Waste incineration on its way to the power plants; Muellverbrennung auf dem Weg zum Kraftwerk

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Reich, J. [STEAG encotec GmbH, Essen (Germany); Neukirchen, B. [STEAG AG, Essen (Germany)

2004-07-01

Looking at the year 2005 and the end of disposal of untreated domestic waste the politic hopes that the prognosticated lack of waste treatment capacity is remedied by coal-fired power plants. The classical municipal waste incinerators by contrast want to get recognition as energetic recycler in comparison with power stations. The decision of the European Court of Justice concerning recycling and disposal of domestic waste by incineration has started the discussion and competition on fuel-rich commercial waste. Are municipal waste incineration plants power stations or must power plants be regarded as incinerators? These questions are still open. (orig.) [German] Mit Blick auf das Jahr 2005 und das Ende der Ablagerung von unbehandeltem Siedlungsabfall hofft die Politik, dass der prognostizierte Mangel an Vorbehandlungskapazitaeten von den Kohlekraftwerken behoben wird. Die klassischen Muellverbrennungsanlagen wollen dagegen mit dem Kraftwerksvergleich die Anerkennung als energetische Verwerter erreichen. Das EuGH-Urteil zur Verwertung oder Beseitigung von Siedlungsabfall durch Verbrennen hat in diesem Jahr die Diskussion und den Kampf um den heizwertreichen Gewerbeabfall angeheizt. Die Frage, wie weit in Zukunft die Muellverbrennungsanlagen als Kraftwerke, aber auch die Kraftwerke als Muellverbrennungsanlagen angesehen werden muessen, ist noch offen. (orig.)

Modern control systems in the combined-cycle power plant `Salinenstrasse` of Stadtwerke Schwaebisch Hall GmbH; Einsatz moderner Kraftwerksleittechnik im GuD-Kraftwerk Salinenstrasse der Stadtwerke Schwaebisch Hall GmbH

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Breuning, P [Stadtwerke Schwaebisch Hall GmbH (Germany); Menschel, M [Stadtwerke Schwaebisch Hall GmbH (Germany); Friedrich, G [IDS Gesellschaft fuer Informations-, Datenuebertragungs- und Steuerungssysteme mbH, Karlsruhe (Germany); Radtke, W [IDS Gesellschaft fuer Informations-, Datenuebertragungs- und Steuerungssysteme mbH, Karlsruhe (Germany)

1994-11-14

Run-of-river power plants, CHP systems and heating power stations produce much of the heat and power consumed in the supply area of the Stadtwerke Schwaebisch Hall. The most recent component is a modern combined-cycle power station based on a reconstructed steam power plant commissioned in 1935. Modern control systems supplied by IDS Karlsruhe ensure optimal grid and power plant operation. (orig.) [Deutsch] Laufwasser-Kraftwerke, BHKW und Heizkraftwerke decken einen grossen Teil des Bedarfs an Waerme und Energie im Versorgungsgebiet der Stadtwerke Schwaebisch Hall. Vor kurzem ist hier als weitere Komponente ein modernes GuD-Kraftwerk in Betrieb genommen worden. Um ein bestehendes, bereits 1935 erbautes Dampfkraftwerk wirtschaftlicher nutzen zu koennen, haben die Stadtwerke Schwaebisch Hall den Umbau zum GuD-Kraftwerk vorgenommen. Durch den Einsatz der von IDS Karlsruhe gelieferten Kraftwerksleittechnik, verbunden mit einem modernen Netzleitsystem wird eine optimale Netz- und Kraftwerksfuehrung ermoeglicht. (orig.)

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

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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.

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

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

1981-12-15

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

Virtual power plants in energy industry law. Possible manifestations and from them resulting legal questions; Virtuelle Kraftwerke im Energiewirtschaftsrecht. Moegliche Erscheinungsformen und daraus resultierende Rechtsfragen

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Kahlbrandt, Lea Katharina [Bucerius Law School, Hamburg (Germany)

2017-08-15

Although cogeneration plants are operated with fossil fuels are not quite as environmentally friendly as EEG systems they have a much more favorable effect due to their high efficiency climate as conventional power plants. In the future this could can even improve with the aid of fuel cell technology. Therefore, they play for the transition to a safe and secure more efficient power supply conditions for a merger of cogeneration plants overall favorable, in particular because that no influence on the or the emission trading obligation of the plant operators has. However, the complete elimination of avoided network charges could be counterproductive. Just virtual power plants of cogeneration plants have an effect on a feed-in that the grid not charged, so fees for a decentralized feed in these cases can be justified. Also the development of cogeneration development within the framework of the newly introduced calls will have a major impact on the development of virtual power stations. [German] Zwar sind KWK-Anlagen, die mit fossilen Brennstoffen betrieben werden, nicht ganz so umweltfreundlich wie EEG-Anlagen, doch haben sie aufgrund ihres hohen Wirkungsgrades eine viel guenstigere Klimabilanz als konventionelle Kraftwerke. In Zukunft koennte diese sich mithilfe der Brennstoffzellen-Technologie sogar noch verbessern. Daher spielen sie fuer den Uebergang zu einer sicheren und klimafreundlicheren Stromversorgung eine wichtige Rolle. Die Bedingungen fuer einen Zusammenschluss von KWK-Anlagen sind insgesamt guenstig, insbesondere weil jener keinen Einfluss auf die Foerdersaetze oder die Emissionshandelspflicht der Anlagenbetreiber hat. Allerdings koennte die vollstaendige Abschaffung vermiedener Netzentgelte kontraproduktiv sein. Gerade virtuelle Kraftwerke aus KWK-Anlagen wirken auf eine Einspeisung hin, die das Netz nicht ueberfordert, sodass Entgelte fuer eine dezentrale Einspeisung in diesen Faellen durchaus eine Rechtfertigung haben. Auch die Entwicklung des KWK

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

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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

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

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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

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

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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

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

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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

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

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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

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

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

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

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Sri Kuntjoro

2015-04-01

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

The trans-unit operation management system of VEAG AG`s power plant in Jaenschwalde; Das werksuebergreifende Betriebsmanagementsystem im Kraftwerk Jaenschwalde der VEAG AG

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Weidich, H.; Platzke, R.

1997-12-31

Jaenschwalde coal power plant consists of 3 so-called ``modules`` of 2 power blocks each. The new operation management system at Jaenschwalde power plant has greatly improved the temporal availability and quality of process data needed by its various departments. The possibilities of process data analysis and the various optional extensions are capable of integration in various ways and at reasonable cost. At present the operation management system is managed by two employees. As the job does not even fully occupy these two, they are available for other work as well. In earlier times there were instead 6 process computers whose operation and maintenance occupied 30 employees. Beside these tremendous savings in labour the system has also brought about great functional improvements in terms of the supply of process data for the power plant as a whole and also for the entire VEAG network. [Deutsch] Das Braunkohlekraftwerk Jaenschwalde besteht aus insgesamt 6 Kraftwerksbloecken, von denen jeweils 2 Kraftwerksbloecke sogenannte `Module` bilden. Die zeitliche Verfuegbarkeit und die Guete der von den Fachabteilungen benoetigten Prozessdaten ist durch das neue Betriebsmanagementsystem im Kraftwerk Jaenschwalde drastisch erhoeht worden. Die Moeglichkeiten der Prozessdatenanalyse und die individuellen Erweiterungen sind vielseitig und mit einem ueberschaubaren Aufwand integrierbar. Die Pflege des gesamten heutigen Betriebsmanagementsystems wird heute von 2 Personen durchgefuehrt, die nicht einmal 100% ihrer Arbeitszeit dafuer aufzuwenden haben, so dass sie noch Aufgaben aus anderen Bereichen erledigen koennen. Frueher wurden dagegen 30 Personen fuer die Pflege und Wartung der 6 Prozessrechner benoetigt. Neben dem Einsparungspotential wurde eine grosse funktionelle Verbesserung fuer die Bereitstellung der Prozessdaten im gesamten Kraftwerk und darueber hinaus im gesamten VEAG-Netzwerk erreicht. (orig./RHM)

Theseus, the 50 MW solar thermal power plant; Das solarthermische 50-MW-Kraftwerk Theseus

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Brakmann, G. [Fichtner GmbH und Co. KG, Stuttgart (Germany). Solarenergieprojekte

1998-04-01

The Isle of Crete measures 8331 km{sup 2}, and this island renowned for its historical sites attracts millions of tourists every year. Like any other branch of industry, tourism, which is called a ``white`` industry, has an ever growing demand for electric power. Up to now, electricity generation on the island is based on fossil-fuelled thermal power plants. However, recent developments indicate that this technology might be overtaken soon by the novel Theseus power plant (Thermal Solar European Power Station) currently under construction. It is expected to usher in a new era of power generation on the Isle of Crete. (orig./CB) [Deutsch] Die 8 331 km{sup 2} grosse Insel Kreta wurde vor ueber 3 500 Jahren besiedelt. Der geschichtstraechtige Ort ist ein hochgeschaetztes Reiseziel von Millionen Griechenlandurlaubern. Wie jede Art von Industrie, so benoetigt auch die als `weisse Industrie` bezeichnete Touristikbranche immer mehr elektrische Energie. Diese wird derzeit auf Kreta ausschliesslich mit thermischen Kraftwerken, welche fossile Brennstoffe verbrennen, erzeugt. Aber die Vorherrschaft dieser Technologie kann schon bald mit dem neuen solarthermischen Kraftwerk Theseus (Thermal Solar European Power Station) gebrochen werden. Es soll in wenigen Jahren eine neue Aera der Energieerzeugung auf Kreta einlaeuten. (orig.)

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

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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

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

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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

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

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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

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

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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.

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

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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

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

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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

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.

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.

Chemistry in power plants 2011; Chemie im Kraftwerk 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

Within the VGB Powertech conference from 25th to 27th October, 2011, in Munich (Federal Republic of Germany), the following lectures and poster contributions were presented: (1) The revised VGB standard for water-steam-cycle Chemistry; (2) Switchover from neutral operation to oxygen treatment at the power station Stuttgart-Muenster of EnBW Kraftwerke AG; (3) Steam contamination with degradation products of organic matters present in the feedwater of the Lanxess-Rubber cogeneration plant; (4) Laboratory scale on-line noble metal deposition experiments simulating BWR plant conditions; (5) Building a new demin installation for the power plant EPZ in Borssele; (6) Replacement of the cooling tower installations in the nuclear power plant Goesgen-Daenien AG; (7) Aging of IEX resins in demin plants - Cost optimisation by adaptation of regenerants; (8) The largest DOW trademark EDI System at a combined cycled plant in Europe; (9) Upgrading river Main water to boiler feed water - Experiences with ultrafiltration; (10) Experiences with treatment of the water-steam-cycle in the RDF power plant Nehlsen Stavenhagen with film-forming amines; (11) Comparative modelling of the bubbles thermal collapse and cavitations for estimation of bubbles collapse influence; (12) Overcoming the steam quality - issues from an HRSG for the production of process steam; (13) Legionella - new requirements for power plant operation; (14) How the right chemistry in the FGD helps to improve the removal in the waste water treatment plant; (15) High efficiency filtration in dry/semi-dry FGD plants; (16) Expanding the variety of renewable fuels in the biomass power plant Timelkam using the chemical input control; (17) Corrosion, operating experiences and process improvements to increase the availability and operating time of the biomass power plant Timelkam; (18) The influence of temperature on the measurement of the conductivity of highly diluted solutions; (19) A multiparameter instrumentation approach

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

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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

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

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

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.

Lessons learned from full-scale vibration tests on nuclear power plant auxiliary structure in Switzerland

International Nuclear Information System (INIS)

Berger, E.; Tinic, S.

1988-01-01

The Beznau Nuclear Power Plant is located in northern Switzerland. The plant is owned and operated by the Nordostschweizerische Kraftwerke AG (NOK) in Baden, Switzerland. It is a twin unit plant (2 x 350 MWe) which was designed in the early 1960's and placed into commercial operation between 1969 and 1971. In connection with a major backfit project, which will improve the safety of the plant against external events, the free-standing boric water tanks had to be relocated and were replaced by two boric water tanks in a new building (the so called BOTA-building). It enabled to plan and perform full scale vibration tests.The scope of experimental investigation was to determine the eigenfrequencies and damping values for fundamental soil-structure interaction. The vibration tests allowed identification of the important modes of the soil-structure system in the range 3 to 15 Hz. The excitation was strung enough to generate accelerations in the structure comparable to those of a small earthquake. From the comparisons of computed and measured results it is concluded that the rocking frequency can be reasonably well predicted by either Finite Element or Lumped Parameter models with springs simulating the soil-foundation stiffness, provided in the case of the latter the embedment is taken into account. The prediction of the amplitude of structural response appears to be more difficult, as shown by the differences in the mode shapes. In the frequency range 8 to 10 Hz the agreement between computed and test results was less satisfactory. The actual structural behaviour turned out to be more complex than expected and needs further investigation with the aid of more refined models for the soil-structure system

Lessons learned from full-scale vibration tests on nuclear power plant auxiliary structure in Switzerland

Energy Technology Data Exchange (ETDEWEB)

Berger, E [Basler and Hofmann AG, Consulting Engineers, Zurich (Switzerland); Tinic, S [Nordostschweizerische Kraftwerke AG, Baden (Switzerland)

1988-07-01

The Beznau Nuclear Power Plant is located in northern Switzerland. The plant is owned and operated by the Nordostschweizerische Kraftwerke AG (NOK) in Baden, Switzerland. It is a twin unit plant (2 x 350 MWe) which was designed in the early 1960's and placed into commercial operation between 1969 and 1971. In connection with a major backfit project, which will improve the safety of the plant against external events, the free-standing boric water tanks had to be relocated and were replaced by two boric water tanks in a new building (the so called BOTA-building). It enabled to plan and perform full scale vibration tests.The scope of experimental investigation was to determine the eigenfrequencies and damping values for fundamental soil-structure interaction. The vibration tests allowed identification of the important modes of the soil-structure system in the range 3 to 15 Hz. The excitation was strung enough to generate accelerations in the structure comparable to those of a small earthquake. From the comparisons of computed and measured results it is concluded that the rocking frequency can be reasonably well predicted by either Finite Element or Lumped Parameter models with springs simulating the soil-foundation stiffness, provided in the case of the latter the embedment is taken into account. The prediction of the amplitude of structural response appears to be more difficult, as shown by the differences in the mode shapes. In the frequency range 8 to 10 Hz the agreement between computed and test results was less satisfactory. The actual structural behaviour turned out to be more complex than expected and needs further investigation with the aid of more refined models for the soil-structure system.

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

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

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

Solar thermal power plants for the Mediterranean region: A chance for a new era in the field of electricity supply; Solarthermische Kraftwerke fuer den Mittelmeerraum: Chance fuer eine neue Aera der Elektrizitaetsversorgung

Energy Technology Data Exchange (ETDEWEB)

Nitsch, J [DLR, Stuttgart (Germany)

1994-12-31

One promising option for a really environmentally and climaticly friendly electricity supply is the erection of solar thermal power plants in regions of the earth with a considerably high solar irradiation. In this work the technical and economical chances for this technology are analysed and explanations are given as to which energetic and econmic marginal conditions must be created for a successful market introduction, which could already be initiated with several demonstration power plants. (orig.) [Deutsch] Eine der vielversprechenden Optionen fuer wirklich umwelt- und klimafreundliche Elektrizitaetsversorgung stellt der Bau solarthermischer Kraftwerke in den einstrahlungsreichen Regionen der Erde dar. Der Beitrag analysiert die technisch-oekonomischen Chancen dieser Technologie und zeigt auf, welche energiewirtschaftlichen Randbedingungen als Voraussetzung fuer eine erfolgreiche Markteinfuehrung geschaffen werden muessen, die schon jetzt mit einer Reihe von Demonstrationskraftwerken beginnen koennte. (orig.)

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

Theseus is shaping up. 50 MW solar thermal power plant projected on Crete; Projekt Theseus nimmt Gestalt an. Solarthermisches 50-MW-Kraftwerk auf Kreta in Planung

Energy Technology Data Exchange (ETDEWEB)

Bachmann, O.; Brakmann, G. [Fichtner GmbH und Co. KG, Stuttgart (Germany)

1998-10-01

On the Greek island of Crete, with 8331 km{sup 2}, electric power is mainly generated by combustion of oil. This will change with Theseus (Thermal Solar European Power Station). Theseus is projected on a site with 2,200 sunshine hours per annum. The power station will cost around 125 Mio. ECU. It will have a capacity of 50 MWe. An auxiliary fossil-fuel boiler will provide steam for the turbines in the evening hours and in times of low insolation. Theseus is being constructed by a consortium under German leadership (orig.) [Deutsch] Auf der 8331 km{sup 2} grossen Insel Kreta wird die elektrische Energie bisher zum ueberwiegenden Teil durch Verbrennen von Oel erzeugt. Dies soll sich mit Theseus (Thermal Solar European Power Station) aendern. Theseus wird an einem Ort, der 2.200 Stunden pro Jahr Solarbetrieb gewaehrleistet, errichtet. Das rund 135 Mio. ECU teure Kraftwerk soll 50 MWe leisten und mit einem zusaetzlichen konventionellen, fossil gefeuerten Kessel ausgeruestet werden, der in den Abendstunden und bei geringer Sonnenstrahlung Dampf fuer die Turbinen erzeugt. Fuer die Realisierung von Theseus hat sich ein unter deutscher Leitung stehendes Konsortium gebildet. (orig./AKF)

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)

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

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

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.

