada larutan NaOH dengan variasi konsentrasi 0,03 M, 0,05 M, dan 0,07 M, selanjutnya dipanaskan pada reaktor resistive heating dengan variasi suhu pemanasan 75 oC, 85 oC, dan 99 oC. Selulosa merupakan senyawa yang akan dikonversi lebih lanjut menjadi glukosa. Sehingga pada penelitian ini dipilih kondisi optimum berdasarkan peningkatan selulosa tertinggi hingga 8,88% serta penurunan lignin dan hemiselulosa sebesar 1,39% dan 4,33% pada perlakuan suhu pemanasan 75 oC dan konsentrasi NaOH 0,07 M. Alkalisasi resistive heating dapat diterapkan pada pretreatment jerami padi karena dapat mengurangi kandungan lignin dan hemiselulosa serta meningkatkan kandungan selulosa.

  20. Research nuclear reactor RA - Annual Report 1975. Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1975. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-01-15

    The plan for 1975 was successfully fulfilled. This is reflected in research related to improvement of operating properties of the RA reactor, mostly due to the effort of the RA staff employed in operation and maintenance of the reactor. Fuel saving achieved by this activity amounted to about 38% (80% enriched fuel). Preliminary work is done, concerned with new reactor core with highly enriched fuel. This is a significant saving as well. New fuel elements have arrived at the end of this year. It is going to enable increase of neutron flux by 50% without changing the nominal operating power. The possibility of further improvement of the reactor are analyzed, to enable material testing and production of radioactive sources. Mid term plan for reactor operation was made according to this analysis. It is planned to further increase the neutron flux in isolated smaller zones, and building new experimental loops with cooling and fast neutron converters. Much was done to increase the safety level of reactor operation and preparing the safety report. [Serbo-Croat] Izvrsenje zadataka u 1975. godini bilo je uspesno. To se ogleda u povecanju istrazivackog rada vezanog za poboljsanje eksploatacionih karakteristika reaktora RA, pretezno koriscenjem sopstvenog kadra angazovanog u pogonu i odrzavanju reaktora. Ovim radom postignuta je usteda goriva od oko 38% (80% obogaceno gorivo). Izvrseni su preliminarni radovi na prevodjenju reaktora RA na novo gorivo, sto je takodje velika usteda. Novo gorivo je stiglo krajem godine i ono ce obezbediti porast neutronskog fluksa od 50%, bez promene nominalne snage reaktora. Izvrsena je analiza mogucnosti daljeg usavrsavanja reaktora za potrebe ispitivanja materijala kao i proizvodnju radioaktivnih izvora. Na osnovu ove analize nacinjen je srednjorocni program rada reaktora RA sa tezistem na daljem povecanju fluksa u izdvojenim manjim zonama i ugradnju 'hladjenih petlji' i brzih konvertora. Mnogo je ucinjeno na povecanju stepena sigurnosti reaktora RA i izradi sigurnosnog izvestaja.

  1. Ácido linoléico conjugado (CLA em dietas para tilápia-do-nilo: desempenho produtivo, composição química e perfil de ácidos graxos Conjugated linoleic acid (CLA in Nile tilapia diets: productive performance, chemical and fatty acids composition

    Directory of Open Access Journals (Sweden)

    Lilian Dena dos Santos

    2007-10-01

    Full Text Available Objetivou-se avaliar a influência da adição de CLA na dieta sobre o desempenho produtivo, a composição química e o perfil de ácidos graxos de tilápia-do-nilo. Foram utilizados 80 peixes revertidos, com 109 ± 10 g, distribuídos em oito tanques (0,8 m³ cada, em densidade de 10 peixes/tanque, durante 90 dias. Avaliou-se a inclusão na dieta de 2% de CLA (Luta-CLA®-BASF, Brasil com 60% dos isômeros (cis-9,trans-11 e trans-10,cis-12 e 40% do veículo (ácido oléico e outros ácidos graxos. Como dieta utilizou-se ração comercial extrusada, com 29% PB e 3.000 kcal ED/kg de ração. Ao final do experimento, todos os peixes foram utilizados para avaliação do desempenho, da composição química e do perfil de ácidos graxos no fígado e nos filés. A taxa de eficiência protéica, o rendimento de carcaça, o índice hepatossomático e a gordura visceral não diferiram com a adição de CLA a dieta. A adição de CLA a dieta promoveu melhora no ganho de peso, aumento no consumo e melhora na conversão alimentar. Os peixes alimentados com dietas com adição de CLA apresentaram aumento na composição de ácidos graxos saturados e redução dos ácidos graxos n-6 nos filés. Houve também aumento na composição de ácidos graxos n-3 e de ácidos graxos poliinsaturados totais no fígado. Houve aumento da proteína nos filés de tilápias alimentadas com dietas enriquecidas com CLA. O uso do CLA melhora variáveis de desempenho produtivo, afeta o metabolismo e a proporção dos ácidos graxos nos filés e fígados e aumenta proteína nos filés em tilápia-do-nilo.The objective of this work was to evaluate the influence of the addition of CLA in the diet on Nile tilapia productive performance, chemical and fatty acids composition. Eighty reversed fish with 109 ± 10 g were used, distributed in eight tanks (0.8 m³ each in density of ten fishes/tank, during 90 days. It was evaluated the inclusion in the diets of 2% of CLA (Luta-CLA®-BASF

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-15

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

  3. Post-Irradiation Behaviour of I{sup 131} in TeO{sub 2}; Comportement de {sup 131}I Dans TeO{sub 2} Apres Irradiation; 041f 041e 0412 0415 0414 0415 041d 0418 0415 0419 041e 0414 0410 -131 0412 TeO{sub 2} 0433 041f 041e 0421 041b 0415 041e 0411 041b 0423 0427 0415 041d 0418 042f ; Comportamiento del {sup 131}I en TeO{sub 2} Despues de su Irradiacion

    Energy Technology Data Exchange (ETDEWEB)

    Jacimovic, Lj.; Stevovic, J.; Veljkovic, S. R. [Boris Kidric Institute of Nuclear Sciences, Belgrade, Yugoslavia (Serbia)

    1965-04-15

    cinetica del recocido. (author) [Russian] Sistema joda-131 v TeO{sub 2} predstavljaet interes, potomu chto malo izvestno o termohimicheskih izmenenijah v jetoj misheni. Radioaktivnyj jod poluchalsja pri nejtronnom obluchenii TeO{sub 2} v reaktore. Obluchennyj TeO{sub 2} rastvorjalsja v razbavlennom rastvore NaOH. Analiz razlichnyh valentnyh form joda proizvodilsja ionoobmennym metodom. Izuchalis' termicheskaja i radiacionnaja ustojchivost' TeO{sub 2} putem ispol'zovanija spektrofotometricheskogo metoda dlja opredelenija tellura i otzhig joda-131 v TeO{sub 2} posle obluchenija v zavisimosti ot vremeni i temperatury nagreva. Glavnaja tendencija otzhiga sostojala v vosstanovlenii radioaktivnogo joda. Zavisimost' jetogo processa ot vremeni ukazyvaet na bystroe izmenenie pri vysokoj temperature. Pri bolee nizkih temperaturah krivye javljajutsja bolee slozhnymi. Otzhig verojatno javljaetsja slozhnym vvidu mnogoobrazija teplovyh reakcij, vkljuchajushhih promezhutochnye soedinenija joda. On mozhet vstupat' v reakciju s produktami processa otdachi jader tellura v sootvetstvujushhej gorjachej zone, beta-perehoda Te{sup 131} i s samoj dvuokis'ju tellura. Rassmatrivalas' kinetika jetih izmenenij i proizvodilas' ocenka processov vo vremja otzhiga. Izuchalos' takzhe vlijanie nejtronnogo potoka na kinetiku otzhiga. (author)

  4. Degradation of phosphorescent blue organic light-emitting diodes (OLED); Degradation der phosphoreszenten blauen organischen Leuchtdioden

    Energy Technology Data Exchange (ETDEWEB)

    Chiu, Chien-Shu

    2011-07-01

    Phosphorescent organic materials harvest singlet and triplet excitons through inter-system crossing and improve the efficiency of organic light-emitting diodes (OLEDs). This improvement increases the potential of OLEDs, particularly white phosphorescent OLEDs (PHOLEDs), for lighting application. Although much progress has been made in the development of white PHOLEDs, the lifetime of phosphorescent emitters, especially the blue emitter, still needs to be improved. This thesis discusses the developments of blue PHOLEDs and investigations of degradation mechanisms. For development of blue PHOLEDs, two phosphorescent blue emitters were investigated: commercially available FIrpic and B1 provided by BASF. By varying the matrix and blocker materials, diode efficiency and lifetime have been investigated and improved. Blue PHOLEDs with emitter B1 show better efficiency and lifetime than devices with FIrpic. From lifetime measurement with constant DC current density, intrinsic degradation including luminance loss and voltage increase on both FIrpic and B1 PHOLEDs was observed. Photoluminescence measurement shows degradation in the emitting layers. To investigate the degradation of emitter layers, single-carrier devices with emitter systems or pure matrix materials were fabricated. Degradation on these devices was investigated by applying constant DC current, UV-irradiation and combination of both. We found that due to excited states (excitons), FIrpic molecules become unstable and polarons would enhance the degradation of FIrpic during DC operation and UV-excitation. To investigate the impact the exciton formation and exciton decay have on the degradation of FIrpic molecules, red phosphorescent emitter Ir(MDQ){sub 2}(acac) was doped in blue emitter layer TCTA:20% FIrpic. The doping concentration of Ir(MDQ){sub 2}(acac) was much lower than FIrpic to ensure that most of the exciton formation occurred on FIrpic molecules. Lower triplet energy of Ir(MDQ){sub 2}(acac) molecules

  5. Experience with the SE in Germany

    Directory of Open Access Journals (Sweden)

    Jochem Reichert

    2008-03-01

    Full Text Available A rather significant proportion of the Societas Europaeas (the European Company, or SE formed to date have had German roots. German corporate law has been enriched by an interesting alternative which meanwhile seems to have gained momentum. This contribution focuses on SEs incorporated by German entrepreneurs and provides an interesting account concerning the use of SEs in Germany in practice, such as Allianz, Fresenius, BASF and Porsche. Has the SE been used to circumvent rigid company law provisions or is it a more flexible and effective tool, perhaps, for company mobility? The practical motives behind setting up this company form are also reflected upon. These include: the facilitation of cross-border mergers; transfer of the registered office; the ‘European’ image; a more flexible form of co-determination in large companies (reduction of the number of supervisory board members; avoidance and freezing of co-determination for medium-sized enterprises; the appeal of the one-tier system and its endangerment by German co-determination; and flat and uniform structures for company groups. The author also briefly discusses some of the problems arising from the formation of SEs in Germany. He ultimately concludes that practice has shown that it is possible to work with the legal regime of the SE in Germany, which adds a new company form to those available in that Member State.

  6. The role of driver nodes in managing epileptic seizures: Application of Kuramoto model.

    Science.gov (United States)

    Mohseni, Ali; Gharibzadeh, Shahriar; Bakouie, Fatemeh

    2017-04-21

    Synchronization is an important global phenomenon which could be found in a wide range of complex systems such as brain or electronic devices. However, in some circumstances the synchronized states are not desirable for the system and should be suppressed. For example, excessively synchronized activities in the brain network could be the root of neuronal disorders like epileptic seizures. According to the controllability theory of the complex networks, a minimum set of driver nodes has the ability to control the entire system. In this study, we examine the role of driver nodes in suppressing the excessive synchronization in a generalized Kuramoto model, which consists of two types of oscillators: contrarian and regular ones. We used two different structural topologies: Barabási-Albert scale-free (BASF) network and Caenorhabditis elegans (C.elegans) neuronal network. Our results show that contrarian driver nodes have the sufficient ability to break the synchronized level of the systems. In this case, the system coherency level is not fully suppressed that is avoiding dysfunctions of normal brain functions which require the neuronal synchronized activities. Moreover, in this case, the oscillators grouped in two distinct synchronized clusters that could be an indication of chaotic behavior of the system known as resting-state activity of the brain. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Nutritional impact on the plasma metabolome of rats.

    Science.gov (United States)

    Mellert, W; Kapp, M; Strauss, V; Wiemer, J; Kamp, H; Walk, T; Looser, R; Prokoudine, A; Fabian, E; Krennrich, G; Herold, M; van Ravenzwaay, B

    2011-11-30

    Metabolite profiling (metabolomics) elucidates changes in biochemical pathways under various conditions, e.g., different nutrition scenarios or compound administration. BASF and metanomics have obtained plasma metabolic profiles of approximately 500 compounds (agrochemicals, chemicals and pharmaceuticals) from 28-day rat studies. With these profiles the establishment of a database (MetaMap(®)Tox) containing specific metabolic patterns associated with many toxicological modes of action was achieved. To evaluate confounding factors influencing metabolome patterns, the effect of fasting vs. non-fasting prior to blood sampling, the influence of high caloric diet and caloric restriction as well as the administration of corn oil and olive oil was studied for its influence on the metabolome. All mentioned treatments had distinct effects: triacylglycerol, phospholipids and their degradation product levels (fatty acids, glycerol, lysophosphatidylcholine) were often altered depending on the nutritional status. Also some amino acid and related compounds were changed. Some metabolites derived from food (e.g. alpha-tocopherol, ascorbic acid, beta-sitosterol, campesterol) were biomarkers related to food consumption, whereas others indicated a changed energy metabolism (e.g. hydroxybutyrate, pyruvate). Strikingly, there was a profound difference in the metabolite responses to diet restriction in male and female rats. Consequently, when evaluating the metabolic profile of a compound, the effect of nutritional status should be taken into account. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

  8. Synthesis and Use of Stable Isotope Enriched Retinals in the Field of Vitamin A

    Directory of Open Access Journals (Sweden)

    Johan Lugtenburg

    2010-03-01

    Full Text Available The role of vitamin A and its metabolites in the life processes starting with the historical background and its up to date information is discussed in the introduction. Also the role of 11Z-retinal in vision and retinoic acid in the biological processes is elucidated. The essential role of isotopically enriched systems in the progress of vision research, nutrition research etc. is discussed. In part B industrial commercial syntheses of vitamin A by the two leading companies Hoffmann-La Roche (now DSM and BASF are discussed. The knowledge obtained via these pioneering syntheses has been essential for the further synthetic efforts in vitamin A field by other scientific groups. The rest of the paper is devoted to the synthetic efforts of the Leiden group that gives an access to the preparation of site directed high level isotope enrichment in retinals. First the synthesis of the retinals with deuterium incorporation in the conjugated side chain is reviewed. Then, 13C-labeled retinals are discussed. This is followed by the discussion of a convergent synthetic scheme that allows a rational access to prepare any isotopomer of retinals. The schemes that provide access to prepare any possible isotope enriched chemically modified systems are discussed. Finally, nor-retinals and bridged retinals that give access to a whole (as yet incomplete library of possible isotopomers are reviewed.

  9. High Speed, Low Cost Fabrication of Gas Diffusion Electrodes for Membrane Electrode Assemblies

    Energy Technology Data Exchange (ETDEWEB)

    DeCastro, Emory S.; Tsou, Yu-Min; Liu, Zhenyu

    2013-09-20

    Fabrication of membrane electrode assemblies (MEAs) depends on creating inks or pastes of catalyst and binder, and applying this suspension to either the membrane (catalyst coated membrane) or gas diffusion media (gas diffusion electrode) and respectively laminating either gas diffusion media or gas diffusion electrodes (GDEs) to the membrane. One barrier to cost effective fabrication for either of these approaches is the development of stable and consistent suspensions. This program investigated the fundamental forces that destabilize the suspensions and developed innovative approaches to create new, highly stable formulations. These more concentrated formulations needed fewer application passes, could be coated over longer and wider substrates, and resulted in significantly lower coating defects. In March of 2012 BASF Fuel Cell released a new high temperature product based on these advances, whereby our customers received higher performing, more uniform MEAs resulting in higher stack build yields. Furthermore, these new materials resulted in an “instant” increase in capacity due to higher product yields and material throughput. Although not part of the original scope of this program, these new formulations have also led us to materials that demonstrate equivalent performance with 30% less precious metal in the anode. This program has achieved two key milestones in DOE’s Manufacturing R&D program: demonstration of processes for direct coating of electrodes and continuous in-line measurement for component fabrication.

  10. Effect of composition in the development of carbamazepine hot-melt extruded solid dispersions by application of mixture experimental design.

    Science.gov (United States)

    Djuris, Jelena; Ioannis, Nikolakakis; Ibric, Svetlana; Djuric, Zorica; Kachrimanis, Kyriakos

    2014-02-01

    This study investigates the application of hot-melt extrusion for the formulation of carbamazepine (CBZ) solid dispersions, using polyethyleneglycol-polyvinyl caprolactam-polyvinyl acetate grafted copolymer (Soluplus, BASF, Germany) and polyoxyethylene-polyoxypropylene block copolymer (Poloxamer 407). In agreement with the current Quality by Design principle, formulations of solid dispersions were prepared according to a D-optimal mixture experimental design, and the influence of formulation composition on the properties of the dispersions (CBZ heat of fusion and release rate) was estimated. Prepared solid dispersions were characterized using differential scanning calorimetry, attenuated total reflectance infrared spectroscopy and hot stage microscopy, as well as by determination of the dissolution rate of CBZ from the hot-melt extrudates. Solid dispersions of CBZ can be successfully prepared using the novel copolymer Soluplus. Inclusion of Poloxamer 407 as a plasticizer facilitated the processing and decreased the hardness of hot-melt extrudates. Regardless of their composition, all hot-melt extrudates displayed an improvement in the release rate compared to the pure CBZ, with formulations having the ratio of CBZ : Poloxamer 407 = 1 : 1 showing the highest increase in CBZ release rate. Interactions between the mixture components (CBZ and polymers), or quadratic effects of the components, play a significant role in overall influence on the CBZ release rate. © 2013 Royal Pharmaceutical Society.

  11. Produksi Biofuel dari Minyak Kelapa Sawit dengan Katalis Au/HZSM-5 dan Kompositnya

    Directory of Open Access Journals (Sweden)

    Tillotama Anindita Sari

    2012-09-01

    diperoleh untuk katalis Au/HZSM-5 yield tertinggi kerosene 25,24%, gasoline 15,69% dan diesel 10,71% pada temperatur reaktor 500 °C dengan laju alir  gas N2 90 ml/min. Untuk katalis Komposit (HZSM-5/MCM-41 yield tertinggi diesel 26,53%, kerosene 19,26% dan gasoline 6,41% pada temperatur 450 °C laju alir 300 ml/min serta pada temperatur 350 °C dengan laju alir 90 ml/min dengan yield diesel tertinggi 24,38%, kerosene 18,84% dan gasoline 4,41%.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-12-15

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

  13. Selective separation of anaerobic sludge by means of hydrocyclones; Selektive Abtrennung von Anaerobschlamm mit Hydrozyklonen

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, M.; Bohnet, M. [Technische Univ. Braunschweig (Germany). Inst. fuer Verfahrens- und Kerntechnik

    1999-07-01

    In anaerobic waste water cleaning, biomass concentration constitutes a central problem because of long generating times and low biomass sinking speeds. In order to decouple hydraulic retention time from biomass retention time, biomass must be fed back into the reactor. The fact that separation by means of common gravitational separators such as sedimentation tanks and baffle plate thickeners is unspecific results in the enrichment in the reactor of inorganic solids, whose presence is corollary to the anaerobic sludge process. Hence, industry has a great interest in separating anaerobic sludge into organic and inorganic constituents as a means of safeguarding high operating stability and degradation efficiency of anaerobic reactors. Hydrocyclones, permitting selective separation, are an obvious approach. (orig.) [German] Bei der anaeroben Abwasserreinigung ist die Biomassekonzentrierung aufgrund langer Generationszeiten und geringer Sinkgeschwindigkeiten der Biomasse ein zentrales Problem. Zur Entkopplung der hydraulischen Verweilzeit von der Verweilzeit der Biomasse ist eine Rueckfuehrung der Biomasse erforderlich. Da bisher eingesetzte Schwerkraftabscheider, wie Absetzbecken und Lamellenklaerer, unspezifisch trennen, kommt es zu einer Anreicherung anorganischer Feststoffe im Reaktor, die sich prozessbedingt im Anaerobschlamm befinden. So hat die Industrie ein grosses Interesse an einer Auftrennung des Anaerobschlamms in organische und anorganische Bestandteile, um eine hohe Betriebsstabilitaet und Abbauleistung der Anaerobreaktoren zu gewaehrleisten. Hierzu bieten sich Hydrozyklone an, weil mit ihnen eine selektive Trennung moeglich ist. (orig.)

  14. Fluidized-bed gasification of biomass: Conversion of fine carabon particles in the freeboard; Biomassevergasung in der Wirbelschicht: Umsatz von feinen Kohlenstoffpartikeln im Freeboard

    Energy Technology Data Exchange (ETDEWEB)

    Miccio, F [Ist. Ricerche sulla Combustione-CNR, Napoli (Italy); Moersch, O; Spliethoff, H; Hein, K R.G. [Stuttgart Univ. (Germany). Inst. fuer Verfahrenstechnik und Dampfkesselwesen

    1998-09-01

    The conversion of carbon particles in gasification processes was investigated in a fluidized-bed reactor of the Institute of Chemical Engineering and Steam Boiler Technology of Stuttgart University. This reactor is heated electrically to process temperature, and freeboard coal particles can be sampled using an isokinetic probe. The fuel used in the experiments consisted of beech wood chips. The temperature and air rating, i.e. the main parameters of the process, were varied in order to investigate their influence on product gas quality and carbon conversion. The conversion rate is influenced to a significant extent by grain disintegration and discharge of carbon particles. In gasification conditions, a further conversion process takes place in the freeboard. (orig.) [Deutsch] In dieser Arbeit wird die Umsetzung von Kohlenstoffpartikeln unter Vergasungsbedingungen untersucht. Die Versuche wurden an einem Wirbelschichtreaktor des Instituts fuer Verfahrenstechnik und Dampfkesselwesen der Universitaet Stuttgart durchgefuehrt. Dieser Reaktor wird elektrisch auf Prozesstemperatur beheizt. Mit Hilfe einer isokinetischen Sonde koennen Proben von Kohlenstoffpartikeln im Freeboard genommen werden. Als Brennstoff wurden zerkleinerte Buchenholz-Hackschnitzel eingesetzt. Variiert wurden als Hauptparameter des Prozesses Temperatur und Luftzahl. Untersucht wurde der Einfluss dieser Parameter auf die Qualitaet des Produktgases und die Umsetzung des Kohlenstoffes. Kornzersetzungs- und Austragsvorgaenge von Kohlenstoffpartikeln spielen eine wichtige Rolle fuer den Kohlenstoffumsatz. Unter Vergasungsbedingungen findet im Freeboard eine weitere Umsetzung der Partikel statt. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

    Ninkovic, M; Ajdacic, N; Zaric, M; Vukovic, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    Radon protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each category is described as a separate annex of this report.

  16. UV and humidity sensing properties of ZnO nanorods prepared by the arc discharge method

    International Nuclear Information System (INIS)

    Fang, F; Futter, J; Markwitz, A; Kennedy, J

    2009-01-01

    The UV and humidity sensing properties of ZnO nanorods prepared by arc discharge have been studied. Scanning electron microscopy and photoluminescence spectroscopy were carried out to analyze the morphology and optical properties of the as-synthesized ZnO nanorods. Proton induced x-ray emission was used to probe the impurities in the ZnO nanorods. A large quantity of high purity ZnO nanorod structures were obtained with lengths of 0.5-1 μm. The diameters of the as-synthesized ZnO nanorods were found to be between 40 and 400 nm. The nanorods interlace with each other, forming 3D networks which make them suitable for sensing application. The addition of a polymeric film-forming agent (BASF LUVISKOL VA 64) improved the conductivity, as it facilitates the construction of conducting networks. Ultrasonication helped to separate the ZnO nanorods and disperse them evenly through the polymeric agent. Improved photoconductivity was measured for a ZnO nanorod sensor annealed in air at 200 deg. C for 30 min. The ZnO nanorod sensors showed a UV-sensitive photoconduction, where the photocurrent increased by nearly four orders of magnitude from 2.7 x 10 -10 to 1.0 x 10 -6 A at 18 V under 340 nm UV illumination. High humidity sensitivity and good stability were also measured. The resistance of the ZnO nanorod sensor decreased almost linearly with increasing relative humidity (RH). The resistance of the ZnO nanorods changed by approximately five orders of magnitude from 4.35 x 10 11 Ω in dry air (7% RH) to about 4.95 x 10 6 Ω in 95% RH air. It is experimentally demonstrated that ZnO nanorods obtained by the arc discharge method show excellent performance and promise for applications in both UV and humidity sensors.

  17. Systematic characterization of HT PEMFCs containing PBI/H{sub 3}PO{sub 4} systems. Thermodynamic analysis and experimental investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bandlamudi, George Chakravarthy

    2011-07-01

    High temperature PEMFCs (HT PEMFCs), operating at 120 C - 200 C are rather new and offer tremendous advantages. For instance fuel cells operating at > 100 C reduce issues related to water management substantially. Circulating excess heat energy from such fuel cells into other system processes where heat is needed would be much more practical (due to higher {delta}T) compared to the standard LT PEMFCs where the produced heat has less than 90 C (lower {delta}T). Higher tolerance to fuel impurities such as CO, by these HT PEMFCs has made them very practical for many applications. Although PBI/H{sub 3}PO{sub 4} based membranes have been explored for use in PEMFCs from the early 1990s, only recently PEMEAS (currently BASF) has marketed them as commercially available MEAs. Besides, some companies such as Sartorius (currently Elcomax) and Fuma Tech of Germany, Danish Power Systems of Denmark are offering HT-MEAs on a commercial basis. Although some issues remain, such as development of durable and low cost catalyst and catalyst support materials, acid management, the rapid development of membranes and MEAs has been motivated by a huge demand from many a market. Recently, DLR in Germany has tested its pilot airplane (Antares) fully operated with a HT PEMFC stack (with on-board H{sub 2} bottle). ClearEdge Power in Portland, USA has been developing systems based on HT PEMFC technology to be deployed in the US as well as in South Korean households. Many more companies are increasingly interested in this technology due to the many fold advantages it has to offer. This work is aimed at elucidating this HT PEMFC technology, in terms of giving an in-depth view of what it means to operate a HT PEMFC. (orig.)

  18. The Role of Exponential and PCTR Experiments at Hanford in the Design of Large Power Reactors; Roles Respectifs des Experiences Exponentielles et du Reacteur d'Etude des Constantes Physiques de Hanford dans les Etudes de Grands Reacteurs de Puissance; Znachenie ehksponentsial'nykh opytov i opytov na reaktore PCTR pri proektirovanii bol'shikh ehnergeticheskikh reaktorov v khehnforde; Papel de los Experimentos Exponenciales y del Reactor PCTR de Hanford en el Proyecto de Grandes Reactores de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Heineman, R. E. [General Electric Company, Richland, WA (United States)

    1964-02-15

    introduccion de cambios en el manejo de los reactores ya existentes, como instrumentos de investigacion en la esfera de la fisica de los reactores y como medio de ensenanza. Compara tambien los capitales invertidos en esas instalaciones y los gastos de explotacion. Describe el perfeccionamiento de nuevas tecnicas experimentales que estas instalaciones permiten aplicar con miras a satisfacer la demanda de nuevos datos experimentales. Es menester tener presentes todos estos datos para poder predecir la evolucion de las necesidades y las tendencias futuras en el empleo de estas instalaciones para los estudios de los reactores de potencia. La memoria describe sucintamente el reactor para el estudio de constantes fisicas e indica la manera en que se piensa utilizarlo en el marco de esa evolucion. (author) [Russian] V Hjen- fordskih laboratorijah v techenie pochti 15 let provodjatsja jeksponencial'nye reaktornye iz- merenija na grafito-uranovyh reshetkah. Hotja rezul'taty jetih opytov ispol'zovalis' dlja opredelenija laplasianov predlagaemyh proizvodjashhih reaktorov, oni takzhe sodejstvovali razvitiju ponimanija fiziki reaktorov jetih sistem. Davno priznano, chto poleznost' kri- ticheskogo opyta ogranichena vvidu ego bol'shogo masshtaba i nedostatochnoj chuvstvitel'nosti v otnoshenii nebol'shih lokalizovannyh narushenij sistemy. Zatem mysl' byla napravlena na sozdanie cel'nogo opytnogo reaktora, v kotorom bylo by svedeno do minimuma kolichest- vo materialov, neobhodimyh dlja poluchenija nuzhnyh dannyh. Jeta popytka privela k postrojke usovershenstvovannoj kriticheskoj ustanovki s neskol'kimi zonami reaktora dlja izmerenija fizicheskih konstant PCTR. Ustanovka ispol'zuetsja dlja okazanija sodejstvija pri razrabot- ke proekta po fizike reaktorov dlja neskol'kih jenergeticheskih reaktorov. Krome togo,re- aktor RSTNjavljaetsja ustanovkoj obshhego naznachenija dlja provedenija izmerenij poperechnyh sechenij na reaktore i dlja opredelenija differencial'nyh i integral'nyh fizicheskih para

  19. RB Research nuclear reactor, Annual report for 1994, I - III; Istrazivacki nuklearni reaktor RB, Izvestaj o radu u 1994. godini, I - III

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, D; Milosevic, M; Pesic, M [Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia); Marinkovic, P [Elektrotehnicki fakultet, beograd (Yugoslavia); Kocic, A; Ilic, R; Dasic, N; Ljubenov, V; Petronijevic, M; Jevremovic, M [Institute of Nuclear Sciences Vinca, Belgrade (Serbia)

    1994-12-15

    Report on RB reactor operation during 1994 contains 3 parts. Part one contains a brief description of the reactor, reactor operation and operational capabilities, reactor components, relevant dosimetry and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization as well as operation of the VAX-8250 computer.

  20. RB research nuclear reactor, Annual report for 1989, I - III; Istrazivacki nukleani reaktor RB (Izvestaj o radu u 1989. godini), I - III

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, D; Pesic, M; Hadimahmutovic, N; Vranic, S; Petronijevic, M; Jevremovic, M; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1989-12-15

    This report is made of three parts. Part one contains a short description of the reactor, reactor operation, incidents, status of reactor equipment and components (nuclear fuel, heavy water, reactor vessel, heavy water circulation system, electronic, electric and mechanical equipment, auxiliary systems and Vax-8250 computer). It includes dosimetry and radiation protection data, personnel and financial data. Second part of this report in concerned with maintenance of reactor components and instrumentation. Part three includes data about reactor utilization during 1989.

  1. RB Research nuclear reactor, Annual report for 1995, I-IV; Istrazivacki nuklearni reaktor RB, Izvestaj o radu u 1995. godini, I-IV

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovic, D; Milosevic, M; Pesic, M [Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia); Marinkovic, P [Elektrotehnicki fakultet, Beograd (Yugoslavia); Ilic, R; Dasic, N; Milovanovic, S; Ljubenov, V; Petronijevic, M; Jevremovic, M [Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1995-12-15

    Report on RB reactor operation during 1995 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor.

  2. RB research nuclear reactor, Annual report for 1984, I - III; Istrazivacki nuklearni reaktor RB, Izvestaj o radu u 1984. godini, I - III

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Zivkovic, B; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1984-07-01

    The annual report for 1984 contains 3 parts. Part one includes the following: description of the reactor, exploitation possibilities of the reactor, reactor operation, accident and incidents analysis; reactor equipment and components; dosimetry and radiation protection; RB reactor staff and financial data. Part two of this report is devoted to maintenance and control of reactor components, electronic and electric equipment as well as auxiliary systems. Part three describes reactor exploitation; development of experimental methods; utilization of the reactor as a radiation source.

  3. RB research nuclear reactor - Annual report for 1986, I - III; Istrazivacki nuklearni reaktor RB (Izvestaj o radu u 1986. godini), I-III

    Energy Technology Data Exchange (ETDEWEB)

    Markovic, H; Pesic, M; Vranic, S; Petronijevic, M; Jevremovic, M; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1987-07-01

    This report includes data concerning the RB reactor operation in 1986, state of the reactor components, data about the employed personnel and the database of experimental and other reactor related devices. It is made of 3 parts: Engineering description and operation of the RB reactor including dosimetry, reactor staff data and financial report; Reactor facility components and maintenance; RB reactor operation and utilization in 1986. Izvestaj pokazuje podatke o radu reaktora RB u toku 1986. godine, stanje reaktorske opreme, podatke o angazovanom osoblju na reaktoru i datoteku sa podacima o eksperimentalnoj i drugoj opremi reaktora RB. Sastoji se od 3 dela: tehnicki opis, pogon i rad reaktora, oprema postrojenja i njeno odrzavanje, koriscenje reaktora u 1986. godini.

  4. Formulation and pharmacokinetic evaluation of a paclitaxel nanosuspension for intravenous delivery

    Directory of Open Access Journals (Sweden)

    Wang YL

    2011-07-01

    Full Text Available Yonglu Wang1,4, Xueming Li1,2*, Liyao Wang3, Yuanlong Xu1, Xiaodan Cheng1, Ping Wei41College of Pharmacy, Nanjing University of Technology, Nanjing; 2State Key Laboratory of Materials-Oriented Chemical Engineering, Nanjing University of Technology, Nanjing; 3College of Life Science, Anhui Agricultural University, Hefei; 4College of Biotechnology and Pharmaceutical Engineering, Nanjing University of Technology, Nanjing, People’s Republic of China *These authors contributed equally to this work.Abstract: Paclitaxel is a diterpenoid isolated from Taxus brevifolia. It is effective for various cancers, especially ovarian and breast cancer. Due to its aqueous insolubility, it is administered dissolved in ethanol and Cremophor® EL (BASF, Ludwigshafen, Germany, which can cause serious allergic reactions. In order to eliminate Cremophor EL, paclitaxel was formulated as a nanosuspension by high-pressure homogenization. The nanosuspension was lyophilized to obtain the dry paclitaxel nanoparticles (average size, 214.4 ± 15.03 nm, which enhanced both the physical and chemical stability of paclitaxel nanoparticles. Paclitaxel dissolution was also enhanced by the nanosuspension. Differential scanning calorimetry showed that the crystallinity of paclitaxel was preserved during the high-pressure homogenization process. The pharmacokinetics and tissue distribution of paclitaxel were compared after intravenous administration of paclitaxel nanosuspension and paclitaxel injection. In rat plasma, paclitaxel nanosuspension exhibited a significantly (P < 0.01 reduced area under the concentration curve (AUC0–∞ (20.343 ± 9.119 µg · h · mL−1 vs 5.196 ± 1.426 µg · h · mL−1, greater clearance (2.050 ± 0.616 L · kg−1 · h−1 vs 0.556 ± 0.190 L · kg−1 · h−1, and shorter elimination half-life (5.646 ± 2.941 vs 3.774 ± 1.352 hours compared with the paclitaxel solution. In contrast, the paclitaxel nanosuspension resulted in a

  5. Surfaktan Sodium Ligno Sulfonat (SLS dari Debu Sabut Kelapa

    Directory of Open Access Journals (Sweden)

    Mukti Mulyawan

    2015-03-01

    Full Text Available Indonesia merupakan negara agraris yang menghasilkan beragam hasil pertanian yang melimpah. Salah satu hasil pertanian yang menonjol di Indonesia adalah kelapa. Produksi buah kelapa di Indonesia rata-rata sebanyak 15,5 miliar butir/tahun atau setara dengan 3,02 juta ton kopra, 3,75 juta ton air, 0,75 juta ton arang tempurung, 1,8 juta ton serat sabut (coir fiber dan 3,3 juta ton debu sabut (coir dust/ cocopeat. Komposisi sabut kelapa terdiri dari 25% gabus dan 75% serat . Tetapi, debu sabut kelapa masih dikembangkan sebatas sebagai media tanam. sisanya akan menjadi limbah dengan kontribusi sangat besar dari pengisi pada volume total sampah domestiK. Banyaknya komoditas kelapa dan potensi limbah sabut yang dihasilkan, membuat pemanfaatan Debu Sabut menjadi bahan yang bernilai ekonomis patut untuk dilakukan. Salah satunya adalah sebagai bahan pembuatan Surfakatan Sodium Ligno Sulfonat (SLS yang selama ini komoditasnya diperoleh seluruhnya dari impor. Adapun tahapan proses pembuatan SLS dari Debu Sabut kelapa adalah mempersiapan Bahan Baku berupa Debu Sabut Kelapa. Dilanjutkan dengan pemasakan/pulping menggunakan metode organosolv dengan alat pemasak digester (R-120. Dari lindi hitam yang dihasilkan, akan diproses dengan Isolasi Lignin dengan metode presipitasi asam. Lindi hitam yang telah didapat diendapkan dengan menambahkan secara perlahan H2SO4dengan konsentrasi 20% sampai pH 2 pada tangki isolasi pertama (M-211.Proses isolasi dengan metode pengasaman banyak digunakan untuk mendapatkan lignin dengan kemurnian tinggi. Untuk Menghasilkan SLS, Lignin Isolat perlu direaksikan dengan bahan penyulfonasi natrium bisulfit (NaHSO3, sehingga menghasilkan natrium lignosulfonat (SLS pada reaktor sulfonasi (R-310. Berlokasi di Provinsi Riau, Pabrik ini akan dibangun dengan kapasistas 20.150 ton/tahun. Dari analisa ekonomi, diperlukan Modal tetap (FCI sebesar Rp 316.323.349.677; Modal kerja (WCI sebesar Rp 74.429.023.453; Investasi total (TCI sebesar Rp 390

  6. Investigation of mass transfer phenomena in biofilm systems; Untersuchung von Stoffuebergangsphaenomenen in Biofilmsystemen

    Energy Technology Data Exchange (ETDEWEB)

    Waesche, S.; Hempel, D.C. [Technische Univ. Braunschweig (Germany). Inst. fuer Bioverfahrenstechnik; Horn, H. [Fachhochschule Magdeburg (Germany). Hydro- und Abfallchemie

    1999-07-01

    Substance transfer in the boundary layer bulk/biofilm can be only inadequately described by conventional model concepts. In such cases where the surface structure of a biofilm adapts to given hydraulic conditions, the substance transfer phenomena need to be studied in depth. In addition, the entire biofilm structure is much influenced both by substrate conditions and by hydrodynamic conditions during growth. With a view to quantifying these factors, biofilms were cultured under various substrate and hydrodynamic conditions in tube reactors with a diameter of 2.6 cm. For characterizing the cultured biofilms, biofilm density and substrate turnover measured as maximum mass transfer density were determined in each test series. Biofilm density (dry biomass/biofilm volume) was determined by gravimetry. Maximum mass transfer densities in biofilm were established in batch experiments with excess substrate. By means of oxygen microelectrodes, oxygen profiles in the biofilm were measured directly in the reactor. These measurements concerned biofilms of thicknesses ranging from 400 to 2000 {mu}m, where the biofilms did not yet exhibit erosion. (orig.) [German] Der Stoffuebergang in der Grenzschicht Bulk/Biofilm ist mit herkoemmlichen Modellvorstellungen nur ungenuegend beschreibbar. Eine sich an die aktuellen hydraulischen Bedingungen anpassende Oberflaechenstruktur des Biofilms erfordert eine intensive Untersuchung der Stoffuebergangsphaenomene in derartigen Systemen. Darueber hinaus wird die gesamte Biofilmstruktur sowohl von den Substratbedingungen als auch von den hydrodynamischen Bedingungen waehrend des Wachstums stark beeinflusst. Um diese Faktoren quantifizieren zu koennen, wurden Biofilme bei verschiedenen Substrat- und hydrodynamischen Bedingungen in Rohrreaktoren mit einem Durchmesser von 2,6 cm kultiviert. Zur Charakterisierung der kultivierten Biofilme wurde die Biofilmdichte und der Substratumsatz, gemessen als maximale Massestromdichte, bei jeder Versuchsreihe

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-12-15

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

  8. PIROLISIS LIGNIN DARI LIMBAH INDUSTRI KELAPA SAWIT UNTUK PENGEMBANGAN SURFAKTAN DALAM PROSES ENHANCE OIL RECOVERY (EOR (Pyrolysis of Lignin From Waste of Palm Oil Industries for The Development of Surfactants for Enhance Oil Recovery (EOR

    Directory of Open Access Journals (Sweden)

    Suryo Purwono

    2001-12-01

    Full Text Available ABSTRAK Pirolisis dari lignin yang berasal dari limbah industri kelapa sawit dapat menghasilkan alkohol dan derivatif lainnyd yang dapat digunakan sehagai surfaktan. Prosedur penelitian proses pirolisis ini odalah sebagai berikut: I serabut atau tandan sisa pengolahon kelapa sawit yang sudah dikeringkan dimasukkan kedalam reaktor dengan berat tertentu dan dipanaskan sampai suhu yang diinginkan, 2 produk pirolisis yang keluar dari reoktor kemudian didinginkan sampoi mencapai suhu kamor, 3 hasil cair ditampung didalam gelas ukur dan hasil gasnya ditampung di suatu botol tertentu. Suhu paling baik yang dicapai adalah 4A0 "C untuk lignin yong berasal dari serabut dan 350'C untuk lignin yang berasal dari tandan kelapa sawit. Surfaktan yang dihasilkan sekitar j4 sampai 38% dari produk pirolisis. Pada penelitian ini kecepatan reaksi dianggap order satu. Hasil penelitian menunjukkan bahwa surfakton yang dihasilkan dapat membentuk emulsi dengan minyak menta.h. Hal ini menunjukkon bahwa surfaktan yang dihasilkan dapat digunakan sebagai bahan untuk proses EOR.   ABSTRACT Pyrolysis of lignin from waste of palm oil industries produces alcohol and its derivatives which can be sulfonated to become surfactant. The experimental procedures for the pyrolysis process were as follows: 1 dried palm oil husks at a certain weight were put into the pyrolysis reactor and heated up to a certain temperafure; 2 the product leaving the reactor was cooled down to room temperature; and 3 the liquid product was collected in a flask while the gas product was put into a big bottle. The best temperature obtained for producing liquid product was 400 oC for lignin from palm oil fruit fibers and 350 oC for lignin from palm oil fruit stems. The surfactant developed was in the range between 34 and 38% from the pyrolysis product. In this experiment, the reaction rate was assumed to be in first order. The result showed that the surfactant obtained from the experiment could form emulsion

  9. The Threshold of Toxicological Concern for prenatal developmental toxicity in rats and rabbits

    Science.gov (United States)

    van Ravenzwaay, B.; Jiang, X.; Luechtefeld, T.; Hartung, T.

    2018-01-01

    The Threshold Toxicological Concern (TTC) is based on the concept that in absence of experimental data reasonable assurance of safety can be given if exposure is sufficiently low. Using the REACH database the low 5th percentile of the NO(A)EL distribution, for prenatal developmental toxicity (OECD guideline 414) was determined. For rats, (434 NO(A)ELs values) for maternal toxicity, this value was 10 mg/kg-bw/day. For developmental toxicity (469 NO(A)ELs): 13 mg/kg-bw/day. For rabbits, (100 NO(A)ELs), the value for maternal toxicity was 4 mg/kg-bw/day, for developmental toxicity, (112 NO(A)EL values): 10 mg/kg-bw/day. The maternal organism may thus be slightly more sensitive than the fetus. Combining REACH- (industrial chemicals) and published BASF-data (mostly agrochemicals), 537 unique compounds with NO(A)EL values for developmental toxicity in rats and 150 in rabbits were evaluated. The low 5th percentile NO(A)EL for developmental toxicity in rats was 10 mg/kg-bw/day and 9.5 mg/kg-bw/day for rabbits. Using an assessment factor of 100, a TTC value for developmental toxicity of 100 µg/kg-bw/day for rats and 95 µg/kg-bw/day for rabbits is calculated. These values could serve as guidance whether or not to perform an animal experiment, if exposure is sufficiently low. In emergency situations this value may be useful for a first tier risk assessment. PMID:28645885

  10. Tumor necrosis factor-alpha release from rat pulmonary leukocytes exposed to ultrafine cobalt: in vivo and in vitro studies

    International Nuclear Information System (INIS)

    Zhang Qunwei; Kusaka, Yukinori; Sato, Kazuhiro; Wang Deweng; Donaldson, Kenneth

    1999-01-01

    Ultrafine cobalt (Uf-Co), one of the new category of ultrafine particles, is generated in some industrial situations and it also exists in environmental particles. The aim of this study was to investigate the ability of rat pulmonary leukocytes to release tumor necrosis factor alpha (TNF-alpha) after exposure to Uf-Co in vivo and in vitro. Rats were intratracheally instilled with 1 mg of Uf-Co, and then wet lung weight and bronchoalveolar lavage fluid (BASF) profile were analysed 1, 3, 7, 15, and 30 days later. The effects of Uf-Co on indices that can be presumed to reflect epithelial injury and permeability (lactate dehydrogenase (LDH) and total protein (TP)) were increased throughout the 30 day post-exposure period. Furthermore, at 3 days after exposure, leukocytes were collected by bronchoalveolar lavage (BAL). After 3, 6, 12, 24, 48, and 72 hours of incubation, TNF-alpha in supernatants were determined by ELISA method. The results showed that TNF-alpha secretion by activated leukocytes from rats instilled with Uf-Co was significantly higher than that of the controls. BAL leucocytes from the lung of exposed rats revealed time-and dose-related increases in TNF-alpha release. In conclusion, our results reveal, for the first time to our knowledge, that exposure to Uf-Co can stimulate leukocytes to secrete TNF-alpha. These data suggest that the TNF-alpha release from pulmonary leukocytes probably plays a role in the pathogenesis of 'cobalt lung'. (author)

  11. Thin Spray-on Liner - a potential application. Demonstrated at a longwall installation on Dendrobium mine

    Energy Technology Data Exchange (ETDEWEB)

    Byrnes, Roger [BHP Billiton, NSW (Australia). Dendrobium Mine; Martin, Philip [BASF AG Australia (Australia). BASF-CC Australia Ltd' s

    2008-08-21

    The paper describes a potential application of a Thin Spray-on Liner, on a longwall installation in Australia. The BHPBilliton mine, Dendrobium, is a relatively new mine in the Southern New South Wales coalfields, near to Wollongong. Normal installation and start-up operations for a new longwall face is to completely rock bolt and mesh the face. The operations use plastic/glassfibre cutable rock bolts, with steel/plastic mesh to prevent spalling. The biggest problem on face start up is the sheets of steel or plastic mesh getting wrapped around the shearer disc, which requires time consuming additional work removing the mesh. BASF Construction Chemicals Australia Pty Ltd's Underground Construction group, (UGC), proposed the use of Masterseal 845A, a fast sprayable cementitious/polymer membrane material that could be trialed and used to replace the steel mesh, as a surface support in unison with the conventional cutable rock bolts. The application took 12 h spraying to cover the 240 m long face line which averaged about 3.3 m high. The product was sprayed between 3.5 m to 4 mm thick, and according to the mine operators was at least three times quicker than mesh installation, not withstanding the savings in transport of the awkward bundles of mesh. In conclusion the Thin Spray-on Liner (TSL) performed adequately and achieved it's objective in this installation at Dendrobium mine. (orig.)