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

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

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

The text of the agreement of 15 July 1981 between Argentina and the Agency for the application of Safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomica Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant

International Nuclear Information System (INIS)

1995-01-01

The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 15 July 1981 between Argentina and the IAEA for the application of safeguards in connection with contracts concluded between the Comision Nacional de Energia Atomic Argentina and the Kraftwerk Union AG (Federal Republic of Germany) for the supply of the Atucha II Nuclear Power Plant has been suspended

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...

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

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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.

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

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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%.

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

Sewage sludge disposal at the city of Duesseldorf - Conception of co-combustion in a coal power plant; Klaerschlammentsorgung der Stadt Duesseldorf - Konzeption der Mitverbrennung im Kraftwerk

Energy Technology Data Exchange (ETDEWEB)

Lindert, M. [Umweltamt der Landeshauptstadt Duesseldorf (Germany); Hansmann, G. [Stadtwerke Duesseldorf AG (Germany); Mittmann, H. [Kanal- und Wasserbauamt der Landeshauptstadt Duesseldorf (Germany); Goertz, W. [Umweltamt der Landeshauptstadt Duesseldorf (Germany)

1995-11-01

Simultaneously to the enlargement of the biological wastewater treatment plants in Germany the amount of sludges increased. For the reuse or disposal of these sludges different methods - from agricultural use to incineration - are applied. For the city of Duesseldorf it became necessary to outline a new conception for the sludge disposal. A number of methods has been considered, showing that co-incineration in a coal-power-plant appears to be practicable under the circumstances found in Duesseldorf. Hence the effects of such a co-incineration on the emissions and the composition of solid waste materials of the power plant have been investigated in the course of an experimental operation. These experiments show that coincineration of the sludge also has advantages from the ecological point of view. (orig.) [Deutsch] Mit dem Ausbau der biologischen Klaeranlagen in Deutschland stieg in den letzten Jahren auch die Menge des anfallenden Klaerschlamms. Zur Verwertung bzw. Entsorgung dieses Schlammes werden unterschiedliche Verfahren - von der landwirtschaftlichen Verwertung bis zur Verbrennung - herangezogen. Fuer die Stadt Duesseldorf ergab sich die Notwendigkeit, die Klaerschlammentsorgung neu zu konzipieren. Verschiedene Varianten wurden geprueft, wobei die Mitverbrennung in der Schmelzkammerfeuerung eines Steinkohlekraftwerkes unter den in Duesseldorf herrschenden Randbedingungen praktikabel erschien. Daher wurden die Auswirkungen einer solchen Mitverbrennung auf das Emissionsverhalten und die Zusammensetzung der festen Reststoffe des Kraftwerks waehrend eines Probebetriebes untersucht. Die Versuche zeigen, dass die Mitverbrennung auch aus oekologischer Sicht Vorteile aufweist. (orig.)

Planning games for the electricity supply industry

International Nuclear Information System (INIS)

Weber, K.

1977-01-01

The author shows the main differences between the electricity supply planning game for the Bernische Kraftwerke AG (PEW-1) and that for the Rheinisch-Westfaelische Elektrizitaetswerke AG (PEW-2). (orig.) [de

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.

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.

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

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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

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

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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.

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.

KARAKTERISTIK REAKTIVITAS TERAS KERJA RSG-GAS SELAMA 30 TAHUN BEROPERASI

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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.

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

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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

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

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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.

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

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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

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

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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

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

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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.

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

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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

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

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Ralind Re Marla

2015-03-01

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

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

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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%.

Technical dictionary power plant engineering. Vol. 1. German - English. - Pt. 1: Dictionary. Pt. 2: Abbreviations. 4. rev. and enlarged ed. Technisches Woerterbuch Kraftwerkstechnik. Bd. 1. Deutsch - Englisch. - T. 1: Woerterbuch. T. 2: Abkuerzungen

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB).

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

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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.

EFEK DENSITAS BAHAN BAKAR TERHADAP PARAMETER KOEFISIEN REAKTIVITAS TERAS RRI

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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

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

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Setiyanto Setiyanto

2016-10-01

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

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

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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)

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

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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...

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

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

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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.

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

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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%.

Kraftwerki hi-tech show esmakordselt Eestis / Christel Karits

Index Scriptorium Estoniae

Karits, Christel, 1966-

2004-01-01

Saksa elektroonilise muusika ansambel Kraftwerk esitab kontserdil Eesti Näituste suures saalis paremiku oma 30aastasest loomingust ja lugusid viimaselt albumilt "Tour de France Soundtracks", ansamblist

ANALISA KARAKTERISTIK MINYAK PLASTIK HASIL DUA KALI PROSES PIROLISIS

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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

Joint implementation as an instrument for the market introduction of solar thermal power plants; Joint Implementation als Instrument zur Markteinfuehrung Solarthermischer Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Trieb, F.; Nitsch, J.; Fischedick, M.; Luhmann, H.J.

1997-12-31

Investitionen (z.B. fuer eine Verbesserung der Energieeffizienz) in anderen Laendern kostenguenstig erfuellen. Solarkraftwerke erfuellen alle Kriterien eines erfolgreichen JI-Projektansatzes und zeigen zahlreiche positive oekologische und sozio-oekonomische Nebeneffekte, die zu einer umweltvertraeglichen und mittelfristig auch wirtschaftlichen Elektrizitaetsversorgung fuehren koennen. Voraussetzung hierfuer ist, dass der baldigen Markteinfuehrung eine Phase der Massenproduktion mit einer entsprechenden Ausschoepfung des zur Zeit noch vorhandenen Kostensenkungspotentials dieser Technologie von ca. 50% folgt. Das THESEUS Projekt auf Kreta ist ein wichtiger Schritt zur Markteinfuehrung und zur Demonstration der Tragfaehigkeit und der Bedeutung solarthermischer Kraftwerke fuer den Klimaschutz, und vor allem ein entscheidender europaeischer Schritt in die Richtung einer nachhaltigen Energieversorgung. (orig./AKF)

Operating requirements for power plants in the liberalised electricity market; Einsatzanforderungen an Kraftwerke im liberalisierten Strommarkt

Energy Technology Data Exchange (ETDEWEB)

Schwarzbach, G. [Vereinigte Energiewerke AG, Berlin (Germany)

2000-07-01

Einzelkraftwerke und kleine Kraftwerksparks muss mit hoeheren dynamischen Anforderungen gerechnet werden, um moeglichst genau und weitgehend ohne Inanspruchnahme teuerer Regelleistung des Netzbetreibers die mit dem Kunden vereinbarten Stundenfahrplaene abzudecken. Darueber hinaus gegebenenfalls verbleibende Leistung wird - auch nach Entstehen physischer Stromboersen - nicht immer ihre Kaeufer finden. Alternative Beschaffungsmoeglichkeiten werden staendig mit den eigenen Erzeugungskosten verglichen, was ebenfalls eine Erhoehung dynamischer Anforderungen an die Kraftwerke zur Folge haben kann. Fuer groessere Kraftwerksparks und insbesondere bei Vorhandensein ausreichender Pumpspeicherleistung ist demgegenueber zu erwarten, dass ein besserer Ausgleich erhoehter Regelanforderungen moeglich ist, soweit deren wirtschaftliche Auswirkungen in Kurzfrist-Einsatzoptimierungsprogrammen Beruecksichtigung finden. (orig.)

1. expert congress on geothermal power: On the way to a new energy future. Proceedings; 1. Fachkongress Geothermischer Strom: Start in eine neue Energiezukunft. Tagungsband

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

Tagungsband befasst sich mit den folgenden Themen: 1. Allgemeiner Teil: a) Die Rolle der Geothermie im Rahmen einer zukunftsfaehigen Energieversorgung; b) Effiziente Foerderinstrumente fuer Erneuerbare Energien; c) Geothermische Ressourcen fuer die Stromerzeugung (TAB-Studie); d) Vom Potenzial zur Nutzung - Konzepte fuer die geothermische Stromerzeugung in Deutschland; e) Eine energiewirtschaftliche Einordnung der Geothermie in das Energiesystem der Bundesrepublik Deutschland. Vergleich der unterschiedlichen Techniken, des Entwicklungsstandes, Marktpotenzials geothermischer Stromerzeugung und der bisher gemachten Erfahrungen in den laufenden Projekten. 2. Lokalbezug und Poster: a) Erkundung, Aufschluss, Bau und Betrieb der geothermischen Anlage in Neustadt-Glewe; b) Technisches Konzept des geothermischen Kraftwerks Neustadt-Glewe. 3. Exploration, Bohrtechnik: a) Abschaetzung der Erfolgswahrscheinlichkeit bei geothermischen Bohrungen; b) Seismische Exploration, Reservoirmodellierung und Reservoirsimulation zum Geothermieprojekt; c) Bohrtechnik und Bohrkosten fuer Sedimentgesteine. Bohren im Kristallin. 3. Komplettierung, Frac-Technik: a) Frac-Technik im Kristallin; b) Frac-Technik in Sedimenten; c) New-Technology MWD and LWD Systems Designed for Ultra-Deepwater and Geothermal Drilling; d) Weiterentwicklung geothermischer Stromerzeugung im sueddeutschen Kristallin. 4. Verstromung Geothermischer Energie: a) Effizienz der geothermischen Stromerzeugung; b) Duales Heizwerk gespeist mit einem geothermalen Wasser einer mittleren Enthalpie; c) Das Geothermiefeld der Insel Milos in Griechenland: Aktuelle geothermische Exploration und Entwicklung. 5. Poster der Tagung: a) Der UGGW - das innovative Konzept zur Standort unabhaengigen Stromerzeugung; b) Geothermische Ressourcen Russlands und Nutzungsprognose bis 2020; c) Auf der Lernkurve zum Geothermischen Strom: Das In situ Geothermielabor Gross Schoenebeck; d) Waermebegleitende Tiefbohrzemente: Zusammensetzungen, Untersuchungsmethode

Product marketing for eco-power; Produktemarketing fuer Oekostrom

Energy Technology Data Exchange (ETDEWEB)

Huber, D. [Verband Schweizerischer Elektrizitaetswerke, Zuerich (Switzerland)

1998-10-30

The company NaturEnergie (natural energy), a subsidiary of the Energieversorger Kraftwerk Laufenburg AG (KWL) is located in Grenzach-Whylen (Germany) near Basel (Switzerland) has been selling power generated from sun and water since the 1st of October 1998. The company employes a cleverly designed, emotional marketing strategy in order to position the brand ``NaturEnergie`` as a label for ``green power`` on the market. Bulletin VSE talked to Dr. Kai-Hendrik Schlusche (40), co-founder and member of the board of NaturEnergie AG about marketing and pricing of ``green`` power and about relations with Switzerland.(orig.) [Deutsch] Im grenznahen Grenzach-Whylen bei Basel verkauft die Firma NaturEnergie, eine Tochtergesellschaft der Energieversorger Kraftwerk Laufenburg AG (KWL) und Kraftuebertragungswerke Rheinfelden AG (KWR), seit 1. Oktober 1998 Oekostrom aus Sonne und Wasser. Mit Hilfe einer ausgekluegelten emotionellen Marketingstrategie will das junge Unternehmen die Marke `NaturEnergie` als Label fuer `gruenen Strom` im Markt positionieren. Bulletin VSE sprach mit Dr. Kai-Hendrik Schlusche (40), seit Mai 1998 Gruendungsvorstand der NaturEnergie AG, ueber Marketing, Preisgestaltung von `gruenem Strom` und die Beziehungen zur Schweiz. (orig.)

Pra Desain Pabrik Sorbitol dari Tepung Tapioka dengan Hidrogenasi Katalitik

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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.

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

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)

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

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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

FACTORS INFLUENCING HUMAN RELIABILITY OF HIGH TEMPERATURE GAS COOLED REACTOR OPERATION

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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

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.

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.

Technical dictionary power plant engineering. Vol. 1. 4. rev. and enlarged ed.

International Nuclear Information System (INIS)

1987-01-01

This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB). (orig./HP) [de

The Iran-1 and Iran-2 nuclear power station on the Persian Gulf

International Nuclear Information System (INIS)

Altvater, W.

1977-01-01

Iran is a country with large oil reserves which, however, are exploited only very carefully because of ther importance for exports. In the light of this policy it was decided to make increasing use of nuclear energy for the country's electricity supply. Under the 8th Iranian five year plan, a total installed generating capacity of 56,000 MW is foreseen by 1993, of which 24,400 MW will be in nuclear power plants. This large construction program of nuclear power stations is implemented by the Atomic Energy Organization of Iran, AEOI, which started negotiations with potent nuclear industries of various industrialized countries in early 1974. In November 1974, these discussions led to a letter of intent with the German Kraftwerk Union AG (KWU) for the turnkey erection of the first Iranian nuclear power plant, Iran-1 and Iran-2, with two units of 1,300 MW on a site on the Persian Gulf. The siting decision was taken in favor of the Halileh area located some 18 km from the seaport of Bushehr. Construction work on the site began in July 1975. The delivery dates are December 1, 1980 for Iran-1 and November 1, 1981 for Iran-2. (orig.) [de

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

Special features of the safety concept and design requirements applied for Angra-2 and 3

International Nuclear Information System (INIS)

Anon.

1980-01-01

The special features and requirements which have been applied by NUCLEN (Nuclebras Engenharia S/A) for Angra 2 and Angra 3 and which depart somewhat from the KWU (Kraftwerk Union) standard plant, are presented. (E.G.) [pt

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.

Power plant generators. Kraftwerks-Generatoren

Energy Technology Data Exchange (ETDEWEB)

1978-01-01

State of the art, design and types of large turbogenerators (up to 1635 MVA) are described, and their network behaviour is presented with regard to safety problems. It is expected that most progress will be made with iron-free rotors (in the sense of magnetic iron) with superconducting field coils and their thermomechanical problems.

Holger Loodus / Holger Loodus

Index Scriptorium Estoniae

Loodus, Holger

2000-01-01

Ansambli "Dallas" kitarrist Holger Loodus kirjutab oma olulisematest plaatidest:Blondie "The Best Of Blondie", Peter Sarstedt "Peter Sarstedt", Collage "Kadriko", Kraftwerk "Man Machine", Nansy Sinatra ja Lee Hazlewood "The Hits Of Nancy & Lee", The Modern Jazz Quarte "Third Stream Music"

General introduction CSP Technologies and grid management

OpenAIRE

Hoffschmidt, Bernhard

2017-01-01

Der Vortrag gibt einen Überblick über alle relevanten CSP Technologien und beschreibt die besondere Charakteristik der Stromproduktion sowie die aktuelle und mittelfristige Markt- und Kostensituation. Für eine weitere Kostenreduktion wird der Vorteil eines PV-CSP Hybrid Kraftwerks beschrieben.

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

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.

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

Pop / Marek Kallin

Index Scriptorium Estoniae

Kallin, Marek

2005-01-01

Heliplaatidest: Kano "Home Sweet Home", Static-X "Start A War", Kraftwerk "Minimum Maximum", The Juan Maclean "Less Than Human", Andrian Belew "Side Two", Saint Etienne "Tales From Turnpike House", Jamie Cullum "Pointless Nostalgic", James Blunt "Back To Bedlam", Architecture In Helsinki "In Case We Die"

Muusika DVD-d / Juhan Ulfsak

Index Scriptorium Estoniae

Ulfsak, Juhan, 1973-

2006-01-01

Uute DVD-de Eppu Normaali "Video jää pystyyn", Taraf de Haidouks "The Continuing Adventures Of Taraf de Haidouks, "Kraftwerk "Minimum/Maximum", Judas Priest "Rising In The East", R. Kelly "Trapped In The Closet", Deep Purple "Perihelion", Ray Charles "50 Years In Music"

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%.

Experience gained in the training of nuclear power plant operating personnel with nuclear power plant simulators

International Nuclear Information System (INIS)

Buettner, J.; Fueg, J.; Schlegel, G.

1980-01-01

The simulator of a PWR-type reactor with 1.200 MW was accomplished in September 1977. In January 1978, the simulator of a BWR-type reactor with 800 MW started operation. The American company Singer/Link supplied computer hardware and software; Kraftwerk Union AG supplied control room equipment, power plant data and acted as consulting engineers for the construction and acceptance of the simulators. This way it is ensured that the simulated process reflects the state of German nuclear engineering. (orig./DG) [de

Sound-tracking Germany: 70 years of imagining the nation from Schlager to Techno

NARCIS (Netherlands)

Schiller, M.M.

2016-01-01

In the mid-seventies, Kraftwerk asked, "What is the sound of the German Bundesrepublik?" and answered with their international über-hit "Autobahn". In the eighties, Deutsch Amerikanische Freundschaft [DAF] ordered the dance-obsessed New German Wave youth to "shake your ass and do the Adolf Hitler!"

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

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.

Kraftwerk Union (KWU) nuclear fuel service

International Nuclear Information System (INIS)

Knaab, H.; Knecht, K.; Garzarolli, F.

1977-01-01

Activities started with the commissioning of the first German nuclear power stations have led to the present form of the nuclear fuel customer service. In the meantime, based on these tasks numerous test and working methods were developed and applied which are now available to operators of nuclear power station. The paper describes the most important methods and instruments and surveys the nuclear fuel service tasks carriedout to date. Past experience has shown that detailed knowledge of design, fabrication as well as the possibility to compose observations with investigations of engineering and hot cell laboratories are prerequisites for successful service performance. The expected trend towards increasing frequency of service activities in the next few years must be taken into account by a continuous expansion in the number of the qualified personnel. It will become necessary for the coordination of the work at an increasing number of reactor plants to conclude long-term service agreements with the customer. (orig.) [de

Radioactive waste management practices with KWU-boiling water reactors

International Nuclear Information System (INIS)

Queiser, H.

1976-01-01

A Kraftwerk Union boiling water reactor is used to demonstrate the reactor auxiliary systems which are applied to minimize the radioactive discharge. Based on the most important design criteria the philosophy and function of the various systems for handling the off-gas, ventilation air, waste water and concentrated waste are described. (orig.) [de

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.

D1+ Simulator: A cost and risk optimized approach to nuclear power plant simulator modernization

International Nuclear Information System (INIS)

Wischert, W.

2006-01-01

D1-Simulator is operated by Kraftwerks-Simulator-Gesellschaft (KSG) and Gesellschaft f?r Simulatorschulung (GfS) at the Simulator Centre in Essen since 1977. The full-scope control room training simulator, used for Kernkraftwerk Biblis (KWB) is based on a PDP-11 hardware platform and is mainly programmed in ASSEMBLER language. The Simulator has reached a continuous high availability of operation throughout the years due to specialized hardware and software support from KSG maintenance team. Nevertheless, D1-Simulator largely reveals limitations with respect to computer capacity and spares and suffers progressively from the non-availability of hardware replacement materials. In order to ensure long term maintainability within the framework of the consensus on nuclear energy, a 2-years refurbishing program has been launched by KWB focusing on quality and budgetary aspects. The so-called D1+ Simulator project is based on the re-use of validated data from existing simulators. Allowing for flexible project management methods, the project outlines a cost and risk optimized approach to Nuclear Power Plant (NPP) Simulator modernization. D1+ Simulator is being built by KSG/GfS in close collaboration with KWB and the simulator vendor THALES by re-using a modern hardware and software development environment from D56-Simulator, used by Kernkraftwerk Obrigheim (KWO) before its decommissioning in 2005. The Simulator project, launched in 2004, is expected to be completed by end of 2006. (author)

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

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

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

12 billion DM for Germany

International Nuclear Information System (INIS)

Anon.

1975-01-01

The German atomic industry has achieved the break-through to the world market: Brazil orders eight nuclear electricity generating plants from Siemens-AEG daughter Kraftwerk-Union. US concerns attacked the twelve billion DM deal, the biggest export order in the history of German industry. Without avail - the contract is to be signed in Bonn this week. (orig./LH) [de

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

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.

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

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.

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.

Diagnostic and monitoring systems in nuclear power plants

International Nuclear Information System (INIS)

Wehling, H.J.; Jax, P.; Streicher, V.

1987-01-01

Monitoring systems are important for the availability of nuclear power plants. A survey is given about such systems designed and constructed by the Kraftwerk Union AG Erlangen (Federal Republic of Germany) in order to assure the mechanical integrity of reactor cooling systems. Three monitoring systems based on microprocessors are presented: KUES (acoustic detection of loose parts), SUES (vibration), and FAMOS (fatigue)

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

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

OECD/NEA Aagesta decontamination project. Phase 1, final report

International Nuclear Information System (INIS)

1982-12-01

The objective of the project is to utilize the four primary loops of the Aagesta reactor to demonstrate decontamination methods for PWR primary systems. The first phase of the project consisted of laboratory scale tests. The methods tested were developed at a) Studsvik Energiteknik AB, Sweden (a soft chemistry). b) Kraftwerk Union AG, Federal Republic of Germany, (two chemistries, one soft and one hard). c) Swiss Federal Institute of Reactor Research (two chemistries, one soft and one hard). d) Berkeley Nuclear Laboratories, United Kingdom, (a soft chemistry). The test programme consisted of decontamination tests on steam generator tubing and other active material from Aagesta and a number of operating reactors as well as material compatibility tests on standardized samples of a representative selection of modern PWR primary system materials. Six countries have participated in Phase I of the project - the four countries named above as well as the United States of America and Italy. Studsvik Energiteknik AB was appointed Project leader. The results show that all six processes in general met the acceptance criteria both regarding decontamination and corrosion. The decontamination results with the hard chemistries were rather uneven. (Author)

Combination of a pyrolysis plant with a hard coal power station firing system; Kombination einer Pyrolyseanlage mit einer Steinkohlekraftwerksfeuerung

Energy Technology Data Exchange (ETDEWEB)

Schulz, W.; Hauk, R. [Vereinigte Elektrizitaetswerke Westfalen AG (VEW), Dortmund (Germany)

1998-09-01

VEW ENERGIE AG plans and operates power plants and thermal plants for the disposal of residual materials (e.g. household waste, sewage sludge, used wood, residues from paper manufacture). In order to make itself familiar with the market for secondary fuels the company undertook a study to find out what cost-effective techniques are available on the market and how power plants can be used for optimal energy use and with a minimum of disposal costs. Its choice finally fell on pyrolysis because this technology is the most flexible for the thermal and physical utilisation of substitute fuels. Moreover, pyrolysis combines very well with power plants. [Deutsch] VEW ENERGIE AG plant und betreibt Kraftwerke und thermische Anlagen zur Entsorgung von Reststoffen (z.B. Hausmuell, Klaerschlamm, Altholz, Reststoff aus der Papierherstellung). Um sich auf dem Markt der Ersatzbrennstoffe einzustellen, wurde untersucht, welche kostenguenstigen Techniken auf dem Markt verfuegbar sind und wie Kraftwerke zur optimalen Energienutzung und zur Minimierung der Entsorgungskosten eingesetzt werden koennen. Die Pyrolysetechnik wurde ausgewaehlt, weil sie am flexibelsten fuer die thermische und stoffliche Verwertung der Ersatzbrennstoffe ist. Sie laesst sich auch sehr gut mit Kraftwerken kombinieren. (orig.)

Operating experience with KRAFTWERK UNION cementation line

International Nuclear Information System (INIS)

Podmaka, L.; Tomik, L.

1988-01-01

A facility is described designed for fixation in a cement matrix of the radioactive concentrate produced by thickening waste water from the Bohunice nuclear power plant. The cementation line output is 0.6 m 3 concentrate/h. The concentrate is put in 200 l drums. The individual operating units, cement management, air conditioning, dosimetric monitoring and the building part are described. The requirements for the operators and the assessment of the quality of raw materials and the product are discussed. (M.D.). 3 figs., 4 refs

Powerhouse in the foliage; Kraftwerk im Blattwerk

Energy Technology Data Exchange (ETDEWEB)

Roesch, Harald

2010-07-01

Photosynthesis, a veritable stroke of genius on the part of nature, makes the existence of higher life forms possible. If it can be optimized, it may be able to make an even greater contribution to the resolution of future energy problems. Manajit Hayer-Hartl and Ulrich Hartl are currently working on this possibility at the Max Planck Institute of Biochemistry in Martinsried. (orig.)

Electric power plants and networks. Elektrische Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Happoldt, H [Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.). Abt. Centralen; Oeding, D [Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.). Zentralbereich Forschung und Entwicklung

1978-01-01

This book is itended for enginers working in the planning, construction and operation of plants to generate and distribute electric power; it is also a valuable aid for students of power engineering. This new edition places more emphasis on the presentation and calculation of three-phase current networks with the aid of symmetric components. The equations used for calculation are adapted to VDE regulations as far as possible.

Report on the 77th year of business

International Nuclear Information System (INIS)

1977-01-01

The report on the 77th businesss year of the Norddeutsche Kraftwerke AG (NWK) contains information on the company organs, a short directors' reprot, papers on electricity sales and the electricity available, the extension of supply facilities (power plant, nuclear fuel cycle, network extension), and short informative articles on the earning base and financing, on the employees and on social matters, as well as explanations on the annual balance. (HK) [de

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

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

Strands of the future: France and the birth of electronica

OpenAIRE

Albiez, Sean

2005-01-01

The early history of 1970s electronic rock music, or electronica, often centres on the innovations of Brian Eno, Tangerine Dream and Kraftwerk, whose creative roots are identified as in avant-garde modernist and contemporary music (e.g. Luigi Russolo, Edgard Varese, John Cage, Karlheinz Stockhausen and Pierre Schaeffer). German, British and American artists have gained wide recognition for their roles in this history, but French artists who made important contributions to developments in earl...

Bern Power Station Co

International Nuclear Information System (INIS)

1981-01-01

The Bernische Kraftwerke electricity generation/supply company supplies about one eighth of the Swiss electrical energy demand with about one sixth of the Swiss generating capacity. Directly or indirectly one million inhabitants are supplied, a substantial contribution to the Swiss economy. Data given on BKW includes: historical background, structure, organisation, operations, generating plant, transmission/distribution equipment, electricity generated, supplied, exported and imported, financial aspects, accounting practice and cooperation arrangements with other utilities. (P.G.R.)

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)

Information afternoons for BKW personnel

International Nuclear Information System (INIS)

Meichle, A.

1983-01-01

The management of Bernische Kraftwerke AG organise afternoon meetings for the staff each limited to 70/80 people. Brief details of the information afternoons are given, the main aims of which include updating knowledge on energy policy matters and the need for nuclear power, explaining company policy, improving staff motivation, considering the results of the poll on the standing of BKW with its customers, screening a company film and discussing matters raised by employees. (P.G.R.)

The 'electric power' experience: Between nostalgia and the future

International Nuclear Information System (INIS)

Moergeli, H.P.

1994-01-01

The ''Muehleberg'' is a concept which is mostly used in connection with the nuclear power station. But there is more to the ''Muehleberg'' than at first sight. A hydroelectric station, a waste dump gas plant and the brandnew works management centre of the Bernische Kraftwerke AG (BKW) constitute the framework for a host of other attractions in the field of electric power; among others, examples of technological culture in the BKW museum, which are worth seeing. (orig.) [de

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.

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

Modern plant management in the competitive market

Energy Technology Data Exchange (ETDEWEB)

Fischer, B.; Franke, U.; Freitag, J.U. [E.ON Kraftwerke GmbH, Hannover (Germany)

2002-07-01

Forced by the deregulation of the energy market and the big drop of electricity prices E.ON Kraftwerke was completely reorganised. Small, flexible units that are focussed on their key tasks were formed. Costs for electricity generation in our plants were reduced. Power plants that are currently not economically efficient are temporarily shut down. Power plants that are permanently not economically efficient are totally shut down. We have now reached a point at which energy prices slowly start to rise again. With our new plant management organization we have a lasting effect on further successfully operating power plants and a positive development of our company. Looking into the future does not create fear about what to do but positive believe that we will soon start new projects. This is the fundament for a stable, successful power plant company. (orig.) [German] Unter dem erheblichen Kostendruck, dem alle Energieversorger derzeit ausgesetzt sind, wurde die Aufbauorganisation von E.ON Energie grundlegend veraendert. Bei E.ON Kraftwerke wurden durch die Schaffung kleiner, flexibler Einheiten und eine klare Konzentration auf das Kerngeschaeft die Kosten fuer die Stromerzeugung in den eigenen Anlagen deutlich gesenkt. Die Auslastung vorhandener wirtschaftlicher Bloecke ist durch die Konservierung von derzeit nicht wirtschaftlichen bzw. durch die Stillegung langfristig nicht wirtschaftlicher Anlagen erheblich verbessert worden. Nachhaltig wurde damit eine Betriebsfuehrungsstrategie entwickelt, die den Bestand und eine positive Entwicklung der Kraftwerksgesellschaft sichert. (orig.)

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

Can we dispense with nuclear power. [Federal Republic of Germany]. Koennen wir auf Kernenergie verzichten

Energy Technology Data Exchange (ETDEWEB)

Frewer, H; Braun, W; Freiberger, S; Martin, J

1986-01-01

The aims of energy policy, which consist in safeguarding energy supply while using nuclear power as one source of energy, are discussed in an interview (H. Frewer, Managing Director of Kraftwerk Union 'KWU'). The safety of German nuclear power plants is illustratively compared with the safety of nuclear power plants in the USSR, especially the reactor at Chernobyl (Braun and Freiberger, KWU). A further contribution deals with the propagation of the radioactive plume after the accident at Chernobyl (Martin, KWU).

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

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

The 'electric power' experience: Between nostalgia and the future. Erlebnis 'Strom' zwischen Nostalgie und Zukunft

Energy Technology Data Exchange (ETDEWEB)

Moergeli, H.P. (Moergeli und Partner, Muri bei Bern (Switzerland))

1994-03-04

The ''Muehleberg'' is a concept which is mostly used in connection with the nuclear power station. But there is more to the ''Muehleberg'' than at first sight. A hydroelectric station, a waste dump gas plant and the brandnew works management centre of the Bernische Kraftwerke AG (BKW) constitute the framework for a host of other attractions in the field of electric power; among others, examples of technological culture in the BKW museum, which are worth seeing. (orig.)

KWU puts the emphasis on planning and control

International Nuclear Information System (INIS)

Gehring, W.

1977-01-01

The importance of setting up an authoritative centralised department to plan, direct, and control standardisation policy for PWR type reactors and to ensure a proper flow of information was recognised by Kraftwerk Union at an early stage. The benefits and requirements of standardisation are discussed and the role of the KWU standardisation department in project bidding and implementation is illustrated. The Technical Proposal for a Standard turnkey PWR, which comprises eleven volumes, and the development of a Standard Operation Manual are both discussed. (U.K.)

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 ...

Retrofitting of power plants. Chances and partnerships; Kraftwerksmodernisierung. Moeglichkeiten und Partnerschaften

Energy Technology Data Exchange (ETDEWEB)

Bald, A. [Siemens AG, Bereich Energieerzeugung (KWU), Erlangen (Germany); Schwegmann, P. [Siemens AG, Bereich Energieerzeugung (KWU), Erlangen (Germany)

1997-01-01

Thousands of power plant managers in the former Soviet Union and the COMECON countries were compelled in the last few years to make a virtue of necessity, adopting the slogan that says ``necessity is the mother of invention`` in their efforts to keep their power plants operating, although there was no way of getting spare sparts or assistance from the general planning boards in Moscow; due to their improvisatory skills they accomplished a great achievement and managed to maintain electricity supply to date. However, the resulting situation today is that the great majority of power plants in the former COMECON member states, i. e in the CIS and in Central and East Europe, badly need repair and backfitting. The article discusses chances and potentials of power plant retrofitting activities, cooperative activities on the part of western countries, and financial support programmes. (orig./RHM) [Deutsch] Tausende von Kraftwerksdirektoren in der ehemaligen Sowjetunion und in den RGW-Staaten haben aus der Not eine Tugend machen muessen: Mit Improvisation und Flexibilitaet hielten sie ihre Kraftwerke am Laufen - Hilfe und Ersatzteile waren von den zentralen Planungsstellen in Moskau kaum zu erwarten; es war eine ungeheure Leistung, dass die Stromversorgung ueberhaupt noch aufrechterhalten wurde. Als Ergebnis dieser Zwangslage sind die meisten Kraftwerke im ehemaligen RGW-Raum, dem heutigen Mittel-Osteuropa und der GUS, dringend ueberholungsbeduerftig. Moeglichkeiten der Kraftwerksmodernisierung, Kooperationen bei der Rekonstruktion und Fragen der Finanzierung werden im folgenden erlaeutert. (orig./RHM)

Component codification and identification systems

International Nuclear Information System (INIS)

Pannenbaecker, K.

1977-01-01

The lecture covers the codification in power stations during the erection phase and commercial operation phase. A diagram gives a survey. There are three basic-codifications for application; 1) Kraftwerk-Kennzeichen-System (KKS) for marking each component in orientated systems, for marking electrical orientated positions in cubicals, switch gears etc. and for marking rooms in buildings; 2) Ordnungssystem (OS) for cost calculation and ordering; 3) Unterlagenarten-Schluessel (UAS) for letters, reports etc. and for documentation. The OS is developed on the principle of cost account number and is therefore close to the organization of each supplier and his special form of design and constrution. KKS has only to mark hardware. Therefore all German owners, consultants, authorities and suppliers develop KKS together and conform to it in DIN 407119. (ORU) [de

Final report on 3-D experiment project air-water upper plenum experiments

International Nuclear Information System (INIS)

Jacoby, J.K.; Mohr, C.M.

1978-11-01

The results are presented from upper plenum air-water reflood behavior testing performed as part of the program to investigate three-dimensional aspects of PWR LOCA research. Tests described were performed at near ambient temperature and pressure in a plexiglass vessel which included the important features of the upper core and upper plenum regions corresponding to a single fuel bundle in both Westinghouse Electric Corporation (Trojan) and Kraftwerk Union (KKU) PWR designs. The data included observed two-phase flow characteristics, particularly with regard to countercurrent flow, and cinematography of the characteristic upper plenum flow patterns

Brokdorf nuclear power station: Construction scheduling and deadline control

International Nuclear Information System (INIS)

Lembcke, U.D.F.