  12. Research Project 'RB research nuclear reactor' (operation and maintenance), Final report; Naucnoistrazivacki projekt 'Istrazivacki nuclearni reaktor RB, (pogon i odrzavanje), Zavrsni elaborat projekta

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-07-01

    This final report covers operation and maintenance activities at the RB reactor during period from 1981-1985. First part covers the RB reactor operation, detailed description of reactor components, fuel, heavy water, reactor vessel, cooling system, equipment and instrumentation, auxiliary systems. It contains data concerned with dosimetry and radiation protection, reactor staff, and financial data. Second part deals maintenance, regular control and testing of reactor equipment and instrumentation. Third part is devoted to basic experimental options and utilization of the RB reactor including training.

  13. Control of a reactor for conditioning of biogenic waste materials. Final report; Steuerung eines Reaktors zur Aufbereitung von Abfaellen mit biogenen Bestandteilen. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Bartha, B.; Brummack, J.; Kloeden, W.

    2002-10-01

    Mechanical-biological waste treatment implies biological drying and mechanical separation; it produces a pollutant-free fuel fraction with good calorific value and inorganic fractions available for recycling. Apart from some prototypes, mostly static aerobic reactors are used. For moist residues, dynamic reactors may be interesting as they permit coupling of thermal and mechanical processes, i.e. parallel biological drying and mechanical separation. A discontinuous rotary kiln reactor for biological drying of residues was developed in this project. (orig.) [German] Die mechanisch-biologische Aufbereitung von Restabfaellen (MBA) hat sich zu einem Systembaustein innerhalb der Restabfallentsorgung entwickelt. Das Hauptanwendungsziel besteht darin, durch die Kombination von biologischer Trocknung mit mechanischen Stofftrennverfahren eine heizwertreiche und schadstoffentfrachtete Fraktion mit Brennstoffeigenschaften, sowie verwertbare anorganische Fraktionen aus dem Restabfall zu gewinnen. Die Ausgangssituation zeigte, dass, abgesehen von einigen prototypischen Anlagen, in der MBA-Technologie hauptsaechlich statische, aerob arbeitende Reaktoren (Rottetunnel und Rotteboxen) fuer den biologischen Schritt eingesetzt werden. Fuer feuchte Restabfaelle erscheint es interessant, dynamische Reaktoren einzusetzen, die die Kopplung thermischer und mechanischer Prozesse erlauben, die also die biologische Trocknung und den mechanischen Aufschluss parallel zulassen. Im Rahmen des Projektes wurde die Steuerung eines diskontinuierlich betriebenen Drehrohrreaktors zur biologischen Trocknung von Restabfaellen entwickelt. (orig.)

  14. The Siemens-Argonaut reactor as a driver zone for a high-temperature reactor cell. Der Siemens-Argonaut-Reaktor als Treiberzone fuer eine Hochtemperaturreaktorzelle

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, H; Schuerrer, F; Ninaus, W; Oswald, K; Rabitsch, H; Kreiner, H [Technische Univ., Graz (Austria). Inst. fuer Theoretische Physik und Reaktorphysik; Neef, R D [Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung

    1984-12-15

    To enable a validation of neutron physics calculation methods for pebble bed reactors the inner reflector of an Argonaut research reactor was substituted by a full of about 1200 fuel elements of the AVR-Juelich type. The report describes the measuring instruments and the reactor physical layout of the arrangement by the code packages GAMTEREX, ZUT-D.G.L. and MUPO. Comparison of calculated reaction rates with measurements show good agreement. Application of the codes to high-temperature reactors in abnormal states is envisaged. (Author, translated by G.Q.)

  15. Hydrogen Mixing Studies (HMS) assessment manual

    International Nuclear Information System (INIS)

    Lam, K.L.; Wilson, T.L.; Travis, J.R.

    1993-06-01

    This report documents some calculations performed to assess the Hydrogen Mixing Studies (HMS) code. Results are presented first for some analytical test problems, including laminar flow and mass diffusion. The von Karman vortex street problem and the Sandia FLAME Facility and Heiss Dampf Reaktor (HDR) containment facility test problems are then discussed. For the analytical problems, the code gave results that agree exceptionally well with the analytical solutions. Calculations for the von Karman vortex street problem were performed at selected Reynolds numbers for several obstacle types. The computed flow patterns agree well with experimental observations-specifically the occurrence of a vortex street (double row of vortices) above a critical Reynolds number. Calculations for the von Karman vortex street problem were performed at selected Reynolds numbers for several obstacle types. The computed flow patterns agree well with experimental observations-specifically the occurrence of a vortex street (double row of vortices) above a critical Reynolds number. The last assessment problem involves modeling the experiment T31.5. The experiment was carried out in the HDR containment building, which is a large, multi-compartment facility (11 300 m 3 free volume in 72 compartments). In the experiment, a steam-water mixture was first injected into the containment to simulate a large-break blowdown of a pressure vessel, and then superheated steam was injected that was followed by a release of helium-hydrogen light gas. The calculated results (pressure, temperature, and gas concentrations) agree reasonably well with the experimental data

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-12-15

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

  17. The evolution of the break preclusion concept for nuclear power plants in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit, Koeln (Germany)

    1997-04-01

    In the updating of the Guidelines for PWR`s of the {open_quotes}Reaktor-Sicherheitskommission{close_quotes} (RSK) in 1981 the requirements on the design have been changed with respect to the postulated leaks and breaks in the primary pressure boundary. The major change was a revision in the requirements for pipe whip protection. As a logical consequence of the {open_quotes}concept of basic safety{close_quotes} a guillotine type break or any other break type resulting in a large opening is not postulated any longer for the calculation of reaction and jet forces. As an upper limit for a leak an area of 0, 1 A (A = open cross section of the pipe) is postulated. This decision was based on a general assessment of the present PWR system design in Germany. Since then a number of piping systems have been requalified in the older nuclear power plants to comply with the break preclusion concept. Also a number of extensions of the concept have been developed to cover also leak-assumptions for branch pipes. Furthermore due considerations have been given to other aspects which could contribute to a leak development in the primary circuit, like vessel penetrations, manhole covers, flanges, etc. Now the break preclusion concept originally applied to the main piping has been developed into an integrated concept for the whole pressure boundary within the containment and will be applied also in the periodic safety review of present nuclear power plants.

  18. Pengaruh Kecepatan Homegenisasi Terhadap Sifat Fisika dan Kimia Krim Nanopartikel dengan Metode High Speed Homogenization (HSH

    Directory of Open Access Journals (Sweden)

    Galuh Suprobo

    2015-06-01

    Full Text Available Nanoparticle cream is the development of nanotechnology in cosmetics fields for improving the function of cream. High speed homogenization (HSH is one of the methods for creating nanoparticle cream. In this research, the use of natural materials based palm oil derivative  such as stearic acid, cetil alcohol, cetil stearil alcohol was chosen in nanoparticle cream producing by using HSH methods.The speed variable of  homogenization of 1000 rpm, 1500 rpm, 2,000 rpm and 2,500 rpm  intended to find out the influence of speed toward the  properties of cream product. The observation result showed the influence on physical display in term of texture but not in homogeneity , stability and cream color. The pH of the product during two months storage for all variables were still stable. The particle size was increased in the homogeneity of speed at 2000 rpm and 2500 rpm. In this research has produced the cream in particle size from 239.86 to 358.10 nm which enter in nanoparticle category 50 nm to 1000 nm. The stability of nanoparticle cream product in the range of 97,20 to 98%.ABSTRAKKrim nanopartikel merupakan pengembangan nanoteknologi di bidang kosmetik untuk meningkatkan fungsi krim tersebut. High speed homogenization (HSH merupakan salah satu metoda dalam pembuatan krim nanopartikel. Pada penelitian ini, krim nanopartikel dibuat menggunakan bahan baku alami turunan kelapa sawit yaitu asam stearat, setil alkohol, setil stearil alkohol dengan metoda HSH. Variabel kecepatan homogenisasi pada 1000 rpm, 1500 rpm, 2000 rpm dan 2500 rpm dimaksudkan untuk mengetahui pengaruh kecepatan terhadap sifat-sifat krim. Hasil menunjukkan bahwa perubahan kecepatan homogenisasi dalam reaktor berpengaruh terhadap tampilan fisik dari segi tekstur, akan tetapi tidak mempengaruhi terhadap kehomogenan, stabilitas dan warna krim. Dari pengamatan selama 2 bulan penyimpanan diketahui tidak terjadi perubahan pH selama penyimpanan untuk keempat variabel. Ukuran partikel

  19. Hydrogen selective membrane for the natural gas system. Development of CO{sub 2}-selective biogas membrane. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Vestboe, A.P.

    2012-02-15

    the goal to develop membrane materials that are suitable for the removal of CO{sub 2}. Emphasis was put on selecting materials that are commercially available and that can be easily processed into membranes in a large scale. Membrane modules were produced from many capillary tubes of the membranes in order to achieve a system for removing CO{sub 2} in a larger scale. A certain technology was developed in which the membrane material was improved upon by adding certain nanoporous particles called zeolites. A choice was made in thermoplastic polyurethane, and a supplier was found in BASF. This is a rather cheap material and a certain grade of their products was found to offer a reasonable high selectivity of 16 while couple with a high permeability. A zeolite was selected in Linde Type 4A, which has pores that are on the molecular size exactly between CO{sub 2} and CH{sub 4}. By adding these particles, a molecular sieving effect was obtained. It was found that the selectivity was increased by 50% and the permeability of the finished material was 24 Barrer, which is a rather high number when coupled with this selectivity. A success was achieved in the development of a technology in which zeolite articles could be blended with a large range of polymers in such a way that there were no voids around the zeolite particles, but a tight adhesive was obtained. This made it possible to not lose selectivity due to bypassing of gaseous molecules around the zeolite particles. It was found that this technology could be passed over from a small laboratory scale compounder to a large scale compounder-extruder. In going from small-scale membranes used for laboratory testing to industry sized membrane modules a number of designs were considered. A design which consisted of large bundles of capillary tubes were found to be the best suitable solution and was used in the further development. These capillary tubes were made in such a way, that there was a strong carrier tube of a highly

  20. Surface modifications of silica nanoparticles are crucial for their inert versus proinflammatory and immunomodulatory properties

    Directory of Open Access Journals (Sweden)

    Marzaioli V

    2014-06-01

    Full Text Available Viviana Marzaioli,1 Juan Antonio Aguilar-Pimente,1,2 Ingrid Weichenmeier,1 Georg Luxenhofer,3 Martin Wiemann,4 Robert Landsiedel,5 Wendel Wohlleben,5 Stefanie Eiden,6 Martin Mempel,7 Heidrun Behrendt,1 Carsten Schmidt-Weber,1 Jan Gutermuth,1,8 Francesca Alessandrini1 1Center of Allergy and Environment (ZAUM, Technische Universität and Helmholtz Zentrum München, Member of the German Center for Lung Research (DZL, Munich, Germany; 2Department of Dermatology and Allergy Biederstein, Technische Universität München (TUM and German Mouse Clinic, Helmholtz Zentrum München, German Research Center for Environmental Health, Munich-Neuherberg, Germany, 3Institute of Developmental Genetics, Helmholtz Zentrum München, Neuherberg, Germany; 4IBE R&D gGmbH, Münster, Germany; 5BASF, Ludwigshafen, Germany; 6Bayer Technology Services, Leverkusen, Germany; 7Department of Dermatology, Venereology and Allergology, Universitätsmedizin Göttingen (UMG, Göttingen, Germany; 8Department of Dermatology, Vrije Universiteit Brussel, Brussels, Belgium Background: Silica (SiO2 nanoparticles (NPs are widely used in diverse industrial and biomedical applications. Their applicability depends on surface modifications, which can limit potential health problems. Objective: To assess the potential impact of SiO2 NP exposure and NPs chemical modifications in allergic airway inflammation. Methods: Mice were sensitized by five repetitive intraperitoneal injections of ovalbumin/aluminum hydroxide (1 µg over 42 days, then intratracheally instilled with plain or modified SiO2 NPs (50 µg/mouse, and subsequently aerosol challenged for 20 minutes with ovalbumin. One or 5 days later, allergic inflammation was evaluated by cell differentiation of bronchoalveolar lavage fluid, lung function and gene expression and histopathology, as well as electron and confocal microscopy of pulmonary tissue. Results: Plain SiO2 NPs induced proinflammatory and immunomodulatory effects in vivo

  1. Estabelecimento e multiplicação in vitro de brotos no processo de micropropagação de cultivares de bananeira (Musa spp. Establishment and in vitro multiplication of banana (Musa spp. cultivars with the use of PVP (Polyvinylpyrrolidone

    Directory of Open Access Journals (Sweden)

    Hérica Santos de Oliveira

    2011-01-01

    Full Text Available A banana (Musa spp. é uma das frutas mais consumidas no mundo, e amplamente cultivada no Brasil, porém doenças como as sigatokas, negra e amarela, vêm reduzindo a sua produção. A disponibilização imediata de novas cultivares resistentes às principais doenças é limitada pela propagação convencional. A micropropagação é uma alternativa para a produção de mudas com qualidade fitossanitária e vegetativa, mas apresenta fatores que dificultam sua aplicação como a contaminação por fungos e bactérias, associada à oxidação dos explantes. O objetivo desse trabalho foi adaptar e/ou otimizar as etapas do processo de micropropagação para diferentes cultivares de bananeira, por meio do controle de oxidação, contaminação, e multiplicação de brotos, sendo utilizadas as cultivares Caipira (AAA, BRS Caprichosa (AAAB, Pacovan Ken (AAAB, Preciosa (AAAB, PV 03-76 (AAAB, Thap Maeo (AAB. No estudo foram utilizados o antibiótico sulfato de estreptomicina e o fungicida Opera® (BASF visando reduzir a contaminação in vitro provocada por bactérias e fungos, além do anti-oxidante PVP (polivinilpirrolidona para controlar a oxidação. Houve redução da contaminação com uso do sulfato de estreptomicina à concentração de 100 mg L-1 e da oxidação com PVP a 4 g L-1. Na fase de multiplicação de brotos, as cultivares apresentaram médias que variaram de 1,90 a 4,75 brotos/explante. A cultivar caipira (AAA destacou-se das demais com a maior taxa de multiplicação de brotos após três subcultivos, média de 41,50 brotos por rizoma.The banana (Musa spp is one of the most consumed fruits in the world and is widely consumed in Brazil, but diseases such as yellow and black sigatoka have been reducing its production. The immediate availability of new cultivars resistant to major diseases is limited by conventional propagation. The micropropagation, is an alternative for the production of seedlings with phytosanitarium and vegetative

  2. Report on the interpretation of critical experiments in the Siemens-Argonaut-Reactor Graz to study water ingress into spherical elements. Ergebnisbericht zur Auslegung kritischer Experimente am Siemens-Argonaut-Reaktor Graz zum Studium des Wassereinbruches im Kugelhaufen

    Energy Technology Data Exchange (ETDEWEB)

    Schuerrer, F [Technische Univ., Graz (Austria). Inst. fuer Theoretische Physik und Reaktorphysik; Neef, R D [Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung

    1979-04-15

    The experiments described are of interest in the study of water contamination in HTR fuel elements. The Siemens Argonaut Reactor (SAR) has been considered as a research tool for a simulation experiment. Following a brief description of the SAR, planned programs are discussed in 'dry' and 'wet' cores. Detector foil types and locations are noted. A theoretical model is developed and nuclide concentrations estimated in the various spectral zones. Reactivity calculations have been made and are summarised for various H{sub 2}O percentage concentrations. The discussion is supported by simplified core layout diagrams and graphs of core flux distributions. Neutron diffusion and spectra calculations are referenced to computer programs used by KFA-Juelich, published elsewhere, and include GAM, THERMOS, MUPO and EXTERMINATOR-2. (G.C.)

  3. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1984; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

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

    1984-12-15

    During the 1984 the reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981. Operation of the primary cooling system was changed in order to avoid appearance of the previously noticed aluminium oxyhydrate on the surface of the fuel element claddings. The new cooling regime enabled more efficient heavy water purification. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks are planned: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. Financing of the planned activities will be partly covered by the IAEA. this Part I of the report includes 8 Annexes describing in detail the reactor operation, and 6 special papers dealing with the problems of reactor operation and utilization.

  4. FRM-II research neutron source commissioned; Eroeffnung der Forschungs-Neutronenquelle Heinz Maier-Leibnitz - FRM-II

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2004-07-01

    . Thomas Goppel (Bayerischer Staatsminister fuer Wissenschaft, Forschung und Kunst), Professor Wolfgang A. Herrmann (Praesident der Technischen Universitaet Muenchen), Hannelore Gabor (2. Buergermeisterin der Standortgemeinde Garching) und Professor Winfried Petry (Wissenschaftlicher Direktor des FRM-II) unterstrichen die grosse Bedeutung des FRM-II fuer Wissenschaft Forschung, Medizin und Technik. Der FRM-II wird nicht nur die 'Neutronenluecke' schliessen, sondern mit einem wesentlich hoeheren Neutronenfluss als beim Vorgaenger-Reaktor, dem legendaeren Atom-Ei, ausserordentlich brillante Arbeitsbedingungen schaffen. International steht nach ersten Konzeptionsansaetzen ab 1980, dem 1. Spatenstich im August 1996 und der Ostern 2003 erteilten 3. Teilgenehmigung ein einmaliges Werkzeug fuer moderne Wissenschaften sowie medizinische und technische Anwendungen zur Verfuegung. (orig.)

  5. A Comparative Study of Personality Traits and Brain Behavioral activation Systems and Inhibition in Women with Cancer, Cardiovascular Diseases and Normal Women

    Directory of Open Access Journals (Sweden)

    Sohrab Amiri

    2017-04-01

    Full Text Available Background and Objectives: Chronic diseases are among the most important causes of mortality. The aim of the current study was to compare the Brain/behavioral systems and Dark personality traits of Machiavellianism, narcissism, and psychopathy in cancer, cardiovascular female patients and normal women. Methods: In this study, 60 individuals were selected using available sampling in three groups of 20 cancer patients, cardiovascular patients, and normal subjects. Finally, in order to test the goals and hypotheses of the research, the participants were studied based on Behavioral Activation System and Behavioral Inhibition System, and Dark Triad traits. Data analysis was performed using multivariate ANOVA, univariate ANOVA and post-hoc tests. Results: In this study, there was a significant difference among the three groups in Brain/behavioral systems and traits of Machiavellianism, narcissism, and psychopathy, so that the cancer and cardiovascular patients had higher score in dark triad traits compared to normal individuals. Also, the cancer patients had a higher score in Machiavellianism trait compared to the cardiovascular patients. In the brain/behavioral systems, cardiovascular and cancer patients had higher score in behavioral inhibition system (BIS component compared to the normal individuals in the of behavioral inhibition system (BIS. Also, in the reward seeking subscale of behavioral activation system (BAS-f, cancer patients had a higher score compared to cardiovascular patients, which was significantly different. Conclusion: The results of this study indicated that cancer and cardiovascular patients, have greater extent of social disgusting personality traits as well as behavioral inhibition system as anxiety-predisposing factor.

  6. Study of the oxygen reduction reaction using Pt-Rare earths (La, Ce, Er) electrocatalysts for application of PEM fuel cells

    International Nuclear Information System (INIS)

    Gomes, Thiago Bueno

    2013-01-01

    The complexity of the oxygen reduction reaction (ORR) and its potential losses make it responsible for the most part of efficiency losses at the Fuel Cells. For this reaction the electrocatalyst witch is most appropriated and shows better performance is platinum, a noble metal that elevates the cost, raising barriers for Fuel Cells technology to enter the market. First this work focuses on reducing the amount of platinum used in the cathode, by being replaced by rare earths. The most common methods of synthesis involves a large amount of steps and this work proposed to prepare the electrocatalyst through a simpler way that would not take so many steps and time to be done. Using an ultrasound mixer the electrocatalyst was prepared mixing platinum supported on carbon black and the rare earths lanthanum, cerium and erbium oxides to be applied in a half-cell study of the ORR. The Koutecky-Levich plots shows that among the electrocatalysts prepared the Pt80Ce20/C had the catalytic activity close to the commercial BASF platinum on carbon black, suggesting that the reaction was taken by the 4-electron path. As found in some works in literature, among the rare earth used to study the ORR, cerium is the one witch shows the better performance because it is able to store and provide oxygen. This feature is of great interest for the ORR because this reaction is first order to the oxygen concentration. Results show that is possible to reduce the amount of platinum maintaining the same electrocatalyst activity. (author)

  7. Study of the oxygen reduction reaction using Pt-Rare earths (La, Ce, Er) electrocatalysts for application of PEM fuel cells; Estudo da reacao de reducao do oxigenio utilizando eletrocatalisadores a base de Pt-terras raras (La, Ce, Er) para aplicacao em celulas a combustivel tipo PEM

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, Thiago Bueno

    2013-07-01

    The complexity of the oxygen reduction reaction (ORR) and its potential losses make it responsible for the most part of efficiency losses at the Fuel Cells. For this reaction the electrocatalyst witch is most appropriated and shows better performance is platinum, a noble metal that elevates the cost, raising barriers for Fuel Cells technology to enter the market. First this work focuses on reducing the amount of platinum used in the cathode, by being replaced by rare earths. The most common methods of synthesis involves a large amount of steps and this work proposed to prepare the electrocatalyst through a simpler way that would not take so many steps and time to be done. Using an ultrasound mixer the electrocatalyst was prepared mixing platinum supported on carbon black and the rare earths lanthanum, cerium and erbium oxides to be applied in a half-cell study of the ORR. The Koutecky-Levich plots shows that among the electrocatalysts prepared the Pt80Ce20/C had the catalytic activity close to the commercial BASF platinum on carbon black, suggesting that the reaction was taken by the 4-electron path. As found in some works in literature, among the rare earth used to study the ORR, cerium is the one witch shows the better performance because it is able to store and provide oxygen. This feature is of great interest for the ORR because this reaction is first order to the oxygen concentration. Results show that is possible to reduce the amount of platinum maintaining the same electrocatalyst activity. (author)

  8. [Diabetes screening and prevention in a large chemical company].