1986-01-01

Scheduling, especially deadline control, for all installations of the Brokdorf nuclear power station was carried out centrally by the Project Management of Kraftwerk Union AG. 130 timetables encompassing some 13,000 activities were handled, which were interconnected and linked to 189 timetables (approx. 18,000 activities) from various specialized sections by means of data processing systems. Much space in time scheduling was taken by controls of software processing, especially of the preliminary inspection documents in the piping sector and of working documents for construction management in the control systems area. (orig.) [de

150 years of electrical engineering. A review and future prospects for power plant construction; 150 Jahre Elektrotechnik. Rueckblick und Vision im Kraftwerksbau

Energy Technology Data Exchange (ETDEWEB)

Boehm, H. [Siemens AG Unternehmensbereich KWU, Erlangen (Germany). Bereich Energieerzeugung

1997-12-01

The development of power plant construction both in the last 150 years and also relative to the deduced major trends for the future is illustrated by the important milestones. In this respect, the important role of modern power stations is very prominent in ensuring enduring economic development. (orig.) [Deutsch] Anhand von wichtigen Meilensteinen wird die Entwicklung im Kraftwerksbau sowohl in den letzten 150 Jahren als auch entsprechend den sich abzeichnenden grossen Trends fuer die Zukunft beleuchtet. Dabei steht die wichtige Rolle moderner Kraftwerke fuer eine nachhaltige Entwicklung im Vordergrund. (orig.)

The nuclear training centre of the nation. Three years after Chernobyl the question is: how safe are German nuclear power reactors The reactor operators come from the training centre in Essen where everything is alright in the world of simulators: all emergencies can be managed, and MCA is not in the program. Die Atomschule der Nation. Drei Jahre nach Tschernobyl stellt sich die Frage: Wie sicher sind deutsche Atomkraftwerke In Essen wird deren Personal geschult. Am Simulator ist die Welt noch in Ordnung: Stoerfaelle sind allesamt beherrschbar - ein Super-GAU ist nicht im Programm

Energy Technology Data Exchange (ETDEWEB)

Gleich, M.

1989-05-01

This on-the-spot report gives an account of one day at the reactor operator's training centre of Kraftwerks-Simulator Gesellschaft in Essen, West-Germany. Heavy criticism is raised by the reporter who found out that none of the four simulators' computer programs includes the scenarios of accidents that may lead to severe reactor core damage. The conclusion drawn from this fact is that the West-German reactor operating personnel is just as incapable of managing a severe accident as their colleagues in Chernobyl. (DG).

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

An advanced configuration management system for full scope power plant simulators

International Nuclear Information System (INIS)

Storm, J.; Goemann, A.

1996-01-01

In August 1993 KSG Kraftwerks-Simulator-Gesellschaft, Germany, awarded a contract to STN ATLAS Elektronik for the delivery of two full scope replica training simulators for the German BWR plants Isar 1 and Philipsburg 1, known as the double simulator project S30 (S31/S32). For both projects a computer based Configuration Management System (CMS) was required to overcome deficiencies of older simulator systems in terms of limited upgrade and maintenance capabilities and incomplete documentation. The CMS allows complete control over the entire simulator system covering all software- and hardware-items and therewith exceed quality assurance requirements as defined in ISO 9000-3 which gives recommendations for software configuration management only. The system is realized under the project using the UNIX based relational database system EMPRESS and is in use as a development- and maintenance-tool to improve simulator quality and ensure simulator configuration integrity

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

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)

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

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

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

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...

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.

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.)

The pressure suppression system

International Nuclear Information System (INIS)

Aust, E.

1985-01-01

Nuclear plants with boiling water reactors have a safety containment with a pressure suppression system (PSS). Proceeding on significant self-developments, today the three PSS-lines of General Electric Co. (GE), Kraftwerk Union AG (KWU) and ASEA-ATOM are predominant, which are currently represented by the MARK III type, the KWU type 72 and the BWR 75 containment. In addition, there are special developments for the nuclear ship propulsion and for the pressurized water reactors in the Soviet Union. Key design values of the PSS allow a first valuation of its loads during a hypothetical loss-of-coolant accident. (orig.) [de

Experimental prediction of tube support interaction characteristics in steam generators: Volume 2, Westinghouse Model 51 flow entrance region: Topical report

International Nuclear Information System (INIS)

Haslinger, K.H.

1988-06-01

Tube-to-tube support interaction characterisitics were determined experimentally on a single tube, multi-span geometry, representative of the Westinghouse Model 51 steam generator economizer design. Results, in part, became input for an autoclave type wear test program on steam generator tubes, performed by Kraftwerk Union (KWU). More importantly, the test data reported here have been used to validate two analytical wear prediction codes; the WECAN code, which was developed by Westinghouse, and the ABAQUS code which has been enhanced for EPRI by Foster Wheeler to enable simulation of gap conditions (including fluid film effects) for various support geometries

Replacement of the power plant Bruckhaeusl; Neubau des Kraftwerkes Bruckhaeusl

Energy Technology Data Exchange (ETDEWEB)

Egger, Andreas [TIWAG-Tiroler Wasserkraft AG, Innsbruck (Austria)

2011-07-01

The power plant Bruckhaeusl replaces the approx. 100 year-old power stations Einoeden and Soell/Leukental at the entrance to the Brixental in Tyrol. The design flow was raised to 12 from 5 m{sup 3}/s. Through the 2.2 km long penstock the water reaches to the Kaplan-S-turbine and is returned via a generously dimensioned underwater reservoir to the river. The residual water is delivered by a speed-regulated turbine at the weir. (orig.)

Franchise project for the Wettingen power plant; Konzessionsprojekt Kraftwerk Wettingen

Energy Technology Data Exchange (ETDEWEB)

Operto, G. [Elektrizitaetswerk der Stadt Zuerich EWZ, Zurich (Germany); Zimmermann, C. [Creato, Netzwerk fuer kreative Umweltplanung, Ennetbaden (Switzerland)

1999-02-05

Even today, after 65 years of operation, the Wettingen hydroelectric power plant of EWZ still retains many of its original components. They are technically obsolete and need to be replaced. Investments to be made by the municipal works of Zurich (EWZ) are of the order of magnitude of 60 to 70 million Swiss francs. These investments will not have paid back by the time the franchise expires in 2013; therefore, the city of Zurich is negotiating with the two franchise givers, the canton governments of Aargau and Zurich, seeking to obtain premature renewal of the franchise under which it is entitled to use the water rights. Thanks to the installation of a new turbine in the retaining weir, it will then be possible to increase residual water flow over the distance of 1300 metres twelve to twenty-fold. (orig.) [Deutsch] Noch heute, nach 65 Betriebsjahren, bestehen viele Anlageteile des EWZ-Flusskraftwerks Wettingen im Originalzustand. Sie sind technisch veraltet und muessen deshalb erneuert werden. Die geplante Erneuerung erfordert vom Elektrizitaetswerk der Stadt Zuerich (EWZ) Investitionen in der Groessenordnung von 60 bis 70 Millionen Franken. Da sich diese Investitionen bis zum Ablauf der Konzession im Jahre 2013 nicht amortisieren lassen, verhandelt die Stadt Zuerich mit den beiden Konzessionsgebern, den Kantonen Aargau und Zuerich, um eine vorzeitige Erneuerung der Konzession zur Nutzung der Wasserrechte zu erhalten. Dank dem Einbau einer neuen Dotierturbine im Stauwehr wird es dann moeglich sein, die Wasserfuehrung in der 1300 m langen Restwasserstrecke auf das Zwoelf- bis Zwanzigfache des heutigen Wertes zu erhoehen. (orig.)

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.)

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)

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.

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)

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.

TOC in water/steam cycles. Zittau Colloquium on Power Plant Chemistry; TOC in Wasser/Dampf-Kreislaeufen. Zittauer Kraftwerkschemisches Kolloquium

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

Many power plants use treated surface water as boiler feedwater and have difficulties in keeping within the limits for organic substances in feedwater (TOC < 200 ppb) or acid conductivity in steam condensate (< 0.2 {mu}S/cm). The characteristics of surface water and the role of organic substances in boiler feedwater are explained and discussed. [German] Viele Kraftwerke bereiten fuer die Erzeugung von Kesselspeisewasser Oberflaechenwasser auf und haben Probleme, die Richtlinien fuer organische Stoffe im Speisewasser (TOC < 200 ppb) oder Saeure-Leitfaehigkeit in Dampfkondensaten (< 0,2 {mu}S/cm) einzuhalten. Die besonderen Eigenschaften von Oberflaechenwaessern und die Bedeutung organischer Stoffe in Kesselspeisewasser werden erlaeutert und diskutiert. (orig.)

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.

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)

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...

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

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. 

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

Ceramica sphere production by a gel casting

International Nuclear Information System (INIS)

Santos, A.; Assis, G. de; Ferreira, R.A.N.; Ferraz, W.B.; Lopes, J.A.M.; Prado, M.A.S.; Miranda, O.; Drumond, F.J.

1987-01-01

The technology of (Th,U)O 2 microspheres production by gel casting and subsequente thermal treatment has been transferred from NUKEM GmbH assisted by Kraftwerk Union A.G., both West Germany, to NUCLEBRAS, where it was jointly adapted to produce microspheres suitable for pressing. As a result, there are now available various possibilities to produce ceramic spheres with different characteristics that can be used in different applications. Examples of these characteristics are the range of gel sphere diameters (200 to 5000 μmm) and the value of the specific surface (about 50m 2 /g for calcined (Th, U)O 2 and potentially higher than m 2 /g for other ceramic materials) (Author) [pt

Simulator testing of the Westinghouse aware alarm management system

International Nuclear Information System (INIS)

Carrera, J.P.; Easter, J.R.; Roth, E.M.

1997-01-01

Over the last year, Westinghouse engineers and operators from the Beznau nuclear power station (KKB), owned by the Nordostschweizerische Krafwerke AG of Baden, Switzerland, have been installing and testing the Westinghouse AWARE Alarm Management System in Beznau/SNUPPS operator training simulator, owned and operated by the Westinghouse Electric Corp., in Waltz Mill, PA, USA. The testing has focused primarily on validating the trigger logic data base and on familiarizing the utility's training department with the operation of the system in a real-time environment. Some of the tests have included plant process scenarios in which the computerized Emergency Procedures were available and used through the COMPRO (COMputerized PROcedures) System in conjunction with the AWARE System. While the results to date are qualitative from the perspective of system performance and improvement in message presentation, the tests have generally confirmed the expectations of the design. There is a large reduction in the number of messages that the control room staff must deal with during major process abnormalities, yet at times of relative minor disturbances, some additional messages are available which add clarification, e.g., ''Pump Trouble'' messages. The ''flow'' of an abnormality as it progresses from one part of the plant's processes to another is quite visible. Timing of the messages and the lack of message avalanching is proving to give the operators additional time to respond to messages. Generally, the anxiety level to ''do something'' immediately upon a reactor trip appears to be reduced. (author). 8 refs

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.

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...

Demolition of the FRJ-1 research reactor (MERLIN); Abbau des Reaktorblocks des Forschungsreaktors FRJ-1 (MERLIN)

Energy Technology Data Exchange (ETDEWEB)

Stahn, B.; Matela, K.; Zehbe, C. [Forschungszentrum Juelich GmbH (Germany); Poeppinghaus, J. [Gesellschaft fuer Nuklearservice, Essen (Germany); Cremer, J. [SNT Siempelkamp Nukleartechnik, Heidelberg (Germany)

2003-06-01

FRJ-2 (MERLIN), the swimming pool reactor cooled and moderated by light water, was built at the then Juelich Nuclear Research Establishment (KFA) between 1958 and 1962. In the period between 1964 and 1985, it was used for. The reactor was decommissioned in 1985. Since 1996, most of the demolition work has been carried out under the leadership of a project team. The complete secondary cooling system was removed by late 1998. After the cooling loops and experimental installations had been taken out, the reactor vessel internals were removed in 2000 after the water had been drained from the reactor vessel. After the competent authority had granted a license, demolition of the reactor block, the central part of the research reactor, was begun in October 2001. In a first step, the reactor operating floor and the reactor attachment structures were removed by the GNS/SNT consortium charged with overall planning and execution of the job. This phase gave rise to approx. The reactor block proper is dismantled in a number of steps. A variety of proven cutting techniques are used for this purpose. Demolition of the reactor block is to be completed in the first half of 2003. (orig.) [German] Der mit Leichtwasser gekuehlte und moderierte Schwimmbad-Forschungsreaktor FRJ-2 (MERLIN) wurde von 1958 bis 1962 fuer die damalige Kernforschungsanlage Juelich (KFA) errichtet. Von 1964 bis 1985 wurde er fuer Experimente mit zunaechst 5 MW und spaeter 10 MW thermischer Leistung bei einem maximalen thermischen Neutronenfluss von 1,1.10{sup 14} n/cm{sup 2}s genutzt. Im Jahr 1985 stellte der Reaktor seinen Betrieb ein. Die Brennelemente wurden aus der Anlage entfernt und in die USA und nach Grossbritannien verbracht. Seit 1996 erfolgen die wesentlichen Abbautaetigkeiten unter Leitung eines verantwortlichen Projektteams. Bis Ende 1998 wurde das komplette Sekundaerkuehlsystem entfernt. Dem Abbau der Kuehlkreislaeufe und Experimentiereinrichtungen folgte im Jahr 2000 der Ausbau der

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

Detection of beta radiation emitted from painted tiles

International Nuclear Information System (INIS)

Caldas, L.V.E.

1988-06-01

At the Kraftwerk Union (KWU), Erlangen, Federal Republic of Germany, it was confirmed that some types of painted tiles of italian origin were radioactive. In this work, performed at Institut fur Strahlenschutz, GSF, Munich, Germany, ultra-thin (60μm) thermoluminescent samples of CaSO 4 :Tm were used for the determination of absorved dose rates in air (at the tile surface and at the distance of 5 cm from it) and of transmission factors for different tissue equivalent material thicknesses. For comparison the absorved dose rates in air from cement walls without tile revestment and with simple tile revestment (tiles without painted ornaments) were also determined. In these cases the results were the same as those obtained normally from building materials. (author) [pt

Music and astronomy. II. Unitedsoundofcosmos

Science.gov (United States)

Caballero, J. A.; Arias, A.; Machuca, J. J.; Morente, S.

2017-03-01

We have been congratulated on the stage by a Nobel laureate (he was our curtain raiser), shocked audiences in rock concerts, written monthly on Musica Universalis , made the second concert in 3D in Spain after Kraftwerk and broadcasted it live in Radio 3, mixed our music with poetry read aloud by scientists, composed the soundtracks of CARMENES, QUIJOTE, ESTRACK and the Gaia first data release, made a videoclip on how computer simulates the formation of stars, played our music in planetariums, museums, observatories throughout Spain and at the end of the meeting of the ESO telescopes time allocation committee... All those moments will not be lost in time like tears in rain, but put together in Bilbao during the 2016 meeting of the Spanish Astronomical Society.

Paperless activation. Optimization potentials in power plants; Papierlose Freischaltung. Optimierungspotenziale im Kraftwerk

Energy Technology Data Exchange (ETDEWEB)

Goestenkors, Robert [Gemeinschaftskraftwerk Bergkamen der Evonik Steag GmbH und RWE Power AG, Bergkamen (Germany); Wieder, Ralf [Arbeitssicherheit fuer die Kraftwerke der Evonik Steag GmbH, Essen (Germany)

2011-03-15

Activation of plants or components is a very important task in any power plant. Evonik Steag started to use computer-assisted activation procedures many years ago. The operation management system SI {sup registered} was developed by the Evonik Steag subsidiary Evonik Energy Services; it comprises and activation module that manages the planning and execution of activation and connection processes for all aggregates of a power plant. The module was now extended to support also local activation operators. Instead of documents on paper, the activation operator receives a PDA description of the steps to be taken. The correct following of the procedure is ensured by a RFID chip connected at the activation site. Documentation of the activation is still carried out by signing a paper document. Further developments are still required to make the whole activation process at Bergkamen power plant paperless. The contribution describes the current status and the first step that was taken and then proceeds to describe the implemented paperless activation procedure.

The 'Weri' small hydro project; Kraftwerk Weri - Schlussbericht. Programm Kleinwasserkraftwerke

Energy Technology Data Exchange (ETDEWEB)

Burgener, H.-P. [EWBN Elektrizitaetswerk Brig-Naters AG, Brig-Glis (Switzerland); Bodenmann, M. [BSAP Ingenieure und Berater, Brig-Glis (Switzerland)

2008-11-15

This final report for the Swiss Federal Office of Energy (SFOE) reports on a project which augments an existing hydropower complex in Brig-Naters, Switzerland. A project for an additional hydropower installation below the last stage of the existing complex in the North Simplon Pass region is presented and discussed. Details are presented on the amount of water available, the boundary conditions pertaining and the technical concept proposed. Financial aspects, including support from the Swiss cost-covering remuneration scheme for electricity from renewable energy sources are also examined. The costs and economic viability of the project are discussed, as are environmental aspects to be taken into account during the construction and operation of the proposed power station.