    Science.gov (United States)

    Neumann, S; Webendörfer, S; Lang, S; Germann, C; Oberlinner, C

    2015-05-01

    Diabetes is with 6 million cases in Germany one of the most common and most expensive chronic diseases. Studies presume a high number of unreported cases. Early detection of diabetes with a specific screening method is very important. In Germany family physicians offer a preventive check-up starting at the age of 35 years but only 19% males participate. From this background the BASF department for Occupational Medicine and Health Protection introduced for all 35.000 employees at the headquarter, in Ludwigshafen a general health check focused on the early detection of lifestyle diseases. From April 2011 to June 2013 12.114 employees participated in the general health check offered by the medical department (2.530 women, 9.584 men). All participants filled out a questionnaire named "Findrisk" a scientifically validated questionnaire which focuses on risk factors for diabetes. Furthermore, the blood glucose and the HbA1c of the participants have also been checked in a laboratory test Following the Findrisk criteria the results are: 1.368 employees had an elevated risk of 17%, 854 employees a risk factor of 33% and 131 employees a risk factor of 33%. In 1.533 employees (13,2% of all participants) we diagnosed a prediabetes with an elevated HbA1c-parameter between 5.7 to 6,4%. In 243 employees a manifest diabetes disease with HbA1c of > than 6,5% was diagnosed. We found out that diabetes prevention within the workplace setting is helpful to detect prediabetes and diabetes earlier than family doctors outside the company are able to do.Occupational physicians have the opportunity to inform the employees on risks for lifestyle diseases at an early stage when they are still healthy (primary prevention).For secondary prevention surveillance and clearance examination can be easily combined with screening tests for diabetes. For further diagnostics and therapy the family doctors will be addressed. This system helps individuals to prevent negative health effects, it helps the

  9. Pre-harvest treatments with fungicides and post-harvest dips in sodium bicarbonate to control postharvest decay in stone fruit.

    Science.gov (United States)

    D'Aquino, S; Barberis, A; Satta, D; De Pau, L; Schirra, M

    2012-01-01

    The objective of this study was to evaluate the effectiveness of different commercial formulations of fungicides containing one or more active ingredients in controlling postharvest decay of Thyrinthos and Boccuccia apricots, Red top peaches and Caldesi nectarines. Field treatments consisted of two sprays with cupric compounds, at the end of leaf fall and before bud swelling, one with sulfur compound, at fruit about half final size stage, and one with one of the following commercial formulations at the label suggested rates, one week before harvest: Teldor (fenexamid 50%; Bayer Crop Protection), Folicur (Tebuconazole 4.35%; Bayer Crop Protection), Signum (boscalid 26.7%, pyraclostrobin 6.7%; Basf Crop Protection), Score (difenoconazole 23.23%, Syngenta Crop Protection) and Switch (cyprodinil 37.5%, fludioxonil 25%, Syngenta Crop Protection). After harvest the fruit were stored for 1 week at 6 degrees C and 90% RH followed by 1 week at 20 degrees C and 60% RH to simulate retail conditions, or placed directly at 20 degrees C. All formulations significantly reduced decay in all cultivars. Switch, Signum and Folicur were the most active, while Score was slightly less effective. Teldor activity was low, especially in Thyrintos apricots, where the percentage of rotten fruit was slightly lower than in control fruit. Brown rot was the most representative disease, but in apricots a high percentage of fruit was affected by blue mold and grey mold. Rhizopus rot generally developed as a secondary disease on fruit previously affected by other pathogens and was more frequent in control and Teldor treated fruit. Preharvest sprays with Signum 3 days before harvest reduced postharvest decay after 1 week storage at 20 degrees C in Glo haven peaches and Venus nectarine harvested at advanced stage of maturity. Combining pre-harvest sprays with Signum and a 2-min postharvest dip in 2% sodium bicarbonate at 20 degrees C further reduced decay. In Sothern regions of Italy, the use of

  10. HIGH-QUALITY SELF-COMPACTING CONCRETE WITH COAL BURNING WASTE

    Directory of Open Access Journals (Sweden)

    Voronin Viktor Valerianovich

    2018-01-01

    Full Text Available Subject: nowadays self-compacting concretes (SCC, the use of which requires no additional compaction, have become widespread for use in densely-reinforced structures and hard-to-reach places. In self-compacting concretes, finely-ground admixtures-microfillers are widely used for controlling technological properties. Their introduction into the concrete mix allows us to obtain more dense structure of concrete. The influence of micro-fillers on water consumption and plasticity of concrete mix, on kinetics of strength gain rate, heat release and corrosion resistance is also noticeable. Research objectives: the work focuses on the development of composition of self-compacting concrete with assigned properties with the use of fly ash based on coal burning waste, optimized with the help of experimental design method in order to clarify the influence of ash and cement quantity, sand size on strength properties. Materials and methods: pure Portland cement CEM I 42.5 N was used as a binder. Crushed granite of fraction 5…20 mm was used as coarse aggregate, coarse quartz sand with the fineness modulus of 2.6 and fine sand with the fineness modulus of 1.4 were used as fillers. A superplasticizer BASF-Master Glenium 115 was used as a plasticizing admixture. The fly ash from Cherepetskaya thermal power plant was used as a filler. The study of strength and technological properties of self-compacting concrete was performed by using standard methods. Results: we obtained three-factor quadratic dependence of strength properties on the content of ash, cement and fraction of fine filler in the mix of fine fillers. Conclusions: introduction of micro-filler admixture based on the fly ash allowed us to obtain a concrete mix with high mobility, fluidity and self-compaction property. The obtained concrete has high strength characteristics, delayed strength gain rate due to replacement of part of the binder with ash. Introduction of the fly ash increases degree of

  11. Is health, measured by work ability index, affected by 12-hour rotating shift schedules?

    Science.gov (United States)

    Yong, Mei; Nasterlack, Michael; Pluto, Rolf-Peter; Elmerich, Kathrin; Karl, Dorothee; Knauth, Peter

    2010-07-01

    Two forms of continuously forward rotating 12-h shift schedules exist at BASF's Ludwigshafen site. These shift schedules were compared with a daytime working system to investigate potential differential effects on employee's health status assessed with the Work Ability Index (WAI). In the 3 x 12 system, a 12-h day shift is followed 24 h later by a 12-h night shift, and after a day off the employee returns to the day shift. The 4 x 12 schedule follows the same pattern except that there are 2 days off between the night and next day shift. A total of 924 participants (278 3 x 12 and 321 4 x 12 shiftworkers and 325 day workers) were recruited. A self-administered questionnaire was used to obtain information about shiftwork schedule, demographic characteristics, and lifestyle and social factors, and the WAI was applied. The outcomes of interest were the WAI sum score and its seven dimensions. In examining the relationship with the WAI categories, a Proportional Odds Model (POM) was used to identify the potential determinants. Logistic regression models were used to estimate the impact of age on single dimensions of WAI after adjustment for potential confounding factors. Increasing age and obesity (BMI > or = 30) were the only significant determinants of poorer WAI. Although a positive association was found linking the second WAI dimension (work ability in relation to job demands) with age, an inverse association was demonstrated consistently between age and the third and fourth WAI dimensions, i.e., number of diagnosed diseases and estimated work impairment due to disease, after adjustment for potential confounders. The age-dependency was moderate overall, but seemed to be stronger among shift- than day workers, although this difference did not reach statistical significance. There was no significant differential impact of the working time systems on the WAI sum score or on the individual WAI dimensions. Thus, there is no indication of an excessive adverse health impact

  12. Impact of non-target-site-resistance on herbicidal activity of imazamox on blackgrass (Alopecurus myosuroides Huds. in comparison to other ALS-graminicides

    Directory of Open Access Journals (Sweden)

    Sievernich, Bernd

    2014-02-01

    Full Text Available A black-grass (Alopecurus myosuroides Huds. resistance-monitoring conducted by BASF in 2010 - 2012 revealed a high number of accessions with resistance against imazamox. However, application of imazamoxbased products in a winter crop was limited to winter beans in France and United Kingdom only until the introduction of the Clearfield®-production system in autumn 2012 in winter oilseed rape. It is therefore assumed that the resistance mechanisms were probably selected by the frequent use of ACCase- and ALSinhibitors in winter crop rotations during the last 2 decades. Resistance level for each product-biotype combination was calculated according the “R”-classification system (S, R?, RR, RRR by directly comparing the product performance on a biotype versus untreated control. Majority of resistant biotypes did not show a target-site mutation at the known codon Pro197 or Trp574. In order to better evaluate the impact of Non-Target-Site-Resistance (NTSR on the activity of BEYOND (imazamox, ATLANTIS WG (mesosulfuron+iodosulfuron and ABAK (pyroxsulam, biotypes who have shown an ALS-target-site mutation were removed from further analysis. At the dose rate of 35 g ai/ha BEYOND provided good activity on susceptible biotypes of black-grass almost matching up with ATLANTIS WG and ABAK. However, activity of BEYOND declined stronger on biotypes classified as R? or RR for that product, while ATLANTIS WG and ABAK hardly showed any decline in control on this group of biotypes when applied at the recommended dose rate. It is assumed that the underlying NTSR-mechanism is not effective enough yet to confer resistance to ATLANTIS WG and ABAK, but on BEYOND. In contrast, biotypes classified as R? for ATLANTIS WG did show a stronger impact on the activity of BEYOND and ABAK then of ATLANTIS WG. These differences in control level probably do translate into differences in selection pressure as well.

  13. Project RA Research nuclear reactor - Annual report 1993 with comparative review for the period 1991 - 1993; Projekat Istrazivacki nuklearni reaktor RA - Izvestaj za 1993. godinu, uz uporedni pregled za period 1991 - 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-15

    Research reactor RA Annual report for year 1993 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. The ninth separate annex deals with the feasibility of RA reactor applications. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1993. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Poseban prilog razmatra mogucnosti koriscenja istrazivackog reaktora RA. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  14. {sup 137}CS-determination in game meat from some hunting areas in lower Austria; {sup 137}Cs-Bestimmungen im Wildfleisch aus einigen niederoesterreichischen Jagdrevieren

    Energy Technology Data Exchange (ETDEWEB)

    Ayromlou, S. [Inst. fuer Anorganische Chemie der Univ. Wien (Austria); Tataruch, F. [Forschungsinstitut fuer Wildtierkunde und Oekologie der Veterinaermedizinischen Univ., Wien (Austria)

    2001-07-01

    In 1986, the contamination of some regions in Austria by {sup 137}Cs, due to the Chernobyl accident was relatively high. Among other {sup 137}Cs is taken up by people by the consumption of game. In an area of Lower Austria which is relatively heavily contaminated by Chernobyl fallout since 1986 the {sup 137}Cs-contamination of meat of game-animals was measured every year. Clear differences arose in the load of the single game species whose causes just like the temporal changes are discussed. The highest {sup 137}Cs activity concentration was with 5243 Bq/kg measured on a wild boar. With this activity concentration an annual effective dose of only 0,06 mSv can be estimated for an annual average consumption of one kilogram meat of wild boar. (orig.) [German] Druch den Reaktor-Unfall in Tschernobyl wurde Oesterreich gebietsweise relativ stark mit {sup 137}Cs kontaminiert. Unter anderem gelangt {sup 137}Cs durch den Verzehr von Wildfleisch in den Koerper der Menschen. Daher wurden in einem niederoesterreichischen Gebiet, das 1986 durch Fallout verhaeltnismaessig stark kontaminiert worden war seither jaehrlich erlegte Wildtiere auf den {sup 137}Cs-Gehalt ihres Fleisches hin untersucht. Dabei ergaben sich deutliche Unterschiede in der Belastung der einzelnen Wildarten, deren Ursachen ebenso wie die zeitlichen Veraenderungen diskutiert werden. Die hoechste {sup 137}Cs-Aktivitaetskonzentration wurde mit 5243 Bq/kg bei einem Wildschwein gemessen. Mit einen durchschnittlichen Verzehr von 1 kg Wildschweinfleisch pro Jahr kann daraus eine maximale Effektivdosis von nur 0,06 mSv/Jahr abgeschaetzt werden. (orig.)

  15. Interesting Developments in UO{sub 2} Technology; Progres interessants dans la technologie du bioxyde d'uranium; Interesnye usovershenstvovaniya tekhnologii UO{sub 2}; Recientes progresos en la tecnologia del UO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Robertson, J. A.L. [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)

    1963-11-15

    vydelenie iz UO{sub 2} gazov, yavlyayushchikhsya produktami deleniya. V chastnosti, uvelichenie oblucheniya s 10{sup 15} do 10{sup 18} delenij/cm{sup 2} mozhet snizit' ochevidnye skorosti diffuzii dlya ksenona v UO{sub 2} pri posleduyushchikh obzhigakh na koehffitsient 10{sup 3}. Gaz, po-vidimomu, uderzhivaetsya v mel'chajshikh lovushkakh, chast' iz kotorykh sushchestvuet v iskhodnom materiale, a chast' obrazuetsya v rezul'tate radiatsionnogo povrezhdeniya. Tshchatel'nyj analiz pokazal sushchestvovanie medlennoj utechki iz lovushek, chto, veroyatno, ob''yasnyaetsya ogranichennoj rastvorimost'yu ksenona v UO{sub 2}. Vozmozhnost' osushchestvleniya izmerenij v reaktore otkryvaet novuyu fazu eshche bolee vazhnykh ehksperimentov. Oni pokazhut, imeyutsya li kakie-libo potentsial'nye ehkonomicheskie preimushchestva v novykh formakh topliva. V to zhe vremya budut prodolzhat'sya nastojchivye razrabotki spechenoj UO{sub 2} v prostoj geometrii sterzhnya. (author)

  16. Systems of Rb2I2-CdI2-PbI2 and Cs2I2-CdI2-PbI2

    International Nuclear Information System (INIS)

    Volchanskaya, V.V.; Il'yasov, I.I.

    1979-01-01

    The Rb 2 I 2 -CdI 2 -PbI 2 and Cs 2 I 2 -CdI 2 -PbI 2 triple systems have been studied, using the visual-polythermal method. The liquidus of the systems researched consists of the components and compounds crystallization fields: 2RbIxCdI 2 , 2RbIxRbI 2 , RbIxPbI 2 and 2CsIxCdI 2 , 4CsIxPbI 2 , CsIxPbI 2 , respectively. The crystallization fields converge in four non-variant points at 360, 280, 205 and 192 deg C in the Rb 2 I 2 -CdI 2 -PbI 2 system and at 375, 368, 208 and 190 deg C in the CsI 2 -CdI 2 -PbI 2 system

  17. Signum, a new fungicide with interesting properties in resistance management of fungal diseases in strawberries.

    Science.gov (United States)

    Hauke, K; Creemers, P; Brugmans, W; Van Laer, S

    2004-01-01

    Signum, a new fungicide developed by BASF, was applied during 6 successive years against fungal diseases in strawberries. The product is formulated as a water dispersible granule, containing 6.7 % pyraclostrobin and 26.7 % boscalid. Pyraclostrobin is similar in chemistry to other strobilurin fungicides like kresoxim-methyl and trifloxystrobin, registered for fruit disease control. Boscalid belongs to the class of carboxyanilides. Both components in the premix formulation combine two different biochemical modes of action in the fungal cell respiration. Therefore, this co-formulation gives a broad-spectrum activity and also a reduced resistance risk for different target pathogens. Botrytis cinerea is the most important disease on strawberry-fruits and thus the control of fruit rot is mainly focused on this fungus. In average over 6 years, Signum has not only given a very good control against Botrytis fruit rot, but it has also shown a high performance in the control of Colletotrichum. Besides, Signum provides good control of powdery mildew (Podosphaera aphanis) and limits the shift to other fruit rots like leather rot (Phytophthora cactorum and leak (Rhizopus, Mucor). The availability of several categories of fungicide families with a different mode of action gives opportunities in alternating different fungicides and is the best guarantee for a sustainable control of fruit rot in all kinds of strawberry production methods. Signum should be integrated in an overall disease management program. Trials, in which the applications of Signum were timed on disease forecasting, based on environmental factors favorable for Botrytis development, were very promising. This tool can also help in establishing the IPM-concept in the production of strawberries.

  18. Long-Term Efficacy of Various Natural or "Green" Insecticides against Bed Bugs: A Double-Blind Study.

    Science.gov (United States)

    Goddard, Jerome

    2014-11-28

    Bed bugs are resurging throughout the world, and, thus, effective pest control strategies are constantly needed. A few studies have evaluated 25(b) and other natural, or so-called "green" products, as well as over-the-counter insecticides for bed bugs, but additional studies are needed to determine efficacy of bed bug control products. This double-blinded research project was initiated to examine long-term effectiveness of six commercially available natural or "green" insecticides against bed bugs and to compare them with three known traditional residual products. Water was used as a control. Products were evaluated against both susceptible and resistant strains of bed bugs (1200 bugs each), and two different substrates were used. Temprid(®) (Bayer Corporation, Monheim, Germany), Transport(®) (FMC Corp., Philadelphia, PA, USA), Invader(®) (FMC Corporation, Philadelphia, PA USA), Cimexa(®) (Rockwell Laboratories, Kansas City, MO, USA), and BBT-2000(®) (Swepe-Tite LLC, Tupelo, MS, USA) were the only products which showed any substantial (>40%) bed bug control upon exposure to treated substrates after the six-month waiting period, although results with the resistant bed bug strain were much reduced. Alpine dust(®) (BASF Corporation, Florham Park, NJ, USA) killed 27% of bed bugs or less, depending on strain and substrate. EcoRaider(®) (North Bergen, NJ, USA) and Mother Earth D(®) (Whitmire Microgen, Florham Park, NJ, USA) (diatomaceous earth) produced 11% control or less. Cimi-Shield Protect(®) (Pest Barrier, Carson, CA, USA) showed no activity against bed bugs in this study. Analysis using SAS software showed a three-way interaction between treatment, substrate, and bed bug strain (Numerator DF 9; Denominator DF 80; F = 4.90; p < 0.0001).

  19. Investigation of the Na2(H2PO2)2 - Ba(H2PO2)2 - H2O Water-Salt Ternary System at Room Temperature

    OpenAIRE

    Erge, Hasan; Turan, Hakan; Kul, Ali Riza

    2016-01-01

    Objective: In this study, the solubility, density, conductivity and phase equilibria of the Na2(H2PO2)2-Ba(H2PO2)2-H2O ternary system located in the structure of the Na+, Ba2+, (H2PO2)-//H2O quaternary reciprocal water-salt system were investigated using physicochemical analysis methods. Material and Methods: Riedel-de Haen and Merck salts were used to investigate the solubility and phase equilibria of the Na2(H2PO2)2 -Ba(H2PO2)2-H2O ternary water–salt system at room temperature Res...

  20. Does dinitrogen hydrogenation follow different mechanisms for [(eta5-C5Me4H)2Zr]2(mu2,eta2,eta2-N2) and {[PhP(CH2SiMe2NSiMe2CH2)PPh]Zr}2(mu2,eta2,eta2-N2) complexes? A computational study.

    Science.gov (United States)

    Bobadova-Parvanova, Petia; Wang, Qingfang; Quinonero-Santiago, David; Morokuma, Keiji; Musaev, Djamaladdin G

    2006-09-06

    The mechanisms of dinitrogen hydrogenation by two different complexes--[(eta(5)-C(5)Me(4)H)(2)Zr](2)(mu(2),eta(2),eta(2)-N(2)), synthesized by Chirik and co-workers [Nature 2004, 427, 527], and {[P(2)N(2)]Zr}(2)(mu(2),eta(2),eta(2)-N(2)), where P(2)N(2) = PhP(CH(2)SiMe(2)NSiMe(2)CH(2))(2)PPh, synthesized by Fryzuk and co-workers [Science 1997, 275, 1445]--are compared with density functional theory calculations. The former complex is experimentally known to be capable of adding more than one H(2) molecule to the side-on coordinated N(2) molecule, while the latter does not add more than one H(2). We have shown that the observed difference in the reactivity of these dizirconium complexes is caused by the fact that the former ligand environment is more rigid than the latter. As a result, the addition of the first H(2) molecule leads to two different products: a non-H-bridged intermediate for the Chirik-type complex and a H-bridged intermediate for the Fryzuk-type complex. The non-H-bridged intermediate requires a smaller energy barrier for the second H(2) addition than the H-bridged intermediate. We have also examined the effect of different numbers of methyl substituents in [(eta(5)-C(5)Me(n)H(5)(-)(n))(2)Zr](2)(mu(2),eta(2),eta(2)-N(2)) for n = 0, 4, and 5 (n = 5 is hypothetical) and [(eta(5)-C(5)H(2)-1,2,4-Me(3))(eta(5)-C(5)Me(5))(2)Zr](2)(mu(2),eta(2),eta(2)-N(2)) and have shown that all complexes of this type would follow a similar H(2) addition mechanism. We have also performed an extensive analysis on the factors (side-on coordination of N(2) to two Zr centers, availability of the frontier orbitals with appropriate symmetry, and inflexibility of the catalyst ligand environment) that are required for successful hydrogenation of the coordinated dinitrogen.

  1. Syntheses of 4-aminobutanoic acid-2,2-/sup 2/H/sub 2/ and -4,4-/sup 2/H/sub 2/ and progabide-2,2-/sup 2/H/sub 2/ and -4,4-/sup 2/H/sub 2/

    Energy Technology Data Exchange (ETDEWEB)

    Davis, B.