Power plants in Australia and New Zealand; Kraftwerke in Australien und Neuseeland

Energy Technology Data Exchange (ETDEWEB)

Schneider, Joerg [Umweltbundesamt (Germany). Nachhaltige Energieversorgung; Kuhs, Gunter [Umweltbundesamt (Germany). Kraftwerksdaten; Boehringer, Alexander [Umweltbundesamt (Germany). CCS-Technologien

2009-07-01

Australia - rich in mineral resources - disposes among other things occurrence at energy commodities, as for example uranium and coal. Last contributes today with about 80% to the electricity production. After ratification of the Kyoto Protocol in March 2008 the Australian government has fixed the obliging reduction aims of carbon after which till 2020 a large part of the electricity demand from renewable energy and low-carbon power plants is to be covered. Although also New Zealand disposes of fossil energy commodities, today are covered quite about 70% of the electricity demand there about renewable energy - particularly water power and geothermics. The contribution provides information about the status quo of the power plant structures in Australia and New Zealand. (orig.)

Power plants at the bottom of the sea; Kraftwerke auf dem Meeresgrund

Energy Technology Data Exchange (ETDEWEB)

Wilhelm, Klaus

2011-07-01

The depths of the ocean are a hostile environment. In a bid to defy these adverse conditions, many organisms have teamed up to form close relationships called symbioses. Nicole Dubilier and her colleagues at the Max Planck Institute for Marine Microbiology in Bremen keep discovering new symbioses that provide these deep-sea inhabitants with a guaranteed energy supply. (orig.) [German] Die Tiefen der Ozeane sind ein lebensfeindlicher Ort. Um den widrigen Bedingungen zu trotzen, haben sich viele Organismen zu Lebensgemeinschaften zusammengeschlossen. Nicole Dubilier und ihre Mitarbeiter am Max-Planck-Institut fuer marine Mikrobiologie in Bremen entdecken immer wieder neue Symbiosen, mit denen die Tiefseebewohner ihre Energieversorgung sicherstellen.

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.

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.

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)

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

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

Simulator testing of the Westinghouse aware alarm management system

Energy Technology Data Exchange (ETDEWEB)

Carrera, J P; Easter, J R; Roth, E M [Westinghouse Electric Corp., Pittsburgh, PA (United States)

1997-09-01

Over the last year, Westinghouse engineers and operators from the Beznau nuclear power station (KKB), owned by the Nordostschweizerische Krafwerke AG of Baden, Switzerland, have been installing and testing the Westinghouse AWARE Alarm Management System in Beznau/SNUPPS operator training simulator, owned and operated by the Westinghouse Electric Corp., in Waltz Mill, PA, USA. The testing has focused primarily on validating the trigger logic data base and on familiarizing the utility`s training department with the operation of the system in a real-time environment. Some of the tests have included plant process scenarios in which the computerized Emergency Procedures were available and used through the COMPRO (COMputerized PROcedures) System in conjunction with the AWARE System. While the results to date are qualitative from the perspective of system performance and improvement in message presentation, the tests have generally confirmed the expectations of the design. There is a large reduction in the number of messages that the control room staff must deal with during major process abnormalities, yet at times of relative minor disturbances, some additional messages are available which add clarification, e.g., ``Pump Trouble`` messages. The ``flow`` of an abnormality as it progresses from one part of the plant`s processes to another is quite visible. Timing of the messages and the lack of message avalanching is proving to give the operators additional time to respond to messages. Generally, the anxiety level to ``do something`` immediately upon a reactor trip appears to be reduced. (author). 8 refs.

An undertaking planning game for the electricity supply industry

International Nuclear Information System (INIS)

Troescher, H.

1977-01-01

Planning games have been found satisfactory in many field in political and economic life. In particular the more convenient access to electronic calculators has made a contrinution to their wider use. It is therefore surprising that the first planning game which has become known for the electricity supply industry was first published in the year 1975. This is the planning game for the Bernischen Kraftwerke AG, which is based on a simplified model of a small electricity supply undertaking (EVU). This planning game was adapted in the RWE to the conditions in larger EVU and a few additional model components were added. Besides the general points of view on planning games for EVU the author deals with the extended planning game which is termed in the article PEW. (orig.) [de

Behaviour of steam turbine power control of large power plant units in case of network short-circuits

International Nuclear Information System (INIS)

Kindermann, W.; Fork, K.

1978-01-01

In order to investigate the behaviour of the turbine control system during strong pendulum motions, an analysis is carried out using a digital computer program by which the reactor, the turbine, the generator and, in a simplified way, the network can be simulated to the necessary degree. Plotter pictures can show the main physical quantities. In all cases, the turbine control system should be able to distinguish between strong pendulum amplitude with acceleration of the rotational angles and sudden release criteria. This demand can be satisfied by a simple adjustment in the Kraftwerk Union turbine control system. Only a few seconds after shut-off of a severe network failure, the turbines are back to their rated power, thus contributing to reliability of supply in this critical network situation. (orig.) [de

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

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.

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

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

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)

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.

Design issues concerning Iran's Bushehr nuclear power plant VVER-1000 conversion

International Nuclear Information System (INIS)

Carson, C.F.

1996-01-01

On January 8, 1995, the Atomic Energy Organization of Iran (AEOI) signed a contract for $800 million with the Russian Federation Ministry for Atomic Energy (Minatom) to complete Bushehr nuclear power plant (BNPP) unit 1. The agreement called for a Russian VVER-1000/320 pressurized water reactor (PWR) to be successfully installed into the existing German-built BNPP facilities in 5 yr. System design differences, bomb damage, and environmental exposure are key issues with which Minatom must contend in order to fulfill the contract. The AEOI under the Shah of Iran envisioned Bushehr as the first of many nuclear power plants, with Iran achieving 24 GW(electric) by 1993 and 34 GW(electric) by 2000. Kraftwerk Union AG (KWU) began construction of the two-unit plant near the Persian Gulf town of Halileh in 1975. Unit 1 was ∼80% complete and unit 2 was ∼50% complete when construction was interrupted by the 1979 Iranian Islamic revolution. Despite repeated AEOI attempts to lure KWU and other companies back to Iran to complete the plant, Western concerns about nuclear proliferation in Iran and repeated bombings of the plant during the 1980-1988 Iran-Iraq war dissuaded Germany from resuming construction

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.)

Training of power plant operating personnel

International Nuclear Information System (INIS)

Kraftwerksschule, E.V.

1986-01-01

In Germany, professional training of power plant operating personnel became an important issue in the fifties, when power plant parameters as well as complexity of instrumentation and control increased considerably. Working Groups of VGB Technische Vereiningung der Grosskraftwerketreiber e.v. (Association of Large Power Plant Operators) developed a professional career for power plant operating personnel and defined pre-requisites, scope and objectives of training. In 1957 the German utilities founded KRAFTWERKSSCHULE E.V. (kws) as a school for theoretical training and for guidance of practical training in the power plants. KWS is a non-profit organisation and independent of authorities. Today KWS has 127 members in Germany and in 6 other countries. The objectives of KWS include the training of: -Kraftwerker (control room operators; - Kraftwerksmesiter (shift supervisors); and - shift engineers; according the guidelines of the VGB

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.

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.

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)

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. 

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

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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.

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)

Development of alternative fuel for pressurized water reactors

International Nuclear Information System (INIS)

Cardoso, P.E.; Ferreira, R.A.N.; Ferraz, W.B.; Lameiras, F.S.; Santos, A.; Assis, G. de; Doerr, W.O.; Wehner, E.L.

1984-01-01

The utilization of alternative fuel cycles in Pressurized Water Reactors (PWR) such as Th/U and Th/Pu cycles can permit a better utilization of uranium reserves without the necessity of developing new power reactor concepts. The development of the technology of alternative fuels for PWR is one of the objectives of the 'Program on Thorium Utilization in Pressurized Water Reactors' carried out jointly by Empresas Nucleares Brasileiras S.A. (NUCLEBRAS), through its Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) and by German institutions, the Julich Nuclear Research Center (KFA), the Kraftwerk Union A.G. (KWU) and NUKEM GmbH. This paper summarizes the results so far obtained in the fuel technology. The development of a fabrication process for PWR fuel pellets from gel-microspheres is reported as well as the design, the specification, and the fabrication of prototype fuel rods for irradiation tests. (Author) [pt

Fuel cell power plants for decentralised CHP applications; Brennstoffzellen-Kraftwerke fuer dezentrale KWK-Anwendungen

Energy Technology Data Exchange (ETDEWEB)

Ohmer, Martin; Mattner, Katja [FuelCell Energy Solutions GmbH, Dresden (Germany)

2015-06-01

Fuel cells are the most efficient technology to convert chemical energy into electricity and heat and thus they could have a major impact on reducing fuel consumption, CO{sub 2} and other emissions (NO{sub x}, SO{sub x} and particulate matter). Fired with natural or biogas and operated with an efficiency of up to 49 % a significant reduction of fuel costs can be achieved in decentralised applications. Combined heat and power (CHP) configurations add value for a wide range of industrial applications. The exhaust heat of approximately 400 C can be utilised for heating purposes and the production of steam. Besides, it can be also fed directly to adsorption cooling systems. With more than 110 fuel cell power plants operating worldwide, this technology is a serious alternative to conventional gas turbines or gas engines.

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)

SOFC solid oxide fuel cell power plants for the decentralised electric energy supply; SOFC-Brennstoffzellen-Kraftwerke fuer die dezentrale elektrische Energieversorgung

Energy Technology Data Exchange (ETDEWEB)

Fogang Tchonla, Etienne

2012-07-01

To use the fuel cell economically, the efficiency of the system must still be raised so that it can be set up in the market. Within the scope of analysis on this topic, a 120-kW-SOFC-demonstration power plant was to be considered. Since not enough information about the demonstration power plant from the operator was available for the investigation, we had to calculate with the help of the known technical data of similar power plants. After that a model was build and simulated by means of MATLAB/Simulink. Before that the single power plant components were being described. Two of them (the boost converter as well as the inverter) were looked at more thoroughly. As a result of the analysis, it was found that a standard inverter which had been conceived for other applications, for example, Photovoltaic or Wind Power can also be used for fuel cells. Unfortunately, this was not the case for the added boost converter. It had to be precisely conceived for the used fuel cell type. After this discovery information was won for the realization of a 1-MW-Fuel Cell Power Plant. The topology of the 1-MW-power plant was fixed on the basis of the 120-kW-system. A parallel connection of eight 120-kW SOFC-fuel cell aggregates is intended, as well as a connection at the outlet side 120-kW boost converters. A standard inverter with 1 MW electrical power as well as a 1-MVA-transformer could be used for the realization of the 1-MW-power plant. The binding of the power plant in the three-phase current network was examined in view of the norms, laws and connection conditions. Beside the distinction of the operating forms of the power plant (parallel or isolated operation) the security of the plant was emphasized with regard to quick fault recognition, safe supply line isolation in the fault case as well as a compliance of the prescribed regulations. To verify the calculated results as well as the provided models, a 10-kW-labor sample was built and examined in the lab. This experimental

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

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

Spent fuel and fuel pool component integrity. Annual report, FY 1979

International Nuclear Information System (INIS)

Johnson, A.B. Jr.; Bailey, W.J.; Schreiber, R.E.; Kustas, F.M.

1980-05-01

International meetings under the BEFAST program and under INFCE Working Group No. 6 during 1978 and 1979 continue to indicate that no cases of fuel cladding degradation have developed on pool-stored fuel from water reactors. A section from a spent fuel rack stand, exposed for 1.5 y in the Yankee Rowe (PWR) pool had 0.001- to 0.003-in.-deep (25- to 75-μm) intergranular corrosion in weld heat-affected zones but no evidence of stress corrosion cracking. A section of a 304 stainless steel spent fuel storage rack exposed 6.67 y in the Point Beach reactor (PWR) spent fuel pool showed no significant corrosion. A section of 304 stainless steel 8-in.-dia pipe from the Three Mile Island No. 1 (PWR) spent fuel pool heat exchanger plumbing developed a through-wall crack. The crack was intergranular, initiating from the inside surface in a weld heat-affected zone. The zone where the crack occurred was severely sensitized during field welding. The Kraftwerk Union (Erlangen, GFR) disassembled a stainless-steel fuel-handling machine that operated for 12 y in a PWR (boric acid) spent fuel pool. There was no evidence of deterioration, and the fuel-handling machine was reassembled for further use. A spent fuel pool at a Swedish PWR was decontaminated. The procedure is outlined in this report

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)

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)

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.

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

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)

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

Technically-oriented operation management systems in conjunction with commercial DB systems

Energy Technology Data Exchange (ETDEWEB)

Lex, M.; Heselmann, B. [GiS mbH, Erlangen (Germany); Eschbach, P. [BASF Consult GmbH, Muenchen (Germany)

2001-07-01

Due to the liberalization of the electricity market, the efficiency and competitiveness of a power plant is increasingly measured at the cost per amount of energy generated. Thus, aspects of market-orientation and clearly cheaper electricity generation are in the foreground. Technically-oriented DP systems are necessary to save operating cost. These systems have structures differing from the mere business-oriented systems, because of the different frame conditions and operators' desire to stand out against rivalling competitors by technical and organizational measures. (orig.) [German] Die Effektivitaet und damit Konkurrenzfaehigkeit eines Kraftwerkes wird mit der Liberalisierung des Strommarktes verstaerkt an den Kosten je erzeugter Energieeinheit gemessen. Fuer den Betrieb ruecken damit Aspekte einer marktgerechten und somit deutlich kostenguenstigeren Stromerzeugung verstaerkt in den Vordergrund. Wer Betriebskosten sparen will, braucht technisch orientierte DV-Systeme, die aufgrund der unterschiedlichen Rahmenbedingungen und des Wunsches aller Anlagenbetreiber, sich durch technisch-organisatorische Massnahmen vom Wettbewerb vorteilhaft abzuheben, voellig andere Strukturen aufweisen als die betriebswirtschaftlich orientierten Systeme. (orig.)

Safety by simulation; Sicherheit durch Simulation

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, Eberhard [KSG Kraftwerks-Simulator-Gesellschaft mbH, Essen (Germany); GfS Gesellschaft fuer Simulatorschulung mbH, Essen (Germany)

2009-06-15

Simulator training is a key component in achieving and preserving on the long term the necessary expertise of plant personnel also required by the authorities. In this way, it makes an important contribution to the safe operation of nuclear power plants. Simulators are a component in the training of operating personnel of nuclear power plants which allows nuclear power plant operators to be prepared in a focused and practice-oriented way for their activity in everyday plant operation and for possible accident simulation. The simulator center is supported by 5 nuclear power plant operators: the German E.ON Kernkraft GmbH, RWE Power AG, EnBW Kraftwerke AG, and Vattenfall Europe Nuclear Energy GmbH companies as well as the Netherlands N.V. Electriciteits-Produktiemaatschappij Zuid-Nederland. They established a joint enterprise in Essen which performs in one central place the duty of simulator training incumbent upon all nuclear power plants. (orig.)

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

1986-12-01

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

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.

Regional virtual power plant. State of the art; Regionales virtuelles Kraftwerk. Eine Ist-Stand-Analyse

Energy Technology Data Exchange (ETDEWEB)

Seifert, Joachim; Meinzenbach, Andrea [TU Dresden (Germany). Professur fuer Gebaeudeenergietechnik und Waermeversorgung; Hartan, Joerg [VNG Gasspeicher GmbH, Leipzig (Germany). Fachgruppe fuer Automatisierung und Prozessleittechnik; Schegner, Peter [TU Dresden (Germany). Inst. fuer Elektrische Energieversorgung und Hochspannungstechnik; Rehkopf, Andreas [TU Bergakademie Freiberg (Germany). Inst. fuer Automatisierungstechnik

2013-04-15

The politically and socially desired rearrangement of the energy sector in Germany becomes very challenging for the regional and national utility company. In particular, the integration of renewable energy sources into the power structures is mentioned. The activities mainly focus on the electric power sector. Under this aspect, the contribution under consideration reports on two current research projects. These research projects look for solutions in order to operate micro-CHP systems in the network in addition to the isolated operation.

New erection program of the hydroelectric power plant Beznau. Das Neubauprojekt des hydraulischen Kraftwerkes Beznau

Energy Technology Data Exchange (ETDEWEB)

Bretscher, B; Hauenstein, W [NOK Nordostschweizerische Kraftwerke AG, Baden (Switzerland)

1992-02-21

The projected hydroelectric power plant at Beznau on the Aare river will produce about 43% more electric power than the present hydroelectric power plant. The water level and the buildings in the Aare will remain unchanged, so that the enviromental impact will be relativley slight. The project is in accordance with the building permit so that no adaptations on modifications will be required. (orig.).

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.