    1987-10-01

    4-Aminobutanoic acid-2,2-/sup 2/H/sub 2/ and -4,4-/sup 2/H/sub 2/ were synthesized in high yield with high deuterium incorporation, and then converted into the corresponding deuterium-labelled anti-convulsant drug, progabide, by means of a transimination reaction.

  2. HIDROLISIS SELULOSA MENJADI GLUKOSA DENGAN KATALIS HETEROGEN ARANG AKTIF TERSULFONASI

    Directory of Open Access Journals (Sweden)

    Didi Dwi Anggoro

    2014-12-01

    . Hasilnya kemudian dicuci dan dikeringkan, dilakukan uji karakteristik dan performance (kinerja katalis berupa kapasitas H+, ukuran pori katalis dengan BET, uji gugus fungsi dengan FTIR, dan uji struktur marfologi katalis dengan SEM. Kinerja katalis diuji dalam reaktor autoclave melalui proses hidrotermal dengan mevariasikan jumlah katalis, dan variasi temperatur. Hasil penelitian menunjukkan untuk uji karakteristik kapasitas H+ sebesar 2,95 mmol/gr, untuk uji BET ukuran pori 29 m2/gr , untuk uji FTIR keberadaan gugus sulfonat terbaca pada vibrasi panjang gelombang 1750 cm-1 dan 1379 cm-1 , pada uji SEM struktur morfologi katalis yang lebih terbuka pada karbon aktif setelah proses sulfonasi. Kinerja katalis konversi tertinggi selulosa menjadi glukosa mencapai 87,2% pada jumlah alang-alang 2 gr, jumlah katalis 2 gr, dan temperatur 170oC selama  8 jam. Kata kunci : selulosa; glukosa; karbon aktif tersulfonasi; alang-alang

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

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M

    1979-12-15

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

  4. SINTESA GULA DARI SAMPAH ORGANIK DENGAN PROSES HIDROLISIS MENGGUNAKAN KATALIS ASAM

    Directory of Open Access Journals (Sweden)

    Deddy Irawan

    2012-11-01

    Full Text Available SYNTHESIS OF SUGAR FROM ORGANIC WASTES VIA ACID CATALYSTHYDROLYSIS. Hydrolysis process is an important step from every process to produce biofuel withorganic wastes as raw material. Hydrolysis process with chemical uses hydrochloride acid as catalystin which will transform holocellulose to glucose. Raw material of 100 grams is put into hydrolysisreactor with batch system equipped with pressure control and ratio hydrochloride of 1 : 6 w/v. Thevariables studied were temperature of 110-140oC, HCl concentration of 0.5-1%, time of hydrolysis of15-60 minutes. The sugar concentration was taken and then be analyzed by Nelson-Somogy method.The hydrolysis, which was carried out with the temperature of 120oC, time of 30 minutes, HClconcentration of 0.75%, and the pressure of 6 bar, produced sugar reduction of 27.3 mg/mL and yieldof 15.07%. Proses hidrolisis merupakan satu tahap penting dari rangkaian tahapan proses produksi bahan bakarnabati menggunakan bahan baku sampah organik. Proses hidrolisis secara kimiawi menggunakanHCl sebagai katalis akan mengubah holoselulosa yang terdapat pada sampah organik menjadi gula.Gula yang dihasilkan inilah yang dapat difermentasi menjadi bahan bakar nabati. Bahanbaku sebanyak 100 g dimasukkan dalam reaktor hidrolisis sistem batch yang dilengkapi denganpengukur tekanan dan ditambahkan larutan HCl pada perbandingan 1:6 b/v. Hidrolisis dilakukandengan memvariasikan suhu operasi 100-140oC, waktu proses 15-60 menit, serta konsentrasi HCl 0,5-1%. Hidrolisat yang dihasilkan dianalisis kadar gula menggunakan metode Nelson-somogy. Hasilhidrolisis yang dilakukan pada suhu 120oC selama 30 menit serta konsentrasi HCl 0,75% dan tekananterukur 6 bar menghasilkan gula 27,30 mg/mL dan yield gula sebesar 15,07%.

  5. Adaptive Neural Network Algorithm for Power Control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Husam Fayiz, Al Masri

    2017-01-01

    The aim of this paper is to design, test and evaluate a prototype of an adaptive neural network algorithm for the power controlling system of a nuclear power plant. The task of power control in nuclear reactors is one of the fundamental tasks in this field. Therefore, researches are constantly conducted to ameliorate the power reactor control process. Currently, in the Department of Automation in the National Research Nuclear University (NRNU) MEPhI, numerous studies are utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance, safety, efficiency and reliability of nuclear power plants. In particular, a study of an adaptive artificial intelligent power regulator in the control systems of nuclear power reactors is being undertaken to enhance performance and to minimize the output error of the Automatic Power Controller (APC) on the grounds of a multifunctional computer analyzer (simulator) of the Water-Water Energetic Reactor known as Vodo-Vodyanoi Energetichesky Reaktor (VVER) in Russian. In this paper, a block diagram of an adaptive reactor power controller was built on the basis of an intelligent control algorithm. When implementing intelligent neural network principles, it is possible to improve the quality and dynamic of any control system in accordance with the principles of adaptive control. It is common knowledge that an adaptive control system permits adjusting the controller’s parameters according to the transitions in the characteristics of the control object or external disturbances. In this project, it is demonstrated that the propitious options for an automatic power controller in nuclear power plants is a control system constructed on intelligent neural network algorithms. (paper)

  6. Experimental investigation and mathematical modelling of the combustion of brown coal, refuse and mixed fuels in a circulating fluidized bed combustor; Experimentelle Untersuchung und mathematische Modellierung der Verbrennung von Braunkohle, Abfallstoffen und Mischbrennstoffen in einer zirkulierenden Wirbelschichtfeuerung

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, W; Brunne, T; Hiller, A [Technische Univ. Dresden (Germany). Inst. fuer Energietechnik; Albrecht, J [Lurgi Umwelt GmbH, Frankfurt am Main (Germany); Quang, N [Polytechnic Inst., Danang (Viet Nam)

    1998-09-01

    Extensive experiments on combustion of biological materials and residues in fluidized bed combustors and dust combustors have been carried out at the Department of Power Plant Engineering of Dresden University since the early nineties. Particular interest was taken in mixing brown coal with sewage sludge, sugar pulp and waste wood. The experiments were supplemented by modelling in a research project funded jointly by the BMBF and Messrs. Lurgi since early 1997. A combustion cell model designed by Siegen University is being modified for the new mixed fuels, and preliminary investigations were carried out on a batch reactor while the modelling work was continued. (orig.) [Deutsch] An dem Lehrstuhl fuer Kraftwerkstechnik der TU Dresden werden seit Anfang der 90-iger Jahre umfangreiche experimentelle Untersuchungen zur Verbrennung von Bio- und Reststoffen in Wirbelschicht- und Staubfeuerungen durchgefuehrt. Dabei war vor allem die Zufeuerung dieser Stoffe in Waermeerzeugeranlagen auf Braunkohlenbasis von besonderem Interesse. Experimentell konnte nachgewiesen werden, dass sowohl Biobrennstoffe als auch Abfaelle in zirkulierenden Wirbelschichtfeuerungen umweltschonend zur Waermeerzeugung eingesetzt werden koennen. Als Beispiel wird das an Hand von Braunkohle-Klaerschlammgemischen sowie Bagasse- und Holz-Braunkohlegemischen gezeigt. Neben den experimentellen Untersuchungen bietet die Modellierung der Verbrennungsvorgaenge ein geeignetes Mittel um Voraussagen zu anderen Mischungsanteilen sowie anderen geometrischen Abmessungen machen zu koennen. Seit Anfang 1997 wird dazu ein vom BMBF und der Firma Lurgi gefoerdertes Forschungsvorhaben bearbeitet. Ein von der Universitaet Gesamthochschule Siegen fuer die Braunkohleverbrennung konzipiertes Zellenmodell wird auf die neuen Brennstoffgemische erweitert. Da grundsaetzlich andere Stoffzusammensetzungen vorliegen, wurden an einem Batch-Reaktor Voruntersuchungen zum Pyrolyseverhalten der Brennstoffe durchgefuehrt. Erste

  7. (Solid + liquid) phase equilibria of (Ca(H2PO2)2 + CaCl2 + H2O) and (Ca(H2PO2)2 + NaH2PO2 + H2O) ternary systems at T = 323.15 K

    International Nuclear Information System (INIS)

    Cao, Hong-yu; Zhou, Huan; Bai, Xiao-qin; Ma, Ruo-xin; Tan, Li-na; Wang, Jun-min

    2016-01-01

    Graphical abstract: Solubility diagram of the (Ca(H 2 PO 2 ) 2 + NaH 2 PO 2 + H 2 O) system at T = (323.15 and 298.15) K. - Highlights: • Phase diagrams of Ca 2+ -H 2 PO 2 − -Cl − -H 2 O, Ca 2+ -Na + -H 2 PO 2 − -H 2 O at 323.15 K were obtained. • Incompatible double salt of NaCa(H 2 PO 2 ) 3 in Ca 2+ -Na + -H 2 PO 2 − -H 2 O system was determined. • Density diagram of the corresponding liquid were simultaneously measured. - Abstract: Calcium hypophosphite has been widely used as an anti-corrosive agent, flame retardant, fertilizer, assistant for Ni electroless plating, and animal nutritional supplement. High purity calcium hypophosphite can be synthesized via the replacement reaction of sodium hypophosphite and calcium chloride. In this work, the (solid + liquid) phase equilibria of (Ca(H 2 PO 2 ) 2 + CaCl 2 + H 2 O) and (Ca(H 2 PO 2 ) 2 + NaH 2 PO 2 + H 2 O) ternary systems at T = 323.15 K were studied experimentally via the classical isothermal solubility equilibrium method, and the phase diagrams for these two systems were obtained. It was found that two solid salts of CaCl 2 ·2H 2 O and Ca(H 2 PO 2 ) 2 exist in the (Ca(H 2 PO 2 ) 2 + CaCl 2 + H 2 O) system, and three salts of Ca(H 2 PO 2 ) 2 , NaH 2 PO 2 ·H 2 O and one incompatible double salt, NaCa(H 2 PO 2 ) 3 occur in the (Ca(H 2 PO 2 ) 2 + NaH 2 PO 2 + H 2 O) system.

  8. Synthesis and structure of [(NH2)2CSSC(NH2)2]2[OsBr6]Br2 . 3H2O

    International Nuclear Information System (INIS)

    Rudnitskaya, O. V.; Kultyshkina, E. K.; Stash, A. I.; Glukhova, A. A.; Venskovskii, N. U.

    2008-01-01

    The complex [(NH 2 ) 2 CSSC(NH 2 ) 2 ] 2 [OsBr 6 ]Br 2 . 3H 2 O is synthesized by the reaction of K 2 OsBr 6 with thiocarbamide in concentrated HBr and characterized using electronic absorption and IR absorption spectroscopy. Its crystal structure is determined by X-ray diffraction. The crystals are orthorhombic, a = 11.730(2) A, b = 14.052(3) A, c = 16.994(3) A, space group Cmcm, and Z = 4. The [OsBr 6 ] 2- anionic complex has an octahedral structure. The Os-Br distances fall in the range 2.483-2.490 A. The α,α'-dithiobisformamidinium cation is a product of the oxidation of thiocarbamide. The S-S and C-S distances are 2.016 and 1.784 A, respectively. The H 2 O molecules, Br - ions, and NH 2 groups of the cation are linked by hydrogen bonds.

  9. Hydrothermal synthesis and crystal structures of new uranyl oxalate hydroxides: α- and β-[(UO2)2(C2O4)(OH)2(H2O)2] and [(UO2)2(C2O4)(OH)2(H2O)2].H2O

    International Nuclear Information System (INIS)

    Duvieubourg, Laurence; Nowogrocki, Guy; Abraham, Francis; Grandjean, Stephane

    2005-01-01

    Two modifications of the new uranyl oxalate hydroxide dihydrate [UO 2 ) 2 (C 2 O 4 )(OH) 2 (H 2 O) 2 ] (1 and 2) and one form of the new uranyl oxalate hydroxide trihydrate [(UO 2 ) 2 (C 2 O 4 )(OH) 2 (H 2 O) 2 ].H 2 O (3) were synthesized by hydrothermal methods and their structures determined from single-crystal X-ray diffraction data. The crystal structures were refined by full-matrix least-squares methods to agreement indices R(wR)=0.0372(0.0842) and 0.0267(0.0671) calculated for 1096 and 1167 unique observed reflections (I>2σ(I)), for α (1) and β (2) forms, respectively and to R(wR)=0.0301(0.0737) calculated for 2471 unique observed reflections (I>2σ(I)), for 3. The α-form of the dihydrate is triclinic, space group P1-bar , Z=1, a=6.097(2), b=5.548(2), c=7.806(3)A, α=89.353(5), β=94.387(5), γ=97.646(5) o , V=260.88(15)A 3 , β-form is monoclinic, space group C2/c, Z=4, a=12.180(3), b=8.223(2), c=10.777(3)A, β=95.817(4), V=1073.8(5)A 3 . The trihydrate is monoclinic, space group P2 1 /c, Z=4, a=5.5095(12), b=15.195(3), c=13.398(3)A, β=93.927(3), V=1119.0(4)A 3 . In the three structures, the coordination of uranium atom is a pentagonal bipyramid composed of dioxo UO 2 2+ cation perpendicular to five equatorial oxygen atoms belonging to one bidentate oxalate ion, one water molecule and two hydroxyl ions in trans configuration in 2 and in cis configuration in 1 and 3. The UO 7 polyhedra are linked through hydroxyl oxygen atoms to form different structural building units, dimers [U 2 O 10 ] obtained by edge-sharing in 1, chains [UO 6 ] ∼ and tetramers [U 4 O 26 ] built by corner-sharing in 2 and 3, respectively. These units are further connected by oxalate entities that act as bis-bidentate to form one-dimensional chains in 1 and bi-dimensional network in 2 and 3. These chains or layers are connected in frameworks by hydrogen-bond arrays

  10. THE PROPERTIES OF CHARCOAL FROM THE BLACK LIQUOR OF THE SODA PULPING OF RICE STRAW

    Directory of Open Access Journals (Sweden)

    Nyoman Jaya Wistara

    2013-11-01

    Full Text Available The main goal of the present works was to determine chemical changes, thermal decomposition, and the content of moisture, ash, volatile, fixed carbon and calorific value of soda pulping black liquor of the rice straw. Neutralized black liquor was dried to a moisture content of 10% and then pyrolized at 106oC-750oC. It was found that calorific value, fixed carbon, volatile mater, and moisture content were in the range of 2782-4716 cal/g, 49.2-81.6%, 15.5-47.5%, and 0.2-3.5%, respectively. Ash content was not influenced by the temperature of pyrolysis and was thought to depend on its initial silicate content. The weight loss of pulp was higher than that of black liquor. Extreme weight loss has been found in the temperature of 200-400oC. Noticeable functional groups changes were found with the increasing temperature of pyrolysis. Hydroxyl group completely disappeared at 300oC and above. Carbonyl related groups were also disappeared at 300-500oC, but it was reformed at 650 and 750oC. It might be brought about by the deformation of chemical bonding of oxygen ring in lignin structures. SIFAT-SIFAT ARANG LINDI HITAM DARI PEMASAKAN JERAMI DENGAN LARUTAN SODA API. Penelitian ini bertujuan untuk menentukan perubahan sifat kimia, dekomposisi termal dan kadar air, abu, zat terbang, karbon terikat serta nilai kalor arang lindi hitam pemasakan soda jerami padi. Dalam penelitian ini, lindi hitam netral dikeringkan (kadar air 10%, kemudian dipirolisis pada selang suhu 100-750oC di dalam reaktor berpengatur suhu. Hasil penelitian menunjukkan bahwa nilai kalor, karbon terikat, zat terbang dan kadar air masing-masing berselangdari 2782-4716 cal/g, 49,2-81,6%, 15,5-47,5%, dan 0,2-3,5%. Kadar abu tidak dipengaruhi oleh suhu pirolisis dan diduga bergantung pada kadar silika bahan bakunya. Nilai kalor meningkat dengan meningkatnya kadar karbon terikat. Perilaku kehilangan berat arang dari lindi hitam berbeda dengan perilaku kehilangan berat pulp jerami. Kehilangan

  11. PEMBUATAN BAHAN BAKU SPREADS KAYA KAROTEN DARI MINYAK SAWIT MERAH MELALUI INTERESTERIFIKASI ENZIMATIK MENGGUNAKAN REAKTOR BATCH [Preparation of Red Palm Oil Based-Spreads Stock Rich in Carotene Through Enzymatic Interesterification in Batch-type Reactor

    Directory of Open Access Journals (Sweden)

    Nur Wulandari1,2

    2012-12-01

    Full Text Available Enzymatic interesterification of red palm oil (a mixture of red palm olein/RPO and red palm stearin/RPS in 1:1 weight ratio and coconut oil (CNO blends of varying proportions using a non-specific immobilized Candida antartica lipase (Novozyme 435 was studied for the preparation of spread stock. The interesterification reaction was held in a batch-type reactor. Two substrate blends were chosen for the production of spread stock i.e. 77.5:22,5 and 82.5:17.5 (RPO/RPS:CNO, by weight through enzymatic interesterification in three different reaction times (2, 4, and 6 hours. The interesterification reactions were conducted at 60°C, 200 rpm agitation speed and 10% of Novozyme 435. The interesterified products were evaluated for their physical characteristics (slip melting point or SMP and solid fat content or SFC and chemical characteristics (carotene retention, moisture content, and free fatty acid/FFA content. All of the interesterified products had lower SFC and SMP as compared to the initial blends. The SMP and SFC increased in longer reaction times. The SMP ranged from 30.8°C to 34.9°C. The carotene retention ranged from 74.80% to 81.08%, while the moisture content and FFA content increased in longer reaction times. The interesterified products had desirable physical properties for possible use as a spread stock rich in carotene.

  12. Full scale application of the autotrophic denitrification in trickling filters for treatment of rejection water with high ammonia concentrations from sludge dewatering. Final report; Untersuchungen zur autotrophen Stickstoffentfernung aus ammoniumreichem Filtratwasser der Schlammentwaesserung mit grosstechnischer Realisierung in Tropfkoerpern. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Neumueller, B.; Metzger, J.W.; Pinnekamp, J.

    2003-07-01

    strictly. In a semi-technical anammox-reactor which was operated for several years showed, that the process is very robust. Performance loss is only temporary, if the operating conditions aren't fulfilled. (orig.) [German] Bei kommunalen Klaeranlagen mit anaerober Schlammbehandlung faellt bei der Entwaesserung des stabilisierten Schlammes stark ammoniumhaltiges Prozesswasser an. Die Mitbehandlung dieses Teilstroms aus der Schlammbehandlung in der Hauptstrombiologie der Klaeranlage kann zu einer Erhoehung der Stickstoffbelastung von bis zu 20% fuehren. Eine separate Behandlung von Prozesswaessern kann die Stickstoff-Ablaufwerte verbessern und schafft Reserven in der Hauptstrombiologie. Die autotrophe Denitrifikation nach vorangegangener Teilnitritation in Tropfkoerpern ist ein neuartiges Verfahren zur Behandlung hoch ammoniumhaltiger Abwaesser. Hierzu werden in einem ersten Tropfkoerper etwa 60% des Ammoniums zu Nitrit umgewandelt, wobei die Nitratation gehemmt wird. In einem zweiten geschlossenen Tropfkoerper wird das Ammonium unter anoxischen Bedingungen, mit Nitrit als Elektronenakzeptor, zu molekularem Stickstoff oxidiert. Dieses Verfahren wurde erstmals im grosstechnischen Betrieb auf der Klaeranlage Sindelfingen realisiert. Die Untersuchungen zeigten, dass bereits wenige mg/l Ammoniak im ersten Reaktor ausreichten, um die Nitratation zu hemmen. Da die Nitratation nach einem Anstieg und dem darauffolgenden Abfallen der Ammoniakkonzentration zunahm, fand offensichtlich eine Adaption der Biomasse an die hoeheren Ammoniakgehalte statt. Deshalb sollte die Ammoniakkonzentration moeglichst konstant gehalten und groessere Schwankungen ueber eine laengere Zeit vermieden werden. Nur mit der thermischen Abtoetung der Mikroorganismen und dem erneuten Einfahren des Prozesses konnte nach einer Adaption wieder eine vollstaendige Nitratationshemmung bei geringen Ammoniakkonzentrationen gewaehrleistet werden. Durch die aeusserst geringe Wachstumsrate der Anammoxbakterien nimmt

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1963-10-15

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

  14. DESAIN AWAL TURBIN UAP TIPE AKSIAL UNTUK KONSEP RGTT30 BERPENDINGIN HELIUM

    Directory of Open Access Journals (Sweden)

    Sri Sudadiyo

    2016-06-01

    Full Text Available ABSTRAK DESAIN AWAL TURBIN UAP TIPE AKSIAL UNTUK KONSEP RGTT30 BERPENDINGIN HELIUM. Konsep reaktor daya nuklir yang dikembangkan merupakan jenis reaktor berpendingin gas dengan temperatur tinggi (RGTT. Gas yang digunakan untuk mendinginkan teras RGTT adalah helium. Konsep RGTT ini dapat menghasilkan daya termal 30 MWth sehingga dinamakan RGTT30. Temperatur helium mampu mencapai 700 °C ketika keluar dari teras RGTT30 dan digunakan untuk memanaskan air di dalam steam generator hingga mencapai temperatur 435 °C. Steam generator dihubungkan dengan turbin uap yang dikopel dengan generator listrik untuk membangkitkan daya 7,27 MWe. Uap yang keluar dari turbin dilewatkan kondensor untuk mencairkan uap menjadi air. Rangkaian komponen dari steam generator, turbin, dan kondensor dinamakan sistem turbin uap. Turbin terdiri dari sudu-sudu yang dimaksudkan untuk mengubah tenaga uap kedalam tenaga mekanis berupa putaran. Efisiensi turbin merupakan parameter yang harus diperhatikan dalam sistem turbin uap ini. Tujuan dari makalah ini adalah untuk mengusulkan sudu tipe aksial dan untuk menganalisa perbaikan efisiensi turbin. Metode yang digunakan yaitu aplikasi prinsip termodinamika yang berhubungan dengan konservasi energi dan massa. Perangkat lunak Cycle-Tempo dipakai untuk mendapatkan parameter termodinamika dan untuk mensimulasikan sistem turbin uap berbasis RGTT30. Pertama, dibuat skenario dalam simulasi sistem turbin uap untuk mengetahui efisiensi dan laju aliran massa uap yang diperoleh nilai optimal 87,52 % dan 8,759 kg/s pada putaran 3000 rpm. Kemudian, turbin uap diberi sudu tipe aksial dengan diameter tip 1580 mm dan panjang 150 mm. Hasil yang diperoleh adalah nilai efisiensi turbin uap naik menjadi 88,3 % pada putaran konstan (3000 rpm. Penambahan nilai efisiensi turbin sebesar 0,78 % menunjukkan peningkatan kinerja RGTT30 secara keseluruhan. Kata kunci: Tipe aksial, turbin uap, RGTT30   ABSTRACT PRELIMINARY DESIGN ON STEAM TURBINE OF AXIAL TYPE

  15. Bis{(E-3-[2-(hydroxyiminopropanamido]-2,2-dimethylpropan-1-aminium} bis[μ-(E-N-(3-amino-2,2-dimethylpropyl-2-(hydroxyiminopropanamido(2−]bis{[(E-N-(3-amino-2,2-dimethylpropyl-2-(hydroxyiminopropanamide]copper(II} bis((E-{3-[2-(hydroxyiminopropanamido]-2,2-dimethylpropyl}carbamate acetonitrile disolvate

    Directory of Open Access Journals (Sweden)

    Andrii I. Buvailo

    2012-12-01

    Full Text Available The reaction between copper(II nitrate and (E-N-(3-amino-2,2-dimethylpropyl-2-(hydroxyiminopropanamide led to the formation of the dinuclear centrosymmetric copper(II title complex, (C8H18N3O22[Cu2(C8H15N3O22(C8H17N3O22](C9H16N3O42·2CH3CN, in which an inversion center is located at the midpoint of the Cu2 unit in the center of the neutral [Cu2(C8H15N3O22(C8H17N3O22] complex fragment. The Cu2+ ions are connected by two N—O bridging groups [Cu...Cu separation = 4.0608 (5 Å] while the CuII ions are five-coordinated in a square-pyramidal N4O coordination environment. The complex molecule co-crystallizes with two molecules of acetonitrile, two molecules of the protonated ligand (E-3-[2-(hydroxyiminopropanamido]-2,2-dimethylpropan-1-aminium and two negatively charged (E-{3-[2-(hydroxyiminopropanamido]-2,2-dimethylpropyl}carbamate anions, which were probably formed as a result of condensation between (E-N-(3-amino-2,2-dimethylpropyl-2-(hydroxyiminopropanamide and hydrogencarbonate anions. In the crystal, the complex fragment [Cu2(C8H15N3O22(C8H17N3O22] and the ion pair C8H18N3O2+.C9H16N3O4− are connected via an extended system of hydrogen bonds.