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

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 obras de G. Burmester – Hamburgo - Alemania Federal

Directory of Open Access Journals (Sweden)

Editorial, Equipo

1976-07-01

Full Text Available The enlargements of the Management Annexes of the firm «Nordwestdeutsche Kraftwerke, AK», were different in design due to their different locations and specific urban and architectural conditions. In the first case, the already existing building, known as the «hanging house» had an entity of its own which made it impossible to add an annex to it. It was then decided to build a new separate pavilion, about 20 m away, which would be joined to the first one by means of a corridor. The structure is of reinforced concrete, with two storeys and a basement, surrounded by gardens. In Oldenburg, the Management Building was situated in the centre of the city, right next to a park and it proved to be relatively easy to enlarge it, whereby the existing square got enclosed. The result came to represent a distinguished new approach, very much in accordance with the functions of the firm. The architectural configuration is sober, with classical lines.Las ampliaciones de los pabellones de Dirección de la Empresa «Nordwestdeutsche Kraftwerke, AG», en Stade y en Oldenburg, tuvieron unas características diferentes de concepción, debido a su emplazamiento distinto y a sus específicas condiciones urbanísticas y arquitectónicas. En el primer caso el edificio ya existente, conocido como «la casa suspendida», tenía una entidad propia, lo que hacía de todo punto imposible adicionarle un anexo. Se optó entonces por construir el nuevo pabellón aislado, a unos 20 m de distancia, uniéndolo al anterior por un paso cubierto. Es de hormigón armado, con dos plantas más sótano, y consigue mejorar el conjunto con la ampliación de zonas ajardinadas. En Oldenburg, el edificio de Dirección se encontraba en el centro de la ciudad, al borde de una amplia zona verde, y resultaba fácil realizar una ampliación, lo que permitió obtener un volumen único que cerraba la plaza allí existente, resultando un nuevo planeamiento de alta categoría, muy

ANALISIS EFEK KECELAKAAN WATER INGRESS TERHADAP REAKTIVITAS DOPPLER TERAS RGTT200K

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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

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.

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

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)

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.)

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

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.

Operator-centered technical documentation of the power plant control system. Betreibergerechte, betriebstechnische Dokumentation der Kraftwerks-Leittechnik

Energy Technology Data Exchange (ETDEWEB)

Welfonder, E

1986-01-01

The report - starting with an overview of the general structure of documentation - includes in chapter 3 an assortment of the main expectations to be had by the technical staff towards control system documentation. These are divided into: general basic requirements; testable compulsory requirements; practical recommendations and information for the manufacturer. In chapter 4 these documentation requirements are reflected to the present state of technical documentation. The main emphasis of the report however is laid on the sample documentation for one control system area presented in chapter 5. This sample documentation is based on a hierarchically structured and function related documentary method developed by the University of Stuttgart on the basis of the derived requirements and the present usual control system documentation. This function-related documentary method proves to be useful, not only for the technical staff in his rapid search for control system disturbances, but also offers - due to its clear and homogeneous meshed structure - considerable advantages for control system planning, projecting and initial start ups. As the presented documentation method is furthermore independent of the control system manufacturers, it is important that all participants try to use it uniformly.

New construction of the Kelchbach hydropower installation - Preliminary project; Vorprojekt Neubau Kraftwerk Kelchbach. Programm Kleinwasserkraftwerke - Schlussbericht

Energy Technology Data Exchange (ETDEWEB)

Kalbermatten, J.

2009-09-15

This final report for the Swiss Federal Office of Energy (SFOE) describes the preliminary project for the new construction of a small hydropower installation on the Kelchbach stream in Naters, Switzerland. After a pressure-pipe rupture, the old, over 100 year-old installation was closed down. The replacement installation is planned to increase power production. The works necessary for the realisation of this hydropower project are described and discussed. Several older studies on the replacement of the installation are listed. Three variants are presented and discussed as are hydrological data on the project. Cost estimates are presented and discussed. Estimates of energy production are also presented and discussed, as is the economic viability of the project. Environmental aspects of the project are also examined.

Lay up of a 750 t/h combined unit under the aspect of the liberalized power market; Konservierung eines 750-t/h-Kombi-Blockes unter dem Aspekt des liberalisierten Strommarktes

Energy Technology Data Exchange (ETDEWEB)

Reimschuessel, R.; Bellroth, A.; Borgwardt, P.; Krohn, K. [Kraftwerke Mainz-Wiesbaden AG, Mainz (Germany)

2003-07-01

We have been forced by the rough competition on the liberalised power market, especially in the last 15 months, to shut down our unit II, a 345 MW el. combined unit with gas turbine with following 750 t once-through boiler (Benson-type) and an efficiency of 44%, for a shorter or longer period of time. At the same time, availability must be ensured to cope with the price situation/development on the power market. Out of this difficult situation we developed a lay-up concept which allows shutdowns from one week up to six months and the restart within 75 hours. (orig.) [German] Durch die harten Wettbewerbsbedingungen des liberalisierten Strommarktes in Deutschland wurden wir gerade in den letzten beiden Jahren gezwungen, unser Kraftwerk II ueber kuerzere oder laengere Zeitraeume stillzulegen. Gleichzeitig sollte eine schnelle Verfuegbarkeit der Anlage gewaehrleistet sein, um der durch die Stromboerse gehandelten Preissituation gerecht werden zu koennen. Aus dieser schwierigen Situation heraus ist ein Konservierungskonzept entwickelt worden, das Stillstaende von einer Woche bis zu sechs Monaten und eine Wiederverfuegbarkeit innerhalb von 75 h erlaubt. (orig.)

Nuclear power: Hour of fog producers; Atomkraft: Stunde der Nebelwerfer

Energy Technology Data Exchange (ETDEWEB)

Rauner, M.; Schuh, H.

2004-03-04

Seven advanced nuclear power plants in Germany can withstand a frontal crash by a full-tanked Jumbo-Jet. But for five older plants even smaller planes can cause an hazard impossible to control. A fog generation around the power plants, favorized by operators and politicians, to camouflage this plants against terroristic flights is absurd because of the possibility of flight automation. However terrorists may attack reactors also from the ground, but how they can do is top secret. (GL) [German] Einem frontalen Aufprall eines voll getankten Jumbo-Jets mit hoher Geschwindigkeit koennen in Deutschland sieben moderne Kernkraftwerke standhalten. Bei fuenf aelteren Modellen kann dagegen selbst ein kleineres Flugzeug ein schwer beherrschbares Unglueck ausloesen. Obwohl Experten eine vorzeitige Schliessung solch alter Meiler fuer realistisch halten, ist die Verhandlungslage aufgrund ideologischer Einfluesse verfahren. Die von Betreibern und Politikern gern gepriesenen Nebelwerfer zur Tarnung der Kraftwerke sind wegen der Moeglichkeit des Instrumentenfluges sinnlos. Die beste Abwehr bieten vorgelagerte Schutzbauten aus Beton. Jedoch koennen Terroristen Reaktoren auch vom Boden aus gefaehrden, wie, ist natuerlich geheim.

33. MPA seminar 2007. Proceedings; 33. MPA Seminar 2007. Vortraege

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

In a single PDF file, the CD-ROM contains all papers presented at the 33. MPA Seminar in Stuttgart. Subjects: Life management of nuclear facilities: Materials, integrity analysis, fracture mechanics; Behaviour of welds; Material development and qualification for power plants with enhanced steam parameters; monitoring concepts (e.g. state monitoring of components, test concepts); Design of pipelines with flanged joints; Assembly and joining technology for flanged joints; Non-destructive testing in plant engineering; Materials for new nuclear reactors. Many of the papers are available as separate items in this database. [German] In einer einzigen PDF-Datei sind auf der CD-ROM alle Vortraege enthalten, die auf dem 33. MPA-Seminar in Stuttgart gehalten wurden. Die Themenschwerpunkte sind: Lebensdauermanagement kerntechnischer Anlagen - Werkstoffverhalten, Integritaetsanalyse, Bruchmechanik; Verhalten von Schweissverbindungen; Werkstoffentwicklung und -qualifizierung fuer Kraftwerke mit erhoehten Dampfparametern; Ueberwachungskonzepte (z.B. Zustandsueberwachung von Komponenten, Pruefkonzepte); Auslegung von Rohrleitungen mit Flanschverbindungen; Montage- und Dichtungstechnik fuer Flanschverbindungen; Zerstoerungsfreie Pruefung in der Anlagentechnik; Werkstoffe fuer neue Kernreaktoren. Ein grosser Teil der Vortraege wurde separat aufgenommen.

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

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

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 ...

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.)

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.

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

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.

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.

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)

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.

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)

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.

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.

Enhancement of the Haemmerli hydro power installation in Lenzburg, Switzerland; Gemeinde Lenzburg (AG). Ausbau Kraftwerk Haemmerli - Vorstudie

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-08-15

This preliminary report for the Swiss Federal Office of Energy (SFOE) presents a project on the refurbishment of an old industrial small hydro installation on the Aabach stream in Lenzburg, Switzerland. The state of the existing installation is described as is the station's concession. The proposals for the renewal of this installation are described and discussed. The necessary building work and the installations required are examined. Investment costs, operating and maintenance costs and expected profitability are discussed. The report is completed with suggestions for further work.

Renewal of the Stanipac hydropower plant in Burgdorf; Febacom AG - Burgdorf. Gesamterneuerung Kraftwerk Stanipac - Burgdorf. Vorprojektstudie - Schlussbericht

Energy Technology Data Exchange (ETDEWEB)

Hintermann, M.

2007-07-01

This report for the Swiss Federal Office of Energy (SFOE), takes a look at the results of a preliminary study on the renewal of the Stanipac hydropower installation in Burgdorf, Switzerland. This small hydropower plant is the first of a series of nine installations situated along a canal. Proposals for the renewal of the installation are discussed. Topographical and hydrological factors are presented and discussed. Also, data on water quantities is presented. The existing installation dating from 1946 is described. Three variants for the renewal are noted and the appropriate installations, their costs and their production estimates are discussed. A best solution is proposed and the necessary installations are described in more detail, as is the economic viability of the scheme. Photos of the existing installation, figures on the proposed installation and project sketches are presented.

Fifty years of Erlangen radiochemistry

International Nuclear Information System (INIS)

Morell, W.

2007-01-01

On June 29, 2006, the Radiochemical Laboratory of AREVA NP GmbH (formerly Siemens AG) in Erlangen celebrated its fiftieth anniversary. The occasion was marked by an event attended by more than 1,000 guests, among them Werner Gebauhr, the 85-year-old founder and first head of the Laboratory; the Managing Directors of AREVA NP GmbH, Ralf Gueldner and Ruediger Steuerlein; representatives of universities, research institutions, power utilities, and public authorities. The present head of the Radiochemical Laboratory, Wilfred Morell, sketched the highlights of the work performed over the past fifty years, which ranged from solid-state and very-high-purity materials technologies to development and service activities for nuclear technology. Manfred Erve, head of the Technical Center of AREVA NP GmbH, of which the Radiochemical Laboratory is a part, emphasized the changes in priorities over the past fifty years, which had always been met successfully by Radiochemistry. In the scientific part of the event, Wolfgang Schwarz (E.ON Kernkraftwerk GmbH, KKW Isar), Ulf Ilg (EnBW Kraftwerk AG, KKW Philippsburg), and Hans-Josef Allelein (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH) explained 3 major subject areas in which Erlangen Radio-chemistry over many years has contributed basic findings (see other articles in this atw issue). On the occasion of the anniversary, a comprehensive booklet was published under the title of '50 Jahre Radiochemie Erlangen - 1956-2006'. (orig.)

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.

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

Testing of corrosion resistant materials for evaporation plants for waste water from wet scrubbing of flue gas from power plants; Erprobung korrosionsbestaendiger Werkstoffe fuer Eindampfanlagen fuer Abwasser aus der Rauchgasreinigung von Grossfeuerungsanlagen

Energy Technology Data Exchange (ETDEWEB)

Riedel, G. [Institut fuer Korrosionsschutz GmbH, Dresden (Germany); Stenner, F.; Brill, U. [Krupp-VDM GmbH, Werdohl (Germany)

2001-07-01

High alloyed superaustenitic steels and NiCrMo alloys are recommended in consequence of the results of extensive laboratory corrosion experiments under the strong corrosive conditions with up to 360 g chloride content at temperatures up to 85 C. Because results of laboratory corrosion tests are only of limited relevance to the behaviour in practice, field tests were carried out with immersion of welded materials and of heat exchanger tubes under operating conditions of an evaporation plant for waste water from flue gas desulphurization of a coal-fired power plant. Different kinds of high alloy superaustenitic steels and NiCrMo alloys were studied as TIG-welded specimens in immersion tests. (orig.) [German] Hochlegierte Sonderedelstaehle und NiCrMo-Legierungen empfehlen sich aufgrund der Ergebnisse umfassender Laboruntersuchungen unter den stark korrosiven Bedingungen fuer Eindampfanlagen fuer Abwasser aus der Nassreinigung von Rauchgasen von Grossfeuerungsanlagen mit bis zu 360 g/l Chloridgehalt und Temperaturen bis zu 85 C. Weil aber Ergebnisse von Laborpruefungen nur begrenzte Aussagefaehigkeit fuer das Verhalten unter Praxisbedingungen haben, wurden Feldversuche mit der Auslagerung geschweisster Werkstoffe und von Waermetauscherrohren unter Betriebsbedingungen einer Eindampfanlage fuer Abwasser aus der Rauchgasentschwefelung eines kohlebefeuerten Kraftwerks durchgefuehrt. (orig.)

Implementation of strength pareto evolutionary algorithm II in the multiobjective burnable poison placement optimization of KWU pressurized water reactor

International Nuclear Information System (INIS)

Gharari, Rahman; Poursalehi, Navid; Abbasi, Mohmmadreza; Aghale, Mahdi

2016-01-01

In this research, for the first time, a new optimization method, i.e., strength Pareto evolutionary algorithm II (SPEA-II), is developed for the burnable poison placement (BPP) optimization of a nuclear reactor core. In the BPP problem, an optimized placement map of fuel assemblies with burnable poison is searched for a given core loading pattern according to defined objectives. In this work, SPEA-II coupled with a nodal expansion code is used for solving the BPP problem of Kraftwerk Union AG (KWU) pressurized water reactor. Our optimization goal for the BPP is to achieve a greater multiplication factor (K-e-f-f) for gaining possible longer operation cycles along with more flattening of fuel assembly relative power distribution, considering a safety constraint on the radial power peaking factor. For appraising the proposed methodology, the basic approach, i.e., SPEA, is also developed in order to compare obtained results. In general, results reveal the acceptance performance and high strength of SPEA, particularly its new version, i.e., SPEA-II, in achieving a semioptimized loading pattern for the BPP optimization of KWU pressurized water reactor

The turbine oil fire in the nuclear power plant, Muehleberg

International Nuclear Information System (INIS)

Lutz, H.R.

1972-01-01

At 21.15 hours on the evening of the 28th July 1971, a turbine oil fire broke out in the Nuclear Power Plant Muehleberg of the Bernische Kraftwerke AG, resulting in damage amounting to around 20 million Swiss Francs and a delay of some ten months in putting the plant into operation. The plant is equipped with a General Electric boiling water reactor and two BBC saturated steam turbines. Up to the time of the fire, both turbo-sets had already been run singly up to their full capacity of 160 MWe and the initial trials with both sets working parallel were shortly due to be carried out. Following the outbreak of fire, the causes of which are described in the contributions of the authors Hagn, L. and H. Huppmann and Christian, H. and H. Grupp, fire fighting action was immediately taken, in line with the emergency measures laid down in the operating regulations. With the assistance of the Berne City Fire Brigade, the blaze in the roof of the turbine hall was first extinguished and the spreading cable conflagration then fought, using foam and water. (orig.) [de

Firewall systems for protection of data communication in power stations; Firewall-Systeme zum Schutz der Datenkommunikation in Kraftwerken

Energy Technology Data Exchange (ETDEWEB)

Schoenfeld, P [Siemens AG KWU (Germany)

1999-12-31

Networking of power plant computer systems is becoming increasingly common. Furthermore, instrumentation and control systems are being connected with general power plant networks to make process information available to administrative personnel. This increases the risk of accidental or intentional access from outside the system (e.g. by hackers). Firewall systems are used to prevent such outside access. A firewall is the sole gateway between two networks which are to be kept separate, and is used to filter and control access to the protected network. Cryptography and personal chip cards are also used to provide additional protection. (orig.) [Deutsch] Rechnersysteme im Kraftwerk werden heute mehr und mehr vernetzt. Auch werden Rechnersysteme zum Messen, Steuern und Regeln (sogenannte Instrumentation and Control Systems) mit allgemeinen Kraftwerksnetzen verbunden, um Prozessinformationen auch in der Verwaltung zugaenglich zu machen. Damit waechst die Gefahr von zufaelligen oder beabsichtigten Eingriffen von aussen (z.B. Hacker). Zum Schutz vor solchen Eingriffen von aussen werden sogenannte Firewall-Systeme eingesetzt. Ein Firewall ist der alleinige Uebergang zwischen zwei zu trennenden Netzen und dient zur Filterung und Kontrolle der Zugriffe auf ein zu schuetzendes Netz. Ergaenzende Schutzmassnahmen sind der Einsatz kryptographischer Verfahren, sowie persoenlicher Chipkarten. (orig.)

Firewall systems for protection of data communication in power stations; Firewall-Systeme zum Schutz der Datenkommunikation in Kraftwerken

Energy Technology Data Exchange (ETDEWEB)

Schoenfeld, P. [Siemens AG KWU (Germany)

1998-12-31

Networking of power plant computer systems is becoming increasingly common. Furthermore, instrumentation and control systems are being connected with general power plant networks to make process information available to administrative personnel. This increases the risk of accidental or intentional access from outside the system (e.g. by hackers). Firewall systems are used to prevent such outside access. A firewall is the sole gateway between two networks which are to be kept separate, and is used to filter and control access to the protected network. Cryptography and personal chip cards are also used to provide additional protection. (orig.) [Deutsch] Rechnersysteme im Kraftwerk werden heute mehr und mehr vernetzt. Auch werden Rechnersysteme zum Messen, Steuern und Regeln (sogenannte Instrumentation and Control Systems) mit allgemeinen Kraftwerksnetzen verbunden, um Prozessinformationen auch in der Verwaltung zugaenglich zu machen. Damit waechst die Gefahr von zufaelligen oder beabsichtigten Eingriffen von aussen (z.B. Hacker). Zum Schutz vor solchen Eingriffen von aussen werden sogenannte Firewall-Systeme eingesetzt. Ein Firewall ist der alleinige Uebergang zwischen zwei zu trennenden Netzen und dient zur Filterung und Kontrolle der Zugriffe auf ein zu schuetzendes Netz. Ergaenzende Schutzmassnahmen sind der Einsatz kryptographischer Verfahren, sowie persoenlicher Chipkarten. (orig.)

Implementation of strength pareto evolutionary algorithm II in the multiobjective burnable poison placement optimization of KWU pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Gharari, Rahman [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Poursalehi, Navid; Abbasi, Mohmmadreza; Aghale, Mahdi [Nuclear Engineering Dept, Shahid Beheshti University, Tehran (Iran, Islamic Republic of)

2016-10-15

In this research, for the first time, a new optimization method, i.e., strength Pareto evolutionary algorithm II (SPEA-II), is developed for the burnable poison placement (BPP) optimization of a nuclear reactor core. In the BPP problem, an optimized placement map of fuel assemblies with burnable poison is searched for a given core loading pattern according to defined objectives. In this work, SPEA-II coupled with a nodal expansion code is used for solving the BPP problem of Kraftwerk Union AG (KWU) pressurized water reactor. Our optimization goal for the BPP is to achieve a greater multiplication factor (K-e-f-f) for gaining possible longer operation cycles along with more flattening of fuel assembly relative power distribution, considering a safety constraint on the radial power peaking factor. For appraising the proposed methodology, the basic approach, i.e., SPEA, is also developed in order to compare obtained results. In general, results reveal the acceptance performance and high strength of SPEA, particularly its new version, i.e., SPEA-II, in achieving a semioptimized loading pattern for the BPP optimization of KWU pressurized water reactor.

Loose parts, vibration and leakage monitoring methods and systems to increase availability, transparency and lifetime of power plants

International Nuclear Information System (INIS)

Streicher, V.; Jax, P.; Ruthrof, K.

1987-01-01

This paper deals with three stand-alone-systems as an aid to check the mechanical integrity of the primary circuit of nuclear power plants. The main goals of these systems are early detection of faults and malfunctions, the facilitation of fault clearance, the avoidance of sequential damage and reduction of inspection time and cost. Obviously the proper application of the systems as well as the measures they induce and make possible increase the availability of the plant and contribute to lifetime extension. In order to detect, identify and pinpoint the changes in component structure such as loosened connections, broken parts or components, loose or loosened particles, fatigued materials, cracks and leaks, specialized monitoring systems were developed by KWU (Kraftwerk Union AG) during the last ten years. Requirements concerning vibration, loose parts and leakage monitoring are part of German guidelines and safety standards. Therefore systems for these applications are implemented in most of the nuclear power plants in Western Germany. This paper presents newly developed, microprocessor-based systems for loose parts monitoring, vibration monitoring and leakage monitoring and also includes specific case histories for the different topics

Possibilities under the `Kreislaufwirtschaft- und Abfallgesetz` for the recycling or for energy generation from waste with a high calorific value having undergone mechanical-biological conditioning; Moeglichkeiten der energetischen und stofflichen Verwertung von heizwertreichen Reststoffen aus der mechanisch-biologischen Restabfallbehandlung im Rahmen des Kreislaufwirtschafts- und Abfallgesetzes

Energy Technology Data Exchange (ETDEWEB)

Franke, J.; Fricke, K. [Ingenieurgemeinschaft Witzenhausen Fricke und Turk GmbH, Witzenhausen (Germany)

1998-12-31

This (partial) project has the following aims: to describe comprehensively the possibilities for the recycling, or generation of energy from, waste with a high calorific value having undergone mechanical-biological conditioning; further, to formulate demands regarding the quality of the separated partial fractions. This basic study takes all relevant, commercial thermal processes into account (power plants, cement works, blast furnaces, etc.). Furthermore, the question is investigated of whether the thermal waste processing plants in the area of the Suedhessische Arbeitsgemeinschaft Abfall (SAGA) are suitable for waste utilization. An environmental compatibility statement is made, and the economic and legal boundary conditions are studied. (orig.) [Deutsch] Ziel des (Teil-)Forschungsvorhabens soll es sein, die Moeglichkeiten der energetischen und stofflichen Verwertung heizwertreicher Abfaelle aus der mechanisch-biologischen Restabfallbehandlung umfassend darzustellen und die Anforderungen an die Qualitaet der abgretrennten Teilfraktionen zu formulieren. Bei der Grundlagenermittlung sollen alle relevanten auf dem Markt angebotenen thermischen Verfahren (Kraftwerke, Zementwerke, Hochoefen usw.) mit einbezogen werden. Weiterhin sollen die im SAGA-Gebiet (Suedhessische Arbeitsgemeinschaft Abfall) vorhandenen thermsichen Anlagen auf ihre Eignung zur energetischen bzw. stofflichen Verwertung hin ueberprueft werden. Neben der Bewertung der Umweltvertraeglichkeit werden die oekonomischen und rechtlichen Rahmenbedingungen untersucht. (orig.)

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

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%.

The use of ozone as microbiocide in cooling water treatment - experiences with an ''All-Organic'' program; Ozon als Mikrobizid bei der Kuehlwasserbehandlung - Praxiserfahrungen mit einem ''All-Organic'' Programm

Energy Technology Data Exchange (ETDEWEB)

Noks, E.; Olkis, A. [Deutsche Nalco Chemie GmbH, Frankfurt am Main (Germany); Kleinstueck, R. [Bayer AG, Leverkusen (Germany); Johnson, D.A. [Nalco Chemical Co., Naperville (United States)

1999-10-01

Since 1995, at the plant EZH Rotterdam, the practice of using ozone as microbiocide in the cooling circuit that uses a poor quality makeup water has proven to be successful. The strict limits for aqueous and emission protection from the plant can be maintained. Careful monitoring of the system is a key to the success of the cooling water treatment. The determining factor in judging the microbiological activity and effectiveness of the ozone addition was the regular determination of ATP values and total bacterial count in the system. Limiting ozone concentrations to the amount needed by the system helps to keep the degradation rate of the organic inhibitors under control and, by minimizing the treatment level, the treatment functions in an environmentally friendly and effective manner. Recovery rates of approximately 80% were measured for the phosphonate PBTC, the stabilizers and dispersants. The corrosion rates for steel and copper are low considering the makeup water quality. The combination of inhibitors controlled the tendency for deposits to form. Previous research in the laboratory and industry have shown that the basic components of the cooling water formulations, phosphonates, react very differently when placed in contact with ozone. In order of decreasing ozone stability they are: PBTC>HEDP>ATMP. A six-month trial was performed in a cooling circuit at Bayer AG in Dormagen using a PBTC-containing, stabilized phosphate treatment program. In spite of the high half-life of the cooling water in the system, it was found that the PBTC was stable with a recovery rate of 50-80%. (orig.) [German] Der seit 1995 praktizerte Einsatz von Ozon als Mikrobizid im Kuehlkreislauf des Kraftwerks EZH Rotterdam mit relativ stark vorbelastetem Zusatzwasser ist eine erfolgreiche Problemloesung. Die strengen Auflagen zum Gewaesser- und Immissionsschutz koennen vom Kraftwerk eingehalten werden. Sorgfaeltige Ueberwachung des Systems ist ein Kernstueck des Erfolgs der

Utilization of online-analysis of ashes in the power plant Neurath; Verwendung der Online-Ascheanalyse im Kraftwerk Neurath

Energy Technology Data Exchange (ETDEWEB)

Hoffmann, Horst [RWE Power, Neurath (Germany); Gocht, Dietmar [Evonik Energy Services GmbH, Essen (Germany)

2008-07-01

The authors of the contribution under consideration report on the use of on-line ash analysis in the power station Neurath (Federal Republic of Germany). On the basis of concrete data from the plant operation it is shown, how the complex closed-loop-monitoring of soot blowing adjusts the effects of changing coal qualities on the contamination reliably. The system preventively reacts to alterations of the coal qualities, since the analyses are accessible online. It has been shown during the continuous operation of the power station that the soot blowing can be accomplished further automatically by these measures also under altered circumstances due to the changing coal qualities. Thus, the personnel of the power station is relieved clearly.

Nature's powerhouse. Innovative technologies for a more sustainable future; Kraftwerk Natur. Innovative Technologien fuer mehr Nachhaltigkeit

Energy Technology Data Exchange (ETDEWEB)

Anon.

2013-09-01

Across the globe, our hunger for energy continues to grow. Yet climate change and dwindling fossil fuel supplies are forcing us to rethink our energy policy and turn increasingly to renewable resources. Achieving a sustainable energy mix and eco-friendly mobility options demands innovative technologies. And that is where Linde's gas and plant engineering specialists come in, developing efficient processes and providing crucial momentum for a greener future. (orig.)

Modernisation of hydrogenerators. Upgrading of power plants for more efficiency; Modernisierung von Hydrogeneratoren. Kraftwerks-Upgrade fuer mehr Effizienz

Energy Technology Data Exchange (ETDEWEB)

Allen, John

2012-07-01

Ever since the construction of the first alternating current hydroelectric power plant with a performance of 12.5 kW in the year 1882, the number and performance of hydroelectric power plants had increased substantially. For example, the hydroelectric power plant at the Three Gorges Dam in the People's Republic of China has a total performance of 22,500 MW. The isolation systems of the hydrogenerators have a limited lifetime and have to be exchanged after fifty years usually. Under this aspect, the authors of the contribution under consideration reports on the upgrading of hydrogenerators for more efficiency.

Micro-size cogeneration plants and virtual power plants. New energy landscapes; Mikro-KWK und virtuelle Kraftwerke. Neue Energielandschaften

Energy Technology Data Exchange (ETDEWEB)

Roon, Serafin von [Forschungsstelle fuer Energiewirtschaft e.V., Muenchen (Germany)

2009-07-01

Combined heat and power generation is an established technology. With micro-size cogeneration units, the technology is now available to private single or multiple dwellings and for decentral power supply of residential blocks. With the right political boundary conditions and integrated into virtual power stations, this is an option for enhanced use of renewable energy sources and for decentral, flexible and climate-friendly heat and power generation in buildings. Economic efficiency analyses by experts, high utilisation rates, innovative developments of the manufacturers and a positive public image are all in favour of a great future for micro-size cogeneration units. (orig.)

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.

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.

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].

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.)

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

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.

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.

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

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

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)

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)

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

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

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.

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.

Training simulators in nuclear power plants: Experience, programme design and assessment methodology. Proceedings of a specialists' meeting

International Nuclear Information System (INIS)

1997-11-01

Simulators became an indispensable part of training world-wide. Therefore, international exchange of information is important to share the experience gained in different countries in order to assure high international standards. A second aspects is the tremendous evolution in the computing capacities of the simulator hardware and the increasing functionality of the simulator software. This background has let the IAEA to invite the simulator experts for an experience exchange. The German Simulator Centre in Essen, which is operated by the companies KSG and GfS, was asked to host this Specialists' Meeting. The Specialists' Meeting on ''Training Simulators in Nuclear Power Plants: Experience, Programme Design and Assessment Methodology'' was organized by IAEA in-cooperation with the German Simulator Centre operated by KSG Kraftwerks-Simulator-Gesellschaft mbH and GfS Gesellschaft fuer Simulatorschulung mbH and was held from 17 - 19 November 1997 in Essen, Germany. The meeting focused on developments in simulation technology, experiences with simulator upgrades, utilization of computerized tools as support and complement of simulator training, use of simulators for other purposes. The meeting was attended by 50 participants from 16 countries. In the course of four sessions 21 technical presentations were made. The present volume contains the papers by national delegates at the Specialists' Meeting

Training simulators in nuclear power plants: Experience, programme design and assessment methodology. Proceedings of a specialists` meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

Simulators became an indispensable part of training world-wide. Therefore, international exchange of information is important to share the experience gained in different countries in order to assure high international standards. A second aspects is the tremendous evolution in the computing capacities of the simulator hardware and the increasing functionality of the simulator software. This background has let the IAEA to invite the simulator experts for an experience exchange. The German Simulator Centre in Essen, which is operated by the companies KSG and GfS, was asked to host this Specialists` Meeting. The Specialists` Meeting on ``Training Simulators in Nuclear Power Plants: Experience, Programme Design and Assessment Methodology`` was organized by IAEA in-cooperation with the German Simulator Centre operated by KSG Kraftwerks-Simulator-Gesellschaft mbH and GfS Gesellschaft fuer Simulatorschulung mbH and was held from 17 - 19 November 1997 in Essen, Germany. The meeting focused on developments in simulation technology, experiences with simulator upgrades, utilization of computerized tools as support and complement of simulator training, use of simulators for other purposes. The meeting was attended by 50 participants from 16 countries. In the course of four sessions 21 technical presentations were made. The present volume contains the papers by national delegates at the Specialists` Meeting Refs, figs, tabs

CBAS - efficient coal management for optimised operation and minimised cost; CBAS - Betriebsoptimierung und Kostenminimierung durch effizientes Kohlenmanagement

Energy Technology Data Exchange (ETDEWEB)

Pechtl, P.; Petek, J.; Shea, S.

2000-07-01

The 'Coal Bland Automation System' CBAS developed by Praxis Engineers, Inc. is a software application which simulates the path of coal from the dispatching station to the burners. The combustion characteristics of coal mixtures are predicted, and the fuel quality can be controlled hours before the coal arrives at the burners. Detailed modelling of the flow patterns in the mixing bunkers and grinding bunkers, time variations of the coal mixture properties at the bunker outlet can be predicted, and the coal mixture can be varied accordingly to account for load peaks. [German] Das von Praxis Engineers, Inc. entwickelte 'Coal Bland Automation System' CBAS ist eine online Softwareapplikation, die den Weg aller in einem Kraftwerk eingesetzten Kohlensorten vom Verladeplatz bis hin zu den Brennern mathematisch simuliert. Die Eigenschaften beliebiger Mischungen zwischen den Kohlen werden vorausgesagt und die Qualitaet des Brennstoffs an den Brennern kann geregelt werden, auch Stunden bevor die Kohlenmischung tatsaechlich an den Brennern ankommt. Aufgrund der detaillierten Modellierung des Fliessverhaltens in den Mischbunkern und den Bunkern der Kohlemuehlen ist es moeglich, die zeitliche Veraenderung der Eigenschaften der Kohlenmischung am Austritt aus den Bunkern vorherzusagen. Dadurch kann das Mischungsverhaeltnis der Kohlen rascher an die Lastanforderungen angepasst werden, was z.B. zum 'Einfangen' von lukrativen Lastspitzen genutzt werden kann. (orig.)

Aspects of remote maintenance in an FRG reprocessing plant from the manufacturer's viewpoint

International Nuclear Information System (INIS)

Zeitzchel, G.; Tennie, M.; Saal, G.

1986-01-01

In April 1986 a consortium led by Kraftwerk Union AG was commissioned by the German society for nuclear fuel reprocessing (DWK) to build the first West German commercial reprocessing plant for spent fuel assemblies. The main result of the planning efforts regarding remote maintenance operations inside the main process building was the introduction of FEMO technology (FEMO is an acronym based on German for remote handling modular technique). According to this technology the two cells in which the actual reprocessing (which is based on the PUREX technique) takes place are provided with frames to accommodate the process components (tanks, pumps, agitators, etc.), each frame together with the components which it supports forming one module. The two cells are inaccessible and windowless. For handling operations each cell is equipped with an overhead crane and a crane-like manipulator carrier system (MTS) with power manipulator. Viewing of the operations from outside the cells is made possible by television (TV) cameras installed at the crane, the MTS, and the manipulator. This paper addresses some examples of problems that still need to be solved in connection with FEMO handling. In particular, the need for close cooperation between the equipment operator, the component designer, the process engineer, the planning engineer, and the licensing authorities will be demonstrated

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.