  16. Gl(2/2)-oscillators and Gl(2/2)-dynamical symmetry

    International Nuclear Information System (INIS)

    Kamupingene, A.H.; Nguyen Anh Ky.

    1991-07-01

    Extending the concept of the dynamical symmetry, we identify the Lie superalgebra Gl(2/2) as a dynamical (super-)algebra of a class of non-canonical quantum systems, whose dynamical variables and quantities can be realized in terms of the Gl(2/2)-generators. In this way, a new class of harmonic oscillators is established. As a consequence of the choice of the dynamical variables the Heisenberg algebra and the Hermitian condition for the Gl(2/2)-representations are also given. (author). 12 refs

  17. 2-(2-Pyridylpyridinium (2,2′-bipyridine-κ2N,N′tetrakis(nitrato-κ2O,O′bismuthate(III

    Directory of Open Access Journals (Sweden)

    Shu-Shen Zhang

    2011-10-01

    Full Text Available The structure of the title compound, (C10H9N2[Bi(NO34(C10H8N2], consists of 2-(2-pyridylpyridinium cations and anions [Bi(NO34(C10H8N2]−. The Bi3+ ion lies on the twofold axis. It is coordinated by two nitrogen atoms from one 2,2′-bipyridine ligand and eight oxygen atoms from four NO3− anions. The disordered cation is positioned at the inversion centre. The [Bi(NO34(C10H8N2]− anions and 2-(2-pyridylpyridinium cations are connected via N—H...O hydrogen bonds into chains. Moreover, these chains are further linked into a two-dimensional layered structure through π–π stacking interactions between bipyridine ligands along the c axis [centroid–centroid distance = 2.868 (4 Å].

  18. Hydraulic Behavior in The Downflow Hanging Sponge Bioreactor

    Directory of Open Access Journals (Sweden)

    Izarul Machdar

    2016-12-01

    Full Text Available Performance efficiency in a Downflow Hanging Sponge (DHS bioreactor is associated with the amount of time that a wastewater remains in the bioreactor. The bioreactor is considered as a plug flow reactor and its hydraulic residence time (HRT depends on the void volume of packing material and the flow rate. In this study, hydraulic behavior of DHS bioreactor was investigated by using tracer method. Two types of sponge module covers, cylindrical plastic frame (module-1 and plastic hair roller (module-2, were investigated and compared. A concentrated NaCl solution used as an inert tracer and input as a pulse at the inlet of DHS bioreactor. Analysis of the residence time distribution (RTD curves provided interpretation of the index distribution or holdup water (active volume, the degree of short-circuiting, number of tanks in series (the plug flow characteristic, and the dispersion number. It was found that the actual HRT was primarily shorter than theoretical HRT of each test. Holdup water of the DHS bioreactor ranged from 60% to 97% and 36% to 60% of module-1 and module-2, respectively. Eventhough module-1 has higher effective volume than module-2, result showed that the dispersion numbers of the two modules were not significant difference. Furthermore, N-values were found larger at a higher flow rate. It was concluded that a DHS bioreactor design should incorporated a combination of water distributor system, higher loading rate at startup process to generate a hydraulic behavior closer to an ideal plug flow.ABSTRAKEfisiensi unjuk kerja bioreactor Downflow Hanging Sponge (DHS berkaitan dengan lamanya waktu tinggal limbah berada di dalam bioreaktor tersebut. Bioreaktor DHS dianggap sebagai seuatu reaktor aliran sumbat (plug flow dimana waktu tinggal hidraulik (HRT tergantung pada volume pori material isian dan laju alir. Dua jenis modul digunakan dalam penelitian ini, yang diberi nama dengan module-1 dan module-2 untuk melihat pengaruh jenis modul

  19. PSA LEVEL 3 DAN IMPLEMENTASINYA PADA KAJIAN KESELAMATAN PWR

    Directory of Open Access Journals (Sweden)

    Pande Made Udiyani

    2015-03-01

    Full Text Available Kajian keselamatan PLTN menggunakan metodologi kajian probabilistik sangat penting selain kajian deterministik. Metodologi kajian menggunakan Probabilistic Safety Assessment (PSA Level 3 diperlukan terutama untuk estimasi kecelakaan parah atau kecelakaan luar dasar desain PLTN. Metode ini banyak dilakukan setelah kejadian kecelakaan Fukushima. Dalam penelitian ini dilakukan implementasi PSA Level 3 pada kajian keselamatan PWR, postulasi kecelakan luar dasar desain PWR AP-1000 dan disimulasikan di contoh tapak Bangka Barat. Rangkaian perhitungan yang dilakukan adalah: menghitung suku sumber dari kegagalan teras yang terjadi, pemodelan kondisi meteorologi tapak dan lingkungan, pemodelan jalur paparan, analisis dispersi radionuklida dan transportasi fenomena di lingkungan, analisis deposisi radionuklida, analisis dosis radiasi, analisis perlindungan & mitigasi, dan analisis risiko. Kajian menggunakan rangkaian subsistem pada perangkat lunak PC Cosyma. Hasil penelitian membuktikan bahwa implementasi metode kajian keselamatan PSA Level 3 sangat efektif dan komprehensif terhadap estimasi dampak, konsekuensi, risiko, kesiapsiagaan kedaruratan nuklir (nuclear emergency preparedness, dan manajemen kecelakaan reaktor terutama untuk kecelakaan parah atau kecelakaan luar dasar desain PLTN. Hasil kajian dapat digunakan sebagai umpan balik untuk kajian keselamatan PSA Level 1 dan PSA Level 2. Kata kunci: PSA level 3, kecelakaan, PWR   Reactor safety assessment of nuclear power plants using probabilistic assessment methodology is most important in addition to the deterministic assessment. The methodology of Level 3 Probabilistic Safety Assessment (PSA is especially required to estimate severe accident or beyond design basis accidents of nuclear power plants. This method is carried out after the Fukushima accident. In this research, the postulations beyond design basis accidentsof PWR AP - 1000 would be taken, and simulated at West Bangka sample site. The

  20. 49 CFR 173.115 - Class 2, Divisions 2.1, 2.2, and 2.3-Definitions.

    Science.gov (United States)

    2010-10-01

    ... substances of Class 8, PG I are forbidden from transportation in an aerosol container. (7) Flammable... 2.1, 2.2, and 2.3—Definitions. (a) Division 2.1 (Flammable gas). For the purpose of this subchapter, a flammable gas (Division 2.1) means any material which is a gas at 20 °C (68 °F) or less and 101.3...

  1. New superhindered polydentate polyphosphine ligands P(CH2CH2P(t)Bu2)3, PhP(CH2CH2P(t)Bu2)2, P(CH2CH2CH2P(t)Bu2)3, and their ruthenium(II) chloride complexes.

    Science.gov (United States)

    Gilbert-Wilson, Ryan; Field, Leslie D; Bhadbhade, Mohan M

    2012-03-05

    The synthesis and characterization of the extremely hindered phosphine ligands, P(CH(2)CH(2)P(t)Bu(2))(3) (P(2)P(3)(tBu), 1), PhP(CH(2)CH(2)P(t)Bu(2))(2) (PhP(2)P(2)(tBu), 2), and P(CH(2)CH(2)CH(2)P(t)Bu(2))(3) (P(3)P(3)(tBu), 3) are reported, along with the synthesis and characterization of ruthenium chloro complexes RuCl(2)(P(2)P(3)(tBu)) (4), RuCl(2)(PhP(2)P(2)(tBu)) (5), and RuCl(2)(P(3)P(3)(tBu)) (6). The bulky P(2)P(3)(tBu) (1) and P(3)P(3)(tBu) (3) ligands are the most sterically encumbered PP(3)-type ligands so far synthesized, and in all cases, only three phosphorus donors are able to bind to the metal center. Complexes RuCl(2)(PhP(2)P(2)(tBu)) (5) and RuCl(2)(P(3)P(3)(tBu)) (6) were characterized by crystallography. Low temperature solution and solid state (31)P{(1)H} NMR were used to demonstrate that the structure of RuCl(2)(P(2)P(3)(tBu)) (4) is probably analogous to that of RuCl(2)(PhP(2)P(2)(tBu)) (5) which had been structurally characterized.

  2. Actividad química de los ligandos puente difósforo y difosfenilo en los complejos binucleares (Mo2Cp2(n-PCy2) (n-K2:K2-P2)(CO)2)-y (Mo2Cp2(n-PCy2)(n-K2:K2-P2Me)(CO)2)

    OpenAIRE

    Lozano Rivera, Raquel

    2015-01-01

    El trabajo de investigación que se recoge en la presente Memoria comprende un amplio estudio de la reactividad de complejos metálicos binucleares con ligandos puente difósforo y metildifosfenilo procedentes de la activación directa del fósforo blanco. Por un lado, se ha llevado a cabo un amplio análisis del comportamiento químico de la especie aniónica [Mo2Cp2(¿-PCy2)(¿-¿2:¿2-P2)(CO)2]- frente a electrófilos de distinta naturaleza, tales como clorofosfinas y complejos metálicos generadores...

  3. SINTESIS DIMETIL ASETAL SITRONELAL DENGAN KATALIS GAS HCL

    Directory of Open Access Journals (Sweden)

    E Cahyono

    2014-06-01

    Full Text Available Perlindungan gugus aldehida melalui pembentukan asetal umumnya dilakukan dengan metanol atau etanol terkatalis asam. Sitronelal memiliki gugus aldehida dan gugus alkena. Dalam lingkungan asam, sitronelal mudah mengalami siklisasi membentuk isopulegol dan isomernya. Penelitian ini bertujuan untuk mensintesis dimetil asetal sitronelal dengan katalis gas HCl. Penggunaan gas HCl secara terbatas dimaksudkan untuk menghindari siklisasi sitronelal. Dalam suatu reaktor, 10 mL sitronelal ditambah dengan 20 mL metanol absolut dan 2 g CaCl2 pada labu leher tiga. Gas HCl dialirkan dengan laju alir 12 mL/menit pada temperatur ruang hingga pH campuran menjadi 2-3. Kemudian dilakukan pengadukan pada 30°C selama 48 jam dan diambil sampel pada durasi reaksi 12, 24 dan 48 jam. Dalam penelitian ini dilakukan variasi temperatur dan jumlah CaCl2. Dimetil asetal sitronelal yang dihasilkan diisolasi dengan distilasi fraksinasi pengurangan tekanan dan diuji strukturnya dengan GC-MS, IR dan 1H-NMR. Peningkatan temperatur dan jumlah CaCl2 meningkatkan konversi sitronelal. Setelah 48 jam kuantitas dimetil asetal sitronelal mencapai 48,65%. Distilasi fraksinasi pengurangan tekanan (5 cmHg terbukti meningkatkan kemurnian dimetil asetal sitronelal menjadi 86,39% terhadap produk kasarnya. Elusidasi struktur dengan spektrofotometer infra merah (IR dan resonansi magnetik inti (1H-NMR pada hasil distilasi fraksinasi membuktikan adanya struktur asetal sitronelal.  Aldehyde group protection through acetal formation is generally performed by acid catalyzed methanol or ethanol. Citronellal that has aldehyde and alkene groups. In acidic environment, it is prone to do cyclization to form isopulegol and its isomers. This study aims to synthesize dimethyl acetal of citronellal with HCl gas catalysts. The limitation of HCl using gas was intended to avoid the citronellal cyclization. In a reactor, 10 mL citronellal was added with 20 mL of absolute methanol and 2 g CaCl2 in the three

  4. Chlorobis(2,2,2-trifluoroethoxy) and dichloro(2,2,2-trifluoroethoxy)-vanadium(III): synthesis and coordination chemistry

    International Nuclear Information System (INIS)

    Chadha, S.L.; Uppal, K.

    1987-01-01

    VCl(OCH 2 CF 3 ) 2 and VCl 2 (OCH 2 CF 3 ) have been synthesised. They form complexes with monodentate oxygen or nitrogen donor ligands. The magnetic moments for these complexes indicate antiferromagnetic interactions and their electronic spectra are consistent with octahedral coordination of V(III) involving chloride, organoxy ions and the ligands. The i.r. spectra support the alkoxy-bridged structure for these complexes in which the ligands are probably cis to each other. 1 H nmr spectrum of VCl(OCH 2 CF 3 ) 2 shows a sharp quartet suggesting a sharp exchange of terminal and bridging alkoxy groups. 19 F nmr spectra of the parent compounds also show a single sharp band. The mass spectra suggest a dimeric form for both compounds in vapour phase

  5. Fermi surfaces of YRu2Si2 and LaRu2Si2

    International Nuclear Information System (INIS)

    Settai, R.; Ikezawa, H.; Toshima, H.; Takashita, M.; Ebihara, T.; Sugawara, H.; Kimura, T.; Motoki, K.; Onuki, Y.

    1995-01-01

    We have measured the de Haas-van Alphen effect of YRu 2 Si 2 and LaRu 2 Si 2 to clarify the Fermi surfaces and cyclotron masses. Main hole-Fermi surfaces of both compounds with a distorted ellipsoid shape are similar, occupying about half of the Brillouin zone. The small hole-Fermi surfaces with the shape of a rugby ball are three in number for LaRu 2 Si 2 , and one for YRu 2 Si 2 . An electron-Fermi surface consists of a doughnut like shape for LaRu 2 Si 2 , while a cylinder along the [001] direction and a multiply-connected shape exist for YRu 2 Si 2 . The cyclotron masses of YRu 2 Si 2 are a little larger than those of LaRu 2 Si 2 . ((orig.))

  6. Study of the solubility, viscosity and density in Na+, Zn2+/Cl− − H2O, Na+ − Zn2+ − (H2PO2)− − H2O, Na+, Cl−/(H2PO2)− − H2O, and Zn2+, Cl−/(H2PO2)− − H2O ternary systems, and in Na+, Zn2+/Cl−, (H2PO2)−//H2O reciprocal quaternary system at 273.15 K

    International Nuclear Information System (INIS)

    Adiguzel, Vedat; Erge, Hasan; Alisoglu, Vahit; Necefoglu, Hacali

    2014-01-01

    Highlights: • The physicochemical properties of ternary and one quaternary have been studied. • Reciprocal quaternary systems’ solubility and phase equilibrium have been studied. • In all systems the solid phases have been found. • It was found that Zn(H 2 PO 2 ) 2 salt contains 70% of the general crystallization field. - Abstract: The solubility and the physicochemical properties (density, viscosity) in the Na-Zn- Cl-H 2 O), (Na + Zn + H 2 PO 2 + H 2 O), (Na + Cl + H 2 PO 2 + H 2 O), and (Zn + Cl + H 2 PO 2 + H 2 O) ternaries, and in Na + , Zn 2+ /Cl − , (H 2 PO 2 ) − //H 2 O reciprocal quaternary systems at T = 273.15 K were investigated by using the isothermal method. The diagrams of ternary salts systems, (NaCl + ZnCl 2 + H 2 O), (NaCl + NaH 2 PO 2 + H 2 O), (NaH 2 PO 2 + Zn(H 2 PO 2 ) 2 + H 2 O), (ZnCl 2 + Zn(H 2 PO 2 ) 2 + H 2 O), are plotted in figures 1–4. However, whole ions of reciprocal quaternary salt systems are plotted in figure 5. Additionally, the density and viscosity values of ternary systems vs. their corresponding composition values in weight per cent are plotted in figures 6–10. At the (i) (ZnCl 2 + Zn(H 2 PO 2 ) 2 + H 2 O), (ii) (NaCl + ZnCl 2 + H 2 O), (iii) (NaCl + NaH 2 PO 2 + H 2 O), (iv) (NaH 2 PO 2 + Zn(H 2 PO 2 ) 2 + H 2 O) ternary systems the solid phase compositions have been determined as: (i) Zn(H 2 PO 2 ) 2 ⋅ H 2 O, Zn(H 2 PO 2 ) 2 , ZnCl 22H 2 O, (ii) NaCl, 2NaCl ⋅ ZnCl 22H 2 O, and ZnCl 22H 2 O, (iii) NaCl and NaH 2 PO 2 ⋅ H 2 O, (iv) Zn(H 2 PO 2 ) 2 ⋅ H 2 O and NaH 2 PO 2 ⋅ H 2 O, respectively. On the other hand reciprocal quaternary system was observed as: ZnCl 22H 2 O, 2NaCl ⋅ ZnCl 22H 2 O, Zn(H 2 PO 2 ) 2 ⋅ H 2 O, NaH 2 PO 2 ⋅ H 2 O, NaCl. According to results, the least soluble salt was Zn(H 2 PO 2 ) 2 . The crystallization field of this salt, being the largest in comparison with those of other salts, occupied 70% of the general crystallization field

  7. 1-Methoxy-3-o-tolylbicyclo[2.2.2]oct-5-ene-2,2-dicarbonitrile

    Directory of Open Access Journals (Sweden)

    Orhan Büyükgüngör

    2009-09-01

    Full Text Available In the title compound, C18H18N2O, the cyclohexene and cyclohexane rings of the bicyclo[2.2.2]oct-5-ene unit adopt distorted boat conformations. In the crystal, molecules exist as C—H...N hydrogen-bonded centrosymmetric R22(14 dimers, which are further linked by C—H...π interactions.

  8. A comparative study of the physical and chemical properties of nano-sized ZnO particles from multiple batches of three commercial products

    Energy Technology Data Exchange (ETDEWEB)

    Yin, Hong [Commonwealth Scientific and Industrial Research Organisation, Manufacturing Flagship (Australia); Coleman, Victoria A. [National Measurement Institute Australia, Nanometrology Section (Australia); Casey, Phil S., E-mail: Phil.Casey@csiro.au [Commonwealth Scientific and Industrial Research Organisation, Manufacturing Flagship (Australia); Angel, Brad [Commonwealth Scientific and Industrial Research Organisation, Land and Water Flagship (Australia); Catchpoole, Heather J. [National Measurement Institute Australia, Nanometrology Section (Australia); Waddington, Lynne [Commonwealth Scientific and Industrial Research Organisation, Manufacturing Flagship (Australia); McCall, Maxine J. [Commonwealth Scientific and Industrial Research Organisation, Food and Nutrition Flagship (Australia)

    2015-02-15

    Given the broad commercial applications for ZnO nanomaterials, accurate attribution of physicochemical characteristics that induce toxic effects is particularly important. We report on the physicochemical properties of three commercial nano-ZnO products: Z-COTE and Z-COTE HP1 from BASF, and Nanosun from Micronisers, and, for reference, “bulk” ZnO from Sigma-Aldrich. Z-COTE, Nanosun and “bulk” consist of uncoated particles with different sizes, while Z-COTE HP1 consists of nanoparticles with a hydrophobic coating. Specific batches of these ZnO products were included in the OECD Sponsorship Programme to test manufactured nanomaterials. In order to identify properties potentially susceptible to variations between production runs, three additional batches of Z-COTE and Nanosun and two additional batches of Z-COTE HP1 were also investigated here. In general, all products showed little variation between batches for properties measured from powdered samples, but batch variations in the amount of surface coating were evident for the coated Z-COTE HP1. Properties measured with samples dispersed in liquids (agglomeration, photocatalytic activity, dissolution) were highly dependent on dispersion protocols, and this made it difficult to differentiate between differences due to dispersion and due to batches. However, batch-sensitive properties did appear to be present in Z-COTE and Z-COTE HP1 (photocatalytic activity), and Nanosun (dissolution). Intra-batch time and/or storage-dependent changes in the applied surface coating, noted specifically for the OECD batch of Z-COTE HP1, highlight the need for best practice when storing and accessing stocks of nano products. Awareness of inter-batch and intra-batch variability is essential for commercial applications and for nanotoxicological studies aimed at identifying links between physicochemical properties and any adverse effects in biological systems.

  9. Opportunities and challenges at the interface between petrochemicals and refinery. The OMV view

    Energy Technology Data Exchange (ETDEWEB)

    Lichtscheidl, J. [OMV Refining and Marketing GmbH, Vienna (Austria)

    2007-07-01

    OMV's refineries have been integrated into petrochemicals since the first steam cracker came on line in 1970. The refineries in Schwechat, Burghausen and Romania, especially Arpechim, have significant petrochemical capacities. In 1998 PCD was merged with Borealis, a leading producer of high grade polymers. OMV's initial 25% stake in Borealis increased to 36 in 2007. The last years have seen major investments in Schwechat and Burghausen: Schwechat's cracker was expanded by approximately 150 KTA to a nominal 500 KTA of ethylene. And in Burghausen the revamp of the cracker has been combined with a metathesis unit in order to feed a new 330 KTA polypropylene plant. The polymer market is still growing. However, the bulk of investments to increase capacity are located in the Middle East and in the Asia-Pacific region, predominately in China. As more and more products from these regions find their way to Europe, the European petrochemicals industry faces fierce competition. The response is restructuring: the creation of Arkema (Total), the takeover of BP's petrochemical assets by INEOS, the disposal of Shell-BASF subsidiary Basell to Haldia Petrochemical and Accent Industries, and the transfer of Statoil's interest in Borealis to IPIC and OMV. And most recently, Basell's acquisition of Lyondell. Compared with competitors in the Middle East and the Asia-Pacific region, producers in Europe are burdened with serious disadvantages: fairly old, small units and high costs of labor, energy and raw materials. There is no single solution. OMV, however, will continue to follow the strategies that have been successful so far: - Ever closer integration of refining and petrochemicals; - Capturing market opportunities for profitable growth; -Remaining market orientated. (orig.)

  10. Signum, a new fungicide for control of leaf diseases in outdoor vegetables.

    Science.gov (United States)

    Callens, D; Sarrazyn, R; Evens, W

    2005-01-01

    During three years, the new fungicide Signum, containing 6.7% pyraclostrobine + 26.7 % boscalid and developed by BASF. has been evaluated in leek, carrots and cabbages in several outdoor field experiments under practical conditions and during one year in outdoor lettuce. In leek, Phytophthora porri is one of the major leaf diseases causing lesions on differ ent places on the leaves, resulting in at least extra labour costs for trimming or even worse sometimes resulting in complete crop loss. So far, crop protection consists of repeated applications of fungicides especially during autumn and winter. Pyraclostrobin + boscalid has been evaluated in comparison with the fungicides mancozeb, mancozeb + metalaxyl-M and azoxystrobin. The progress of the disease during the growth season is discussed. For all parameters evaluated, pyraclostrobin + boscalid gave comparable or even better results than reference products. Especially during 2003, a small drop of the activity of benalaxyl against P. porri has been observed after repeated applications. In carrots, Erisiphe heraclei and Alternaria dauci are both the most common leaf diseases causing yield and quality loss. During periods of very high pressure of A. dauci, pyraclostrobin + boscalid, applied in a three weeks interval, revealed a superior activity compared with triazole references or compared with azoxystrobin. Against E. heraclei, a good control but also a clear dose response activity have been observed with pyraclostrobin + boscalid. Yield gain was approximately 30 ton /ha compared wih untreated. In Brussels sprouts, good efficacy was obtained against Mycosphaerella spp., Albugo candida and Alternaria spp. In outdoor lettuce Botrytis cinerea and Sclerotinia sclerotiorum are the most important diseases causing crop damage and reducing the quality of the heads. Pyraclostrobin + boscalid was evaluated in comparison with the standard fungicide iprodione. The plant protection was better with the new fungicide

  11. Introducing of chrome less protection technology for hot dip galvanized and plasticised sheet in cold mill A.D. plant mill in Skopje

    International Nuclear Information System (INIS)

    Panovska, Liljana; Arsovski, Angel; Sekuloski, Predrag

    2003-01-01

    From the experiences of many well known companies, but also having in mind the legislative of the European Union about the direction which will take in the future and using our own experiences we have come to a conclusion that the process of substitution compounds in which the chromium is found in a shape of its hexavalent ion, as an imperative, as for better environmental protection, so far accomplishing economic effects, and improvement of the products. In other words, we have in plan to make changes in the existing technology for passivation of the galvanized coils and the preparation of the pre-painted coils before the process of applying primer, by ejecting chromate compounds in which chromium is hexavalent and its substitution with non-harmful compounds. Also we predict substitution of the standard chromate primer with universal chromate-free primer. There are planned laboratory experiments in some of the institutes of the companies, which manufacture chemical products of this type (Henkel, BASF, Akzo Nobel and others) as well as semi-industrial and industrial trials at our plant. In the frame of this project the focus will be in a direction of inventing pigments that do not contain strontium chromate that will provide best correlative characteristics in a function of the quality of the pre-painted product. Introducing a green label on the products will mean direct ecological influences (no need of an expensive procedures for reduction and refining) on the environment. Putting out of use the means, which contain hexavalent chromium gives benefits in the possibility of finding sophisticated buyers (manufactures of house-holding products and their decoration) as well as more aggressive marketing appearance on the West European market. (Original)

  12. A comparative study of the physical and chemical properties of nano-sized ZnO particles from multiple batches of three commercial products

    Science.gov (United States)

    Yin, Hong; Coleman, Victoria A.; Casey, Phil S.; Angel, Brad; Catchpoole, Heather J.; Waddington, Lynne; McCall, Maxine J.

    2015-02-01

    Given the broad commercial applications for ZnO nanomaterials, accurate attribution of physicochemical characteristics that induce toxic effects is particularly important. We report on the physicochemical properties of three commercial nano-ZnO products: Z-COTE and Z-COTE HP1 from BASF, and Nanosun from Micronisers, and, for reference, "bulk" ZnO from Sigma-Aldrich. Z-COTE, Nanosun and "bulk" consist of uncoated particles with different sizes, while Z-COTE HP1 consists of nanoparticles with a hydrophobic coating. Specific batches of these ZnO products were included in the OECD Sponsorship Programme to test manufactured nanomaterials. In order to identify properties potentially susceptible to variations between production runs, three additional batches of Z-COTE and Nanosun and two additional batches of Z-COTE HP1 were also investigated here. In general, all products showed little variation between batches for properties measured from powdered samples, but batch variations in the amount of surface coating were evident for the coated Z-COTE HP1. Properties measured with samples dispersed in liquids (agglomeration, photocatalytic activity, dissolution) were highly dependent on dispersion protocols, and this made it difficult to differentiate between differences due to dispersion and due to batches. However, batch-sensitive properties did appear to be present in Z-COTE and Z-COTE HP1 (photocatalytic activity), and Nanosun (dissolution). Intra-batch time and/or storage-dependent changes in the applied surface coating, noted specifically for the OECD batch of Z-COTE HP1, highlight the need for best practice when storing and accessing stocks of nano products. Awareness of inter-batch and intra-batch variability is essential for commercial applications and for nanotoxicological studies aimed at identifying links between physicochemical properties and any adverse effects in biological systems.

  13. Terrestrial exposure and effects of Headline AMP(®) Fungicide on amphibians.

    Science.gov (United States)

    Cusaac, J Patrick W; Mimbs, William H; Belden, Jason B; Smith, Loren M; McMurry, Scott T

    2015-08-01

    Recent studies have demonstrated that a pyraclostrobin-containing fungicide (Headline(®) Fungicide--Headline(®) Fungicide and Headline AMP(®) Fungicide are registered trademarks of BASF) is toxic to amphibians at environmentally relevant concentrations. However, these studies were performed in a laboratory setting of a worst-case direct exposure in clean media. Interception of spray by the crop canopy and ground cover used by animals for security cover will influence exposure. Thus, risk to amphibians is unclear in an environmentally realistic field environment. We tested exposure and toxicity of Headline AMP(®) Fungicide to amphibians in multiple agricultural habitat scenarios (e.g., within treated crop vs. grassy areas adjacent to crop) and at two rates during routine aerial application. Specifically, we placed Woodhouse's toads (Bufo woodhousii) and Blanchard's cricket frogs (Acris blanchardi) in enclosures located within treated and untreated corn (VT stage, approximate height = 3 m), and in the potential drift area (adjacent to treated corn) during aerial application of Headline AMP Fungicide at either 731 or 1052 ml/ha (70 and 100 % the maximum application rate in corn, respectively). Mean concentrations of pyraclostrobin measured at ground level were ≤19 % of nominal application rate in all areas. Overall, mean mortality of recovered individuals of both species was ≤15 %, and mortality within Headline AMP Fungicide-treated corn (where risk was anticipated to be highest) was <10 %. It is important to understand that application timing, interception by the crop canopy (which varies both within and between crop systems), and timing of amphibian presence in the crop field influences risk of exposure and effects; however, our results demonstrate that amphibians inhabiting VT stage corn during routine aerial application of Headline AMP Fungicide are at low risk for acute mortality, matching existing laboratory results from acute toxicity studies of

  14. The EpiOcular Eye Irritation Test (EIT) for hazard identification and labelling of eye irritating chemicals: protocol optimisation for solid materials and the results after extended shipment.

    Science.gov (United States)

    Kaluzhny, Yulia; Kandárová, Helena; Handa, Yuki; DeLuca, Jane; Truong, Thoa; Hunter, Amy; Kearney, Paul; d'Argembeau-Thornton, Laurence; Klausner, Mitchell

    2015-05-01

    The 7th Amendment to the EU Cosmetics Directive and the EU REACH Regulation have reinforced the need for in vitro ocular test methods. Validated in vitro ocular toxicity tests that can predict the human response to chemicals, cosmetics and other consumer products are required for the safety assessment of materials that intentionally, or inadvertently, come into contact with the eye. The EpiOcular Eye Irritation Test (EIT), which uses the normal human cell-based EpiOcular™ tissue model, was developed to address this need. The EpiOcular-EIT is able to discriminate, with high sensitivity and accuracy, between ocular irritant/corrosive materials and those that require no labelling. Although the original EpiOcular-EIT protocol was successfully pre-validated in an international, multicentre study sponsored by COLIPA (the predecessor to Cosmetics Europe), data from two larger studies (the EURL ECVAM-COLIPA validation study and an independent in-house validation at BASF SE) resulted in a sensitivity for the protocol for solids that was below the acceptance criteria set by the Validation Management Group (VMG) for eye irritation, and indicated the need for improvement of the assay's sensitivity for solids. By increasing the exposure time for solid materials from 90 minutes to 6 hours, the optimised EpiOcular-EIT protocol achieved 100% sensitivity, 68.4% specificity and 84.6% accuracy, thereby meeting all the acceptance criteria set by the VMG. In addition, to satisfy the needs of Japan and the Pacific region, the EpiOcular-EIT method was evaluated for its performance after extended shipment and storage of the tissues (4-5 days), and it was confirmed that the assay performs with similar levels of sensitivity, specificity and reproducibility in these circumstances. 2015 FRAME.

  15. Optimization of compositions of multicomponent fine-grained fiber concretes modified at different scale levels.

    Directory of Open Access Journals (Sweden)

    NIZINA Tatyana Anatolevna,

    2017-04-01

    Full Text Available The paper deals with perspectives of modification of cement composites at different scale levels (nano-, micro-, macro-. Main types of micro- and nanomodifiers used in modern concrete technology are presented. Advantages of fullerene particles applied in nanomodification of cement concretes have been shown. Use of complex modifiers based on dispersed fibers, mineral additives and nanoparticles is proposed. These are the basic components of the fiber fine-grained concretes: cement of class CEM I 42,5R produced by JSC «Mordovcement», river sand of Novostepanovskogo quarry (Smolny settlement, Ichalkovsky district, Republic of Mordovia, densified condensed microsilica (DCM-85 produced by JSC «Kuznetskie Ferrosplavy» (Novokuznetsk, highly active metakaolin white produced by LLC «D-Meta» (Dneprodzerzhinsk, waterproofing additive in concrete mix «Penetron Admix» produced by LLC «Waterproofing materials plant «Penetron» (Ekaterinburg, polycarboxylate superplasticizer Melflux 1641 F (Construction Polymers BASF, Germany. Dispersed reinforcement of concretes was provided by injection of the fibers of three types: polypropylene multifilament fiber with cutting length of 12 mm, polyacrylonitrile synthetic fiber FibARM Fiber WВ with cutting length of 12 mm and basalt microfiber «Astroflex-MBM» modified by astralene with length about 100÷500 microns. Analysis of results of the study focused on saturated D-optimal plan was carried out by polynomial models «mixture I, mixture II, technology – properties» that considers the impact of six variable factors. Optimum fields of variation of fine-grained modified fiber concrete components have been identified by the method of experimental-statistical modeling. Polygons of distribution levels of factors of modified cement fiber concretes are constructed, that allowed tracing changes in fields of tensile in compressive strength and tensile strength in bending at age of 28 days depending on target

  16. 4-Aza-1-azoniabicyclo[2.2.2]octane–2-aminobenzoate–2-aminobenzoic acid (1/1/1

    Directory of Open Access Journals (Sweden)

    Hadi D. Arman

    2011-11-01

    Full Text Available A 4-aza-1-azoniabicyclo[2.2.2]octane cation, a 2-aminobenzoate anion and a neutral 2-aminobenzoic acid molecule comprise the asymmetric unit of the title compound, C6H13N2+·C7H6NO2−·C7H7NO2. An intramolecular N—H...O hydrogen bond occurs in the anion and in the neutral 2-aminobenzoic acid molecule. The cation provides a charge-assisted N—H...O hydrogen bond to the anion, and the 2-aminobenzoic acid molecule forms an O—H...N hydrogen bond to the unprotonated amino N atom in the cation. In this way, a three-component aggregate is formed. These are connected into a three-dimensional network by amino–carboxylate N—H...O hydrogen bonds. N—H...N hydrogen bonds are also observed.

  17. Photolysis of H2O-H2O2 Mixtures: The Destruction of H2O2

    Science.gov (United States)

    Loeffler, M. J.; Fama, M.; Baragiola, R. A.; Carlson, R. W.

    2013-01-01

    We present laboratory results on the loss of H2O2 in solid H2O + H2O2 mixtures at temperatures between 21 and 145 K initiated by UV photolysis (193 nm). Using infrared spectroscopy and microbalance gravimetry, we measured the decrease of the 3.5 micrometer infrared absorption band during UV irradiation and obtained a photodestruction cross section that varies with temperature, being lowest at 70 K. We use our results, along with our previously measured H2O2 production rates via ionizing radiation and ion energy fluxes from the spacecraft to compare H2O2 creation and destruction at icy satellites by ions from their planetary magnetosphere and from solar UV photons. We conclude that, in many cases, H2O2 is not observed on icy satellite surfaces because the H2O2 photodestruction rate is much higher than the production rate via energetic particles, effectively keeping the H2O2 infrared signature at or below the noise level.

  18. Opportunities and challenges at the interface between petrochemistry and refinery. Preprints

    Energy Technology Data Exchange (ETDEWEB)

    Ernst, S.; Leitner, W.; Lercher, J.A.; Nees, F.; Perego, C.; Rupp, M.; Santacesaria. E. (eds.)

    2007-07-01

    Within the DGMK/SCI-Conference 'Opportunities and Challenges at the Interface between Petrochemistry and refinery' between 10th and 12th October, 2007, in Hamburg (Federal Republic of Germany) the following lectures were held: (a) Maximizing petrochemicals from refineries (B. Glover, T. Foley, S. Frey); (b) Opportunities and challenges at the interface between petrochemistry and refinery - the OMV view (J. Lichtscheidl); (c) Aspects of petrochemistry in a fuels refinery (J. Essler, J. Mielicke, T. Maier); (d) Enhanced propylene production in FCC by novel catalytic materials (C.P. Kelkar, D. Harris, M. Xu, J. Fu); (e) Retrofit of an MTBE-unit to ETBE (A. Rix, U. Peters); (f) Opportunities and challenges at the interface between petrochemistry and refinery - The BASF perspectives (H.-J. Blankertz); (g) Light olefins - challenges from new production routes? (H. Zimmermann); (h) Conversion of heavy aromatic hydrocarbons to valuable synthetic feed for steamcrackers (A. Cesana, L. Dalloro, F. Rivetti, R. Buzzoni, R. Bignazzi); (i) C{sub 4} olefin/paraffin separation over the metal organic framework material Cu{sub 3}BTC{sub 2} (S. Kunz, O. Tangermann, M. Hartmann); (j) Glycerol tertiary butyl ethers via etherification of glycerol with isobutene (A. Behr); (k) Biorefineries: From concepts to reality? (K. Wagemann); (l) Modern concepts in reactor and separation technologies (D. Agar); (m) Innovative reactive distillation process for the production of the MTBE substitute isooctane from isobutene (M. Chalakova, R. Kaur, H. Freund, S. Mahajani, K. Sundmacher); (n) Supported ionic liquid phase (SILP) systems - novel fixed bed reactor concepts for homogeneous catalysis (A. Riisager, R. Fehrmann, M. Haumann, M. Jakuttis, J. Joni, P. Wasserscheid); (o) Selective oxidations to industrial intermediates (S. Schunck); (p) Perspectives of industrial realization for propane oxidative dehydrogenation over chromium oxide catalysts (A.L. Lapidus, N.A. Gaidai, Yu. A. Agafonov, M

  19. A novel self-micro-emulsifying delivery system (SMEDS) formulation significantly improves the fasting absorption of EPA and DHA from a single dose of an omega-3 ethyl ester concentrate.

    Science.gov (United States)

    Qin, Yan; Nyheim, Hilde; Haram, Else Marie; Moritz, Joseph M; Hustvedt, Svein Olaf

    2017-10-16

    Absorption of EPA and DHA from Omega-3-acid ethyl ester (EE) concentrate supplements occurs most efficiently when taken in context of a fatty meal; adequate fat intake is required to release bile salts that emulsify and pancreatic enzymes that digest omega-3-containing lipids in the intestine. Current guidelines recommend reduction in fat intake and therefore there is a need to optimize the absorption of Omega-3 in those consuming low-fat or no-fat meals. To this end, BASF has developed an Absorption Acceleration Technology, a novel self-micro-emulsifying delivery system (SMEDS) formulation of highly concentrated Omega-3-acid EE which enables rapid emulsification and microdroplet formation upon entering the aqueous environment of the gut therefore enhances the absorption. Two separate single dose, crossover studies were conducted to determine the relative bioavailability of omega-3-acid EE concentrate, either as a novel SMEDS formulation (PRF-021) or as control, in healthy fasted male and female adults at two dose levels (Study 1 "low dose": 630 mg EPA + DHA in PRF-021 vs. 840 mg EPA + DHA in control; Study 2 "high dose": 1680 mg EPA + DHA in PRF-021 vs. 3360 mg EPA + DHA in control). Blood samples were collected immediately before supplementation and at defined time intervals for 48 h. Plasma concentration of total EPA and DHA were determined for pharmacokinetic analysis, area under the curve (AUC) and maximum observed concentration (C max ) was determined. Total EPA plus DHA absorption from SMEDS formulation PRF-021 were 6.4 and 11.5 times higher compared to control in low- and high-dose studies respectively, determined as the ratio of baseline corrected, dose normalized AUC 0-24h of PRF-021 over that of control. EPA and DHA individually showed differing levels of enhancement: the AUC 0-24h ratio for EPA was 23.8 and 25.7 in low and high dose studies, respectively, and the AUC 0-24h ratio for DHA was 3.6 and 5.6 in low and high dose studies

  20. Bis(μ-biphenyl-2,2′-dicarboxylatobis[(2,2′-bipyridinecopper(II

    Directory of Open Access Journals (Sweden)

    Zhe An

    2009-04-01

    Full Text Available The title compound, [Cu2(C14H8O42(C10H8N22], was obtained by solvothermal synthesis. The CuII atom is coordinated by one chelating 2,2′-bipyridine ligand and two carboxyl groups from different biphenyl-2,2′-dicarboxylate ligands, leading to a distorted octahedral environment. Each carboxylate group makes one short Cu—O bond [1.9608 (14 and 1.9701 (14 Å] and one longer Cu—O contact [2.4338 (17 and 2.5541 (17 Å] to each CuII atom. The biphenyl-2,2′-dicarboxylate ligands bridge between CuII atoms, forming a dinuclear complex around a crystallographic inversion centre.

  1. SYNTHESIS AND STRUCTURAL CHARACTERISTICS OF BIS(CITRATEGERMANATES(IV (Hbipy2[Ge(HCit2]•2H2O AND [CuCl(bipy2]2[Ge(HCit2]•8H2O

    Directory of Open Access Journals (Sweden)

    Inna Seifullina

    2016-12-01

    Full Text Available The crystalline compounds (Hbipy2[Ge(HCit22H2O (1 and CuCl(bipy2]2[Ge(HCit2]·8H2O (2 (where H4Cit is citric acid, bipy is 2,2ʹ-bipyridine were obtained for the fi rst time and their structures were determined by the single-crystal X-ray diffraction method. Compounds were characterized by IR spectroscopy, thermogravimetric (TGA and elemental analyses. Both compounds are formed with complex bis(citrategermanate anion and protonated 2,2’-bipyridine or [Cu(bipy2Cl]+ as cations in compounds 1 and 2, respectively.

  2. synthesis and structural characterization of n-(2-{[(2e)-2-(2 ...

    African Journals Online (AJOL)

    E.J. Research Institute of Chemistry, International Center for Chemical and Biological ... Benzamide and its analogues have various application in synthesis of ..... Symmetry codes: (i) x+3/2, y+1/2, z; (ii) −x+1/2, −y+1/2, −z; (iii) x, y−1, z.

  3. Cryptand [2.2.2]quantitation in the synthesis of 2-[fluorine-18]fluoro-2-deoxy-d-glucose

    International Nuclear Information System (INIS)

    Kothari, P.J.; Ginos, J.; Finn, R.D.; Larson, S.M.; Link, J.M.; Krohn, K.A.; Garmestani, K.