High-temperature stable absorber coatings for linear concentrating solar thermal power plants; Hochtemperaturstabile Absorberschichten fuer linear konzentrierende solarthermische Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Hildebrandt, Christina

2009-03-23

This work describes the development of new absorber coatings for different applications - para-bolic trough and linear Fresnel collectors - and operating conditions - absorber in vacuum or in air. The demand for higher efficiencies of solar thermal power plants using parabolic trough technology results in higher temperatures in the collectors and on the absorber tubes. As heat losses increase strongly with increasing temperatures, the need for a lower emissivity of the absorber coating at constant absorptivity arises. The linear Fresnel application envisions ab-sorber tubes stable in air at high temperatures of about 450 C, which are to date commercially not available. This work comprises the theoretical background, the modeling and the fabrication of absorber tubes including the technology transfer to a production-size inline sputter coater. In annealing tests and accompanying optical measurements, degradation processes have been observed and specified more precisely by material characterization techniques. The simulations provided the capability of different materials used as potential IR-reflector. The highest selectivity can be achieved by applying silver which consequently has been chosen for the application in absorber coatings of the parabolic trough technology. Thin silver films how-ever need to be stabilized when used at high temperatures. Appropriate barrier layers as well as process and layer parameters were identified. A high selectivity was achieved and stability of the absorber coating for 1200 h at 500 C in vacuum has been demonstrated. For the application in air, silver was also analyzed as a potential IR-reflector. Even though the stability could be increased considerably, it nevertheless proved to be insufficient. The main factors influencing stability in a positive way are the use of higher quality polishing, additional barrier layers and adequate process parameters. This knowledge was applied for developing coatings which are stable in air at temperatures of 500 C for more than 1000 h, using alternative IR-reflectors. The minimum emissivity which can be achieved depends on economic aspects. (orig.)

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)

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%.

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.

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

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%.

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

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.

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)

Determination of a CO sub 2 rating formula for fossil-fired, electricity-generating power plants. Zur Festlegung einer CO sub 2 -Steuerformel fuer fossil-befeuerte, stromerzeugende Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Seifritz, W [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung

1991-12-01

Dr. Martin Proske was right in Ref (1) to point to the fact that a CO{sub 2}-tax has to take into account the quality of the secondary energy carrier, too. In the opinion of the author, however, the tax-formula of M. Proske has still to be modified if CO{sub 2}-free fossil power stations were introduced. Failing this, the development of CO{sub 2}-free power stations with the necessary removal and disposal of CO{sub 2} would be not attractive although this future type of a power station could substantially contribute to the climate-neutrality of fossil fuels. A corresponding modification of the tax-formula is proposed. (orig.).

Energy: Solar electricity gaining second wind. - The sun as a power plant. Energie: Sonnen-Strom im Aufwind. - Das Kraftwerk Sonne

Energy Technology Data Exchange (ETDEWEB)

Frisch, F; Kippenhahn, R

1990-03-01

The blue cells that convert sunlight directly into electricity are becoming more and more efficient: the dream of cheap solar energy may soon become true. The competitors are more expensive than is often thought, for in the case of the conventional energies the costs of 'side effects' are often forgotten - for example, damage to the environment by power plants and cars. The radiation of the 'Sun Power Plant', on the other hand, creates no fumes and is inexhaustible. (orig.).

Requirements and operation of decentralised power plants in the changing power market; Anforderungen und Einsatz dezentraler Kraftwerke im veraenderten Strommarkt

Energy Technology Data Exchange (ETDEWEB)

Hoenings, Norbert; Hornig, Niels; Steinbach, Sebastian [E.ON Energy Projects GmbH, Muenchen (Germany)

2014-08-01

E.ON plans and realises distributed industrial power plants on the basis of contracting schemes. Target is to reduce energy costs without investment by the customer himself. Gas turbine CHP plants are very flexible and offer many possibilities for the operator to adjust optimally to a constantly changing energy market. This aspect is becoming increasingly important due to the increasing share of renewables. However, the economic situation for CHP plants has deteriorated significantly, due to the current market situation distorted by the subsidised renewable power generation. (orig.)

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

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

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.

Steam generator replacement at the Obrigheim nuclear power station

International Nuclear Information System (INIS)

Pickel, E.; Schenk, H.; Huemmler, A.

1984-01-01

The Obrigheim Nuclear Power Station (KWO) is equipped with a dual-loop pressurized water reactor of 345 MW electric power; it was built by Siemens in the period 1965 to 1968. By the end of 1983, KWO had produced some 35 billion kWh in 109,000 hours of operation. Repeated leaks in the heater tubes of the two steam generators had occurred since 1971. Both steam generators were replaced in the course of the 1983 annual revision. Kraftwerk Union AG (KWU) was commissioned to plant and carry out the replacement work. Despite the leakages the steam generators had been run safely and reliably over a period of 14 years until their replacement. Replacing the steam generators was completed within twelve weeks. In addition to the KWO staff and the supervising crew of KWU, some 400 external fitters were employed on the job at peak work-load periods. For the revision of the whole plant, work on the emergency systems and replacement of the steam generators a maximum number of approx. 900 external fitters were employed in the plant in addition to some 250 members of the plant crew. The exposure dose of the personnel sustained in the course of the steam generator replacement was 690 man-rem, which was clearly below previous estimates. (orig.) [de

Power plant retrofitting in the Ukraine. Step-by-step policy; Kraftwerksrehabilitierung in der Ukraine. Politik der kleinen Schritte

Energy Technology Data Exchange (ETDEWEB)

Hannemann, S. [Kraftwerks- und Anlagenbau AG (KAB), Berlin (Germany)

2001-08-01

Power consumption has been declining since 1990 by 50%, from 268 TWh to about 130 TWh, so that the Ukraine currently has an excess generation capacity of about 12 GW. But on the other hand, power supply bottlenecks have been very common across the country during the last few years, recurrently leading to blackouts of homes and business. The electricity generation industry does not have the financial means to pay for required maintenance, repair or retrofitting of their power plants. The article addresses current international financing schemes and planned support projects and reports details of a cooperation project under the project leadership of KAB, a German power plant manufacturing company, for retrofitting of a coal-fired power plant at a site in the western Ukraine. (orig./CB) [German] Die Halbierung des Verbrauchs seit 1990 von 268 TWh auf ca. 130 TWh hat zu Ueberkapazitaeten von derzeit rund 12 GW gefuehrt. Paradoxerweise gibt es gleichzeitig in den letzten Jahren immer wieder Versorgungsengpaesse, die zu Abschaltungen fuehren. Die permanent unter Geldmangel leidenden Stromerzeuger sind nicht mehr in der Lage, ihre Kraftwerke zu reparieren bzw. zu rehabilitieren. Angesichts der schwierigen Situation koennte, wie das Beispiel der deutsch-ukrainischen Zusammenarbeit unter Fuehrung der KAB im Projekt am Standort Burschtyn zeigt, eine Politik der kleinen Schritte einen moeglichen Weg aus der Krise weisen. Es wird auf laufende internationale Finanzierungsprogramme und weitere Projekte verwiesen. (orig./CB)

{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.)

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)

The AREVA integrated and sustainable concept of fatigue design, monitoring and re-assessment; AREVA FATIGUE CONCEPT - ein geschlossenes Konzept zur Verfolgung und Optimierung der auf Ermuedung basierenden Schaedigungseffekte von thermisch und mechanisch beanspruchten Kraftwerksbauteilen

Energy Technology Data Exchange (ETDEWEB)

Begholz, Steffen; Rudolph, Juergen [AREVA NP GmbH, Erlangen (Germany)

2008-07-01

Prevention of fatigue damage of components is an important topic with respect to safety and availability of a nuclear power plant. The issue of fatigue monitoring should be of primary interest throughout service life. Based on the changing general framework, i.e. planning of new plants with a projected lifetime of 60 years and the lifetime extension of existing plants AREVA is focussing R and D activities on improved detection methods. Primary objective is the realistic determination of the actual usage level of reactor components. The fatigue monitoring is supposed to enhance cost optimization and minimize inspection frequency. Fatigue monitoring should be implemented at the beginning of start-up period since the high loads during this phase introduce a significant contribution to the usage level. AREVA recommends the use of the FAMOS (fatigue monitoring system) for the assessment of the realistic transient loads and the data processing with respect to fatigue evaluation. Every 10 years the actual usage levels should be evaluated in detail according to the standards, based on measured load data. The fatigue evaluation is usually performed using finite element analyses taking into account the transient temperature loads at the component, dependent on the component demands based on elastic or elasto-plastic material behaviour. Potential problematic areas can be identified reliably. Direct measurement of fatigue damage, refined analysis concepts (short crack fracture mechanics, and ratcheting simulation) are supposed to support the concept. [German] Die Vermeidung von Ermuedungsschaeden an Komponenten der nuklearen Kraftwerkstechnik ist ein wichtiges Thema in Hinblick auf die Aufrechterhaltung der Anlagensicherheit sowie auf die Erhoehung der Verfuegbarkeit. Das Thema Ermuedungsueberwachung sollte somit waehrend der gesamten Laufzeit eines Kraftwerkes mit hoher Aufmerksamkeit verfolgt werden. Vor diesem Hintergrund und den sich aendernden Rahmenbedingungen, wie z

Efficiency enhancement of a gas turbine cycle using an optimized tubular recuperative heat exchanger

International Nuclear Information System (INIS)

Sayyaadi, Hoseyn; Mehrabipour, Reza

2012-01-01

A simple gas turbine cycle namely as the Kraftwerk Union AG unit including a Siemens gas turbine model V93.1 with 60 MW nominal power and 26.0% thermal efficiency utilized in the Fars power plant located is considered for the efficiency enhancement. A typical tubular vertical recuperative heat exchanger is designed in order to integrate into the cycle as an air pre-heater for thermal efficiency improvement. Thermal and geometric specifications of the recuperative heat exchanger are obtained in a multi-objective optimization process. The exergetic efficiency of the gas cycle is maximized while the payback time for the capital investment of the recuperator is minimized. Combination of these objectives and decision variables with suitable engineering and physical constraints makes a set of the MINLP optimization problem. Optimization programming is performed using the NSGA-II algorithm and Pareto optimal frontiers are obtained in three cases including the minimum, average and maximum ambient air temperatures. In each case, the final optimal solution has been selected using three decision-making approaches including the fuzzy Bellman-Zadeh, LINMAP and TOPSIS methods. It has been shown that the TOPSIS and LINMAP decision-makers when applied on the Pareto frontier which is obtained at average ambient air temperature yields best results in comparison to other cases. -- Highlights: ► A simple Brayton gas cycle is considered for the efficiency improvement by integrating of a recuperator. ► Objective functions based on thermodynamic and economic analysis are obtained. ► The payback time for the capital investment is minimized and the exergetic efficiency of the system is maximized. ► Pareto optimal frontiers at various site conditions are obtained. ► A final optimal configuration is found using various decision-making approaches.

Component behaviour in the 700 C power plant. Numerical and experimental investigations; Komponentenverhalten im 700 C-Kraftwerk. Numerische und experimentelle Untersuchungen

Energy Technology Data Exchange (ETDEWEB)

Schmidt, Kay H.

2013-07-19

Currently martensitic steels are used in fossil fired power plants with maximum working temperatures up to 625 C. These steels do not show the required creep rupture strength at the target temperature of 700 C. For these high temperatures, new materials like the nickel base alloys have to be qualified for power plants services. Originating from the weld of turbine materials, nickel base alloys show outstanding creep rupture strength. An alloy with good prospects out of the material class of the nickel base alloys is Alloy 617 mod. However, this material is expensive due to its high nickel content. Furthermore, the complex machinability of this material leads to an additional increase in expenses. A complete fabrication of the boiler area using Alloy 617 mod is not economically feasible, which means that the usage of this material has to be limited to the temperature weld of 625 C to 700 C. For the boiler area with temperatures below 625 C the well proven 9 % to 12 % Cr-steels, like T/P92 and VM12/VM12-SHC may be used. In the weld of low temperatures up to 525 C the usage of the 2.5 % Cr-steel T/P24 offers numerous advantages, in particular in the fabrication of membrane walls. This material shows good creep properties up to temperatures of 525 C and, for thin walled components, T24 can be welded without post weld heat treatment by using suitable techniques. For a successful design and fabrication of a 700 C fossil fired power plant, appropriate materials have to be qualified. Here, a special focus is set on the creep properties of these materials. The presented work is a significant contribution to the qualification of these materials. First, the materials Alloy 617 mod, T/P92, VM12/VM12-SHC and T24 are briefly introduced and characterized. After this, the materials are investigated in a detailed creep testing program. This program includes investigations on base material, extracted from tubes, pipes and inductive bends of pipes. In addition, crossweld specimens and specimens made of weld material are creep tested at high temperatures. To gain important information about the behavior under service conditions and multiaxial loadings, a test rig was developed at MPA Universitaet Stuttgart, which is able to test membrane-wall like components under this point of view. The applied mechanical and thermal loads in these tests are dimensioned to cause a status of high damage within the investigated materials after a test time of 2.000 h to 5.000 h. After the test procedure, the membrane-wall like specimens are metallographically investigated. The objectives of these investigations are the characterization of the actual damage within the material caused by the prior testing, in particular within the tube-fin-welds and furthermore to identify the area of crack formation. Besides the characterization and qualification of the materials for the construction of components of a high temperature fossil fired power plant with a peak temperature of 700 C the results of the uniaxial creep test will be used to develop material models for inelastic finite element simulations. For this a creep equation based on a formulation of Graham and Walles will be modified and furthermore extended with a damage parameter. By simulating the component tests presented in this work, the created material models (including three heat affected zones) could be verified. However, it becomes obvious that irregulations in geometry in a tube-fin-weld of a waterwall may exist and may lead to an additional bending load. By evaluating the damage parameter, which is implemented in the used creep equation, the local creep strains and the multiaxiality of the stress state, the area of maximum creep damage and with this the location of crack formation can be precisely predicted in the heat affected zone on the tube side, close to the surface of the tube-fin-weld. The acquired results show, that modern FE codes in combination with suitable creep equations are a powerful tool to support the design process of power plant components. Finally, the results in this work allow the conclusion that with the help of the introduced modified creep equation of Graham and Walles a numerical simulation of high temperature loaded boiler components is possible. Furthermore the data base for design and dimensioning processes of power plant components in the creep regime was extended with reliable data. In addition to that the qualification of the materials Alloy 617 mod, T/P92, VM12/VM12-SHC and T24 for the usage in fossil fired power plants with temperatures up to 700 C was furthered.

Modification and optimisation measures on the demineralisation plant of the Boxberg Power Station; Umbau und Optimierung der Vollentsalzungsanlage im Kraftwerk Boxberg

Energy Technology Data Exchange (ETDEWEB)

Leidich, F.U. [ALSTOM Power Generation AG, Mannheim (Germany); Markert, A. [Vattenfall Europe Generation AG Co KG, E-KT, Cottbus (Germany); Hajdamowicz, S. [Vattenfall Europe Generation AG Co KG, E-GBB, Boxberg (Germany); Kleespies, W. [RoKa GmbH, Butzbach (Germany)

2006-07-01

The demineralisation plant at the Boxberg Power Station, Unit AQ (Plant IV), owned by Vattenfall Europe Generation AG and Co KG, officially started its operation in 2000. In the course of the operation, technical shortcomings became apparent that rendered the quality of the deionised water inadequate and did prevent the plant from being operated in a normal, fully-automatic mode. Due to the insolvency of the supplier, it had not been possible to eliminate a series of problems and optimise the processes in such a way that the plant could be operated as planned. Nevertheless, thanks to measures like retrofitting the system with lowering loops, replacing the regenerating stations by frequency-controlled excenter-screw propeller pumps, installing automatic vents, and optimising the control concept of the plant, it finally was possible to solve some of the main problems. Longer intervals between regenerating procedures came as an additional benefit. (orig.)

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

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.)

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)

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)

TRANSESTERIFICATION OF VEGETABLES OIL USING SUBAND SUPERCRITICAL METHANOL

Directory of Open Access Journals (Sweden)

Nyoman Puspa Asri

2012-11-01

Full Text Available A benign process, non catalytic transesterification in sub and supercritical methanol method was usedto prepare biodiesel from vegetables oil. The experiment was carried out in batch type reactor (8.8 mlcapacity, stainless steel, AKICO, JAPAN by changing the reaction condition such as reactiontemperature (from 210°C in subcritical condition to 290°C in supercritical state with of 20°Cinterval, molar ratio oil to methanol (1:12-1:42 and time of reaction (10-90 min. The fatty acidmethyl esters (FAMEs content was analyzed by gas chromatography-flame ionization detector (GCFID.Such analysis can be used to determine the biodiesel yield of the transesterification. The resultsshowed that the yield of biodiesel increases gradually with the increasing of reaction time atsubcritical state (210-230oC. However, it was drastically increased at the supercritical state (270-290oC. Similarly, the yield of biodiesel sharply increased with increasing the ratio molar of soy oilmethanolup to 1:24. The maximum yield 86 and 88% were achieved at 290oC, 90 min of reaction timeand molar ratio of oil to methanol 1:24, for soybean oil and palm oil, respectively.Proses transesterifikasi non katalitik dengan metanol sub dan superkritis,merupakan proses yang ramah lingkungan digunakan untuk pembuatan biodiesel dari minyak nabati.Percobaan dilakukan dalam sebuah reaktor batch (kapasitas 8,8 ml, stainless steel, AKICO, JAPAN,dengan variabel kondisi reaksi seperti temperatur reaksi (dari kondisi subkritis 210°C-kondisisuperkritis 290°C dengan interval 20°C, rasio molar minyak-metanol (1:12-1:42 dan waktu reaksi(10-90 menit. Kandungan metil ester asam lemak (FAME dianalisis dengan kromatografi gasdengan detektor