    1992-01-01

    Most automated synthetic devices for the preparation of [ 18 F]2-fluoro-2-deoxy-D-glucose ([ 18 F]FDG) employ cryptand [2.2.2](4,7,13,16,21,24-hexaoxa-1,10-diazabicyclo(8.8.8)-hexacosane) to facilitate the 18 F displacement reaction. Lack of simple spectroscopic and/or chromatographic determinations for cryptands prompted our investigation with tritiated [2.2.2] cryptand reagent to determine the absolute concentration of this reagent throughout the synthetic procedure leading to the final formulation. The concentration of cryptand [2.2.2] in the final formulation has been determined to range from 0.39 μg/ml to 0.60 μg/ml which is well below the detection limit by a method recently reported. (author) 1 fig., 1 tab., 5 refs

  4. Pembuatan Biodiesel Dari Minyak Kelapa Dengan Katalis NaOH Menggunakan Gelombang Mikro (Microwave Secara Kontinyu

    Directory of Open Access Journals (Sweden)

    Daru Satria Prayanto

    2016-04-01

    Full Text Available Biodiesel merupakan bioenergi atau bahan bakar nabati yang dibuat dari minyak nabati melalui proses transesterifikasi, esterifikasi, atau proses esterifikasi-transesterifikasi. Proses pembuatan biodiesel dapat dilakukan dengan metode pemanasan konvensional maupun dengan metode pemanasan microwave. Dengan radiasi microwave, maka waktu yang dibutuhkan saat proses transesterifikasi lebih singkat dibandingkan dengan konvensional. Disisi lain, minyak kelapa memiliki potensi yang besar untuk digunakan sebagai bahan baku dalam pembuatan biodiesel karena ketersediaannya yang melimpah. Penelitian ini bertujuan untuk membuat biodiesel dari minyak kelapa secara kontinyu melalui proses transesterifikasi metanol dengan menggunakan radiasi microwave dengan katalis NaOH dan mempelajari pengaruh konsentrasi tiap katalis, daya, dan laju umpan yang digunakan terhadap yield, densitas, dan viskositas biodiesel yang dihasilkan. Dalam penelitian ini di gunakan 3 variabel, yaitu laju umpan 0,73; 1,25; 1,72 ml/s, konsentrasi katalis 0,25; 0,5; 1 (% berat variabel daya microwave 100, 264, 400, 600, dan 800 Watt. Rasio umpan ditentukan pada 1:9. Pada tahap persiapan melarutkan metanol dan katalis sesuai dengan variabel hingga tercampur homogen. Selanjutnya tahap transesterifikasi dengan mencampurkan larutan metanol (metanol dan katalis dengan minyak kelapa dengan mol ratio yang telah ditentukan dan mengatur daya microwave untuk memulai proses transesterifikasi, proses berlangsung secara kontinyu menggunakan mix flow reaktor. Selanjutnya pemisahan hasil transesterifikasi dari gliserol, dilanjutkan dengan tahap pencucian dengan aquadest untuk memisahkan impurities dan katalis yang masih tersisa dalam biodiesel kemudian memanaskan pada oven untuk menguapkan kandungan air dalam biodiesel. Selajutnya menganalisisa hasil biodiesel terhadap yield, densitas, dan viskositasnya. Hasil terbaik dari variabel yang digunakan di atas adalah pada katalis NaOH dengan konsentrasi 1

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-12-15

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-01

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

  7. PENGARUH TEMPERATUR DAN IRADIASI TERHADAP INTERDIFUSI PARTIKEL BAHAN BAKAR JENIS U−7Mo/Al

    Directory of Open Access Journals (Sweden)

    Maman Kartaman Ajiriyanto

    2016-06-01

    Full Text Available ABSTRAK PENGARUH TEMPERATUR DAN IRADIASI TERHADAP INTERDIFUSI PARTIKEL BAHAN BAKAR JENIS U−7Mo/Al. Paduan U−7Mo/Al memiliki potensi besar sebagai bahan bakar reaktor riset, tetapi bahan bakar ini memiliki beberapa kekurangan antara lain dapat membentuk interaction layer pada antarmuka pada saat proses fabrikasi maupun iradiasi di reaktor melalui mekaniame difusi. Penelitian ini dilakukan untuk mengetahui terjadinya interaction layer yang disebabkan oleh interdifusi atau diffusion couple paduan U−7Mo dengan pelat AlMg2 yang dipanaskan pada temperatur 500 °C dan 550 °C selama 24 jam dalam tungku arc furnace dan tungku DTA pada temperatur 30 °C hingga 1400 °C. Hasil pengamatan mikrostruktur menggunakan Scanning Electron Microscope (SEM pada sampel diffusion couple hasil pemanasan pada temperatur 500 °C belum terlihat adanya interaction layeratau pembentukan fasa baru antara partikel U−Mo dan matriks Al. Sementara itu, pemanasan pada temperatur 550 °C telah terjadi interdifusi paduan U−7Mo dengan pelat AlMg2 menghasilkan senyawa (U,MoAlx pada antarmuka atau interface. Hal ini didukung oleh hasil analisis DTA menunjukkan bahwa paduan U−7Mo/Al pada 500 °C mempunyai kompatibilitas panas yang baik, tetapi diatas temperatur 550 °C telah terjadi perubahan fasa a + d menjadi a + g. Pemanasan hingga 679,14 °C terjadi fasa metastabil U(Al,Mox dan selanjutnya mengalami proses interdifusi dengan leburan uranium membentuk interaction layer berupa aglomerat senyawa UAlx (UAl4, UAl3 danUAl2. Aglomerat yang terbentuk dari proses pemanasan secara diffusion couple maupun dalam tungku DTA dibandingkan dengan aglomerat yang terbentuk akibat proses iradiasi. Bahan bakar paduan U−7Mo/Al yang diradiasi dengan burn up 58% mengalami interdifusi antara U−7Mo dengan matriks Al menghasilkan fasa metastabil U(Al,Mox yang berubah menjadi layer (U,MoAl7, presipitat UMo2Al20, (UMoAl3−Al dan membentuk boundary atau aglomerat UAlx (UAl4, UAl3 danUAl2

  8. Crystallization behavior of Li2O-SiO2, Na2O-SiO2 and Na2O-CaO-SiO2 glasses; Li2O-SiO2, Na2O-SiO2, Na2O-CaO-SiO2 kei glass no kessho sekishutsu kyodo

    Energy Technology Data Exchange (ETDEWEB)

    Tsutsumi, K.; Otake, J.; Nagasaka, T.; Hino, M. [Tohoku University, Sendai (Japan)

    1998-06-01

    It has been known that crystallization of mold powder is effective on the disturbance of heat transfer between mold and solidified shell in production of middle carbon steel slabs in continuous casting process. But it has not yet been made clear which composition of mold powder is the most suitable for crystallization. The crystallization behavior of Li2O-SiO2, Na2O-SiO2 and Na2O-CaO-SiO2 glasses was observed by differential thermal analysis (DTA) and hot-thermocouple methods with DTA in the present work. As a result, addition of alkaline metal and alkaline earth metal oxides to SiO2 increased the critical cooling rate for glass formation in binary system of Li2O-SiO2 and Na2O-SiO2 and Li2O-SiO2 system crystallized easier than Na2O-SiO2 system. In ternary system of Na2O-CaO-SiO2, addition of Na2O hurried the critical cooling rate at CaO/SiO2=0.93 mass ratio, but the rate was almost constant in the composition range of more than 15 mass% Na2O. The slag of CaO/SiO2=0.93 made the rate faster than the slag of CaO/SiO2=0.47 at constant content of 10mass% Na2O. 17 refs., 10 figs., 3 tabs.

  9. Coordination polymers of scandium sulfate. Crystal structures of (H2Bipy)[Sc(H2O)(SO4)2]2·2H2O and (H2Bipy)[HSO4]2

    International Nuclear Information System (INIS)

    Petrosyants, S.P.; Ilyukhin, A.B.

    2005-01-01

    Compounds with general formula Cat x [Sc(H 2 O) z (SO 4 ) y ]·nH 2 O (Cat=NH 4 , H 2 Bipy (Bipy - 4,4'-bipyridine), HEdp (Edp - ethylene dipyridine)) identified on element analysis data and IR spectra are synthesized. X-ray diffraction analysis of (H 2 Bipy)[Sc(H 2 O)(SO 4 ) 2 ] 2 ·2H 2 O shows that in structure of the compound chains of ScO 6 octahedron and SO 4 tetrahedrons are joined in bands by tridentate coordination of sulfate ions. Bands form skeleton in endless emptiness of which there are H 2 Bipy 2+ cations [ru

  10. Excitation mechanisms of 2s1/2-2p3/2 and 2p1/2-2p3/2 transitions in U82+ through U89+

    International Nuclear Information System (INIS)

    Decaux, V.; Beiersdorfer, P.; Osterheld, A.

    1994-01-01

    A model based on detailed calculations of the electron-impact excitation of n = 2 electrons in the Li- to Ne-like uranium ions was developed to interpret and explain measurements on EBIT (Electron Beam Ion Trap). While only considering the direct excitation process provided a good model for the electric dipole (El) transitions, it was necessary for the magnetic dipole (Ml) spectrum to include various additional excitation processes in the model. In particular, the model was expanded to include electron-impact excitation of n = 3 levels followed by radiative cascades. Moreover, excitation by the ionization of 2s 1/2 , 2p 1/2 , and 2p 3/2 electrons and by radiative capture of beam electrons into excited levels was added. The new model demonstrates that the dipole-forbidden lines are almost exclusively produced by indirect excitation processes

  11. Selective fluorescence quenching of 2,3-diazabicyclo[2.2.2]oct-2-ene by nucleotides.

    Science.gov (United States)

    Marquez, Cesar; Pischel, Uwe; Nau, Werner M

    2003-10-16

    [reaction: see text] The fluorescence quenching of 2,3-diazabicyclo[2.2.2]oct-2-ene (DBO) by nucleotides has been studied. The quenching mechanism was analyzed on the basis of deuterium isotope effects, tendencies for exciplex formation, and the quenching efficiency in the presence of a molecular container (cucurbit[7]uril). Exciplex-induced quenching appears to prevail for adenosine, cytidine, and uridine, while hydrogen abstraction becomes competitive for thymidine and guanosine. Compared to other fluorescent probes, DBO responds very selectively to the type of nucleotide.

  12. A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido

    Energy Technology Data Exchange (ETDEWEB)

    Allday, C. [United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)

    1963-10-15

    enriquecido tambien se puede utilizar como combustible oxido de uranio natural enriquecido con plutonio. En la memoria se resume la experiencia adquirida en la produccion de combustible de oxido para el AGR y en la explotacion del reactor y los planes para la regeneracion del combustible. Se examina la posibilidad de utilizar combustible de plutonio y se analizan las consecuencias que tendria su adopcion sobre los costos y el ciclo del combustible. Por ultimo, se destaca la importancia de los reactores Magnox y AGR en el programa energetico del Reino Unido. (author) [Russian] a ) Prirodnyj uran/topdivnyj tsikl ''Magnoks''. Soedinennoe Kor olevstvo izb ralo reaktor na prirodnom urane s grafitovym zam edli tel em i gazovy m okhlazhdeniem v kachestve osnovy programmy po yadernoj ehnergii. Ono ehkspluatirovalo ehti reaktory v Kolder-Kholle i Chepelkrosse v techenie semi det; reaktory v Berkli i Braduehlle v nastoyashchee vremya nakhodyatsya v stadii ehkspluatatsii, a reaktory v semi drugikh mestakh v stadii stroitel'stva ili planirovaniya. Toplivo dlya ehtikh reaktorov proizvoditsya na zavode v Springfilde i zatem perevozitsya dlya zagruzki k mestopolozheniyu reaktora. Posle oblucheniya i razgruzki toplivo transportiruetsya na zavod v Uindskejl dlya otdeleniya urana i plutoniya ot produktov deleniya. Daetsya opisanie opyta CK v oblasti konstruktsii i proizvodstva toplivnykh ehlementov, ehkspluatatsii reaktora, transportirovki obluchennogo topliva i posleduyushchej obrabotki topliva. Upominaetsya o povedenii topliva v reaktore i ob al'ternativnykh programmakh zagruzki l razgruzki toplivnykh ehlementov; ehta tema razrabatyvaetsya v drugikh trudakh. b) Reaktory, ispol'zuyushchie obogashchennoe toplivo. Soedinennoe Korolevstvo razrabatyvaet usovershenstvovannyj reaktors gazovym okhlazhdeniem AGE, prototip kotorogo voshel v stroj v 1963 godu. Toplivo proizvoditsya iz obogashchennoj okisi urana, zaklyuchennoj v obolochku iz nerzhaveyushchej stali, i Sudet pererabatyvat'sya posredstvom

  13. PODAAC-OSCT2-L2BV2

    Data.gov (United States)

    National Aeronautics and Space Administration — This dataset consists of the version 2 Level 2B science-quality ocean surface wind vector retrievals from the Oceansat-2 scatterometer (OSCAT), which was designed...

  14. Synthesis, Structure, Bonding, and Reactivity of Metal Complexes Comprising Diborane(4) and Diborene(2): [{Cp*Mo(CO)2 }2 {μ-η22 -B2 H4 }] and [{Cp*M(CO)2 }2 B2 H2 M(CO)4 ], M=Mo,W.

    Science.gov (United States)

    Mondal, Bijan; Bag, Ranjit; Ghorai, Sagar; Bakthavachalam, K; Jemmis, Eluvathingal D; Ghosh, Sundargopal

    2018-04-26

    The reaction of [(Cp*Mo) 2 (μ-Cl) 2 B 2 H 6 ] (1) with CO at room temperature led to the formation of the highly fluxional species [{Cp*Mo(CO) 2 } 2 {μ-η 22 -B 2 H 4 }] (2). Compound 2, to the best of our knowledge, is the first example of a bimetallic diborane(4) conforming to a singly bridged C s structure. Theoretical studies show that 2 mimics the Cotton dimolybdenum-alkyne complex [{CpMo(CO) 2 } 2 C 2 H 2 ]. In an attempt to replace two hydrogen atoms of diborane(4) in 2 with a 2e [W(CO) 4 ] fragment, [{Cp*Mo(CO) 2 } 2 B 2 H 2 W(CO) 4 ] (3) was isolated upon treatment with [W(CO) 5 ⋅thf]. Compound 3 shows the intriguing presence of [B 2 H 2 ] with a short B-B length of 1.624(4) Å. We isolated the tungsten analogues of 3, [{Cp*W(CO) 2 } 2 B 2 H 2 W(CO) 4 ] (4) and [{Cp*W(CO) 2 } 2 B 2 H 2 Mo(CO) 4 ] (5), which provided direct proof of the existence of the tungsten analogue of 2. © 2018 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

  15. Structures of nitrato-(2-hydroxybenzaldehydo) (2,2 Prime -bipyridyl)copper and nitrato-(2-hydroxy-5-nitrobenzaldehydo)(2,2 Prime -bipyridyl)copper

    Energy Technology Data Exchange (ETDEWEB)

    Chumakov, Yu. M. [Academy of Sciences of Moldova, Institute of Applied Physics (Moldova, Republic of); Paladi, L. G. [Moldova State University (Moldova, Republic of); Antosyak, B. Ya.; Simonov, Yu. A. [Academy of Sciences of Moldova, Institute of Applied Physics (Moldova, Republic of); Tsapkov, V. I., E-mail: vtsapkov@gmail.com [Moldova State University (Moldova, Republic of); Bocelli, G. [Institute of Materials for Electronics and Magnetism (Italy); Gulea, A. P. [Moldova State University (Moldova, Republic of); Ginju, D. [Alexandru Ioan Cuza University of Iasi (Romania); Palomares-Sanchez, S. A. [Autonomous University of San Luis Potosi (Mexico)

    2011-03-15

    Nitrato-(2-hydroxy-5-nitrobenzaldehydo)(2,2 Prime -bipyridyl)copper (I) and nitrato-(2-hydroxybenzaldehydo)(2,2 Prime -bipyridyl)copper (II) were synthesized and characterized by X-ray diffraction. The coordination polyhedron of the central copper atom in complex I can be described as a distorted tetragonal pyramid whose base is formed by the phenol and carbonyl oxygen atoms of the monodeprotonated 2-hydroxy-5nitrobenzaldehyde molecule and the nitrogen atoms of the 2,2 Prime -bipyridyl ligand and whose apex is occupied by the oxygen atom of the nitrato group. In the crystal structure, complexes I are linked by the acido ligands and the NO{sub 2} groups of the aldehyde molecule into infinite chains. In complex II, the central copper atom is coordinated by 2-hydroxybenzaldehyde, 2,2 Prime -bipyridyl, and the nitrato group, resulting in the formation of centrosymmetric dimers. The coordination polyhedron of the central copper atom can be described as a bipyramid (4 + 1 + 1) with the same base as in complex I. The axial vertices of the bipyramid are occupied by the oxygen atom of the nitrato group and the bridging phenol oxygen atom of the adjacent complex related to the initial complex by a center of symmetry. In the crystal structure, complexes II are hydrogen bonded into infinite chains.

  16. Micropore Formation of [Zn2(Oxac) (Taz)2]·(H2O)2.5 via CO2 Adsorption.

    Science.gov (United States)

    Zubir, Moondra; Hamasaki, Atom; Iiyama, Taku; Ohta, Akira; Ohki, Hiroshi; Ozeki, Sumio

    2017-01-24

    As-synthesized [Zn 2 (Oxac) (Taz) 2 ]·(H 2 O) 2.5 , referred to as ZOTW 2.5 , was prepared from aqueous methanol solutions of Zn 5 (CO 3 ) 2 (OH) 6 and two kinds of ligands of 1,2,4-triazole (Taz) and oxalic acid (Oxac) at 453 K for 12 h. The crystal structure was determined by the Rietveld method. As-synthesized ZOTW 2.5 was pretreated at 383 K and 1 mPa for t pt h, ZOTW x (t pt h). ZOTW x (≥3h) showed a type I adsorption isotherm for N 2 at 77 K having a saturation amount (V s ) of 180 mg/g, but that pretreated shortly showed only 1/10 in V s . CO 2 was adsorbed at 303 K in sigmoid on nonporous ZOTW x (≤2h) and in Langmuir-type on ZOTW x (≥3h) to reach the adsorption amount of 120 mg/g at 700 Torr. N 2 adsorption on ZOTW x (≤2h)deCO 2 , degassed after CO 2 adsorption on ZOTW x (≤2h), was promoted 5-fold from 180 mg/g on ZOTW x (t pt h) and ZOTW x (≥3h)deCO 2 up to ca. 1000 mg/g. The interaction of CO 2 and H 2 O molecules in micropores may lead to a new route for micropore formation.

  17. Synthesis and crystal structures of new complexes of Np(V) glycolate with 2,2'-bipyridine, [NpO2(C10H8N2)(OOC2H2OH)].1.5H2O and [NpO2(C10H8N2)(OOC2H2OH)].2.5H2O

    International Nuclear Information System (INIS)

    Charushnikova, I.A.; Krot, N.N.; Starikova, Z.A.

    2009-01-01

    Single crystals were prepared, and the structures of two complexes of Np(V) glycolate with 2,2'-bipyridine of the compositions [NpO 2 (C 10 H 8 N 2 )(OOC 2 H 2 OH)].1.5H 2 O (I) and [NpO 2 (C 10 H 8 N 2 )(OOC 2 H 2 OH)]2.5H 2 O (II) were studied. The structures of the compounds are based on neptunyl-glycolate chains in which the glycolate anion manifests its complexation ability in different manner. In structure I, the bidentate-bridging anion links the adjacent NpO 2 - cations through the oxygen atoms of the carboxylate group. The neptunyl-glycolate chains of I exhibits the mutual coordination of the NpO 2 - cations acting toward each other simultaneously as ligands and coordinating centers. In compound II, the glycolate anion is bidentately coordinated to one neptunium atom to form a planar five-membered metallocycle [NpOCCO]. The O atom external with respect to the metallocycle is in the coordination environment of the adjacent neptunyl. The nitrogen-containing molecular ligand Bipy is included into the coordination environment of Np. The coordination polyhedron of the Np atoms in both structures is a pentagonal bipyramid in which the average Np-N bond length is 2.666 Aa (I) and 2.596 Aa (II). (orig.)

  18. Enatioselective[2+2+2] Cycloaddition as A Synthetic Tool

    Institute of Scientific and Technical Information of China (English)

    T.Shibata; S.Yoshida; M.Otsuka; Y.Arai; K.Endo

    2007-01-01

    1 Results Transition metal-catalyzed [2+2+2] cycloaddition is one of the most efficient protocols for the construction of six-membered ring system.Our group has comprehensively studied various types of highly enantioselective [2+2+2] cycloaddition for the synthesis of chiral cycloadducts; we already reported an iridium-catalyzed intermolecular [2+2+2] cycloaddition between α,ω-diynes,having various tethers and substituents on the alkyne termini,and monoalkynes,possessing oxygen or/and nitrogen functiona...

  19. Solvent extraction of Ca2+, Ba2+, Cu2+, Zn2+, Cd2+, Pb2+, UO22+, Mn2+, Co2+ and Ni2+ into nitrobenzene using strontium dicarbol-lylcobaltate and tetra-tert-butyl p-tert-butylcalix[4]arene tetraacetate

    Directory of Open Access Journals (Sweden)

    E. MAKRLÍK

    2008-12-01

    Full Text Available The exchange extraction constants corresponding to the general equilibrium M2+(aq + SrL2+(nb D ML2+ (nb + Sr2+ (aq occurring in the two-phase water–nitrobenzene system (M2+ = Ca2+, Ba2+, Cu2+, Zn2+, Cd2+, Pb2+, UO22+, Mn2+, Co2+ or Ni2+; L = tetra-tert-butyl p-tert-butylcalix[4]arene tetraacetate; aq = aqueous phase; nb = nitrobenzene phase were evaluated from extraction experiments and -activity measurements. Furthermore, the stability constants of the ML2+ complexes in water saturated nitrobenzene were calculated; they were found to increase in the cation order Ba2+ < Mn2+ < Pb2+, Co2+ < Cu2+, Zn2+ < Cd2+, Ni2+ < UO22+ < Ca2+.

  20. Reactions of R(2)P-P(SiMe(3))Li with [(R'(3)P)(2)PtCl(2)]. A general and efficient entry to phosphanylphosphinidene complexes of platinum. Syntheses and structures of [(eta(2)-P=(i)Pr(2))Pt(p-Tol(3)P)(2)], [(eta(2)-P=(t)Bu(2))Pt(p-Tol(3)P)(2)], [{eta(2)-P=(N(i)Pr(2))(2)}Pt(p-Tol(3)P)(2)] and [{(Et(2)PhP)(2)Pt}(2)P(2)].

    Science.gov (United States)

    Domańska-Babul, Wioleta; Chojnacki, Jaroslaw; Matern, Eberhard; Pikies, Jerzy

    2009-01-07

    The reactions of lithium derivatives of diphosphanes R(2)P-P(SiMe(3))Li (R = (t)Bu, (i)Pr, Et(2)N and (i)Pr(2)N) with [(R'(3)P)(2)PtCl(2)] (R'(3)P = Et(3)P, Et(2)PhP, EtPh(2)P and p-Tol(3)P) proceed in a facile manner to afford side-on bonded phosphanylphosphinidene complexes of platinum [(eta(2)-P=R(2))Pt(PR'(3))(2)]. The related reactions of Ph(2)P-P(SiMe(3))Li with [(R'(3)P)(2)PtCl(2)] did not yield [(eta(2)-P=PPh(2))Pt(PR'(3))(2)] and resulted mainly in the formation of [{(R'(3)P)(2)Pt}(2)P(2)], Ph(2)P-PLi-PPh(2), (Me(3)Si)(2)PLi and (Me(3)Si)(3)P. Crystallographic data are reported for the compounds [(eta(2)-P=R(2))Pt(p-Tol(3)P)(2)] (R = (t)Bu, (i)Pr, ((i)Pr(2)N)(2)P) and for [{(Et(2)PhP)(2)Pt}(2)P(2)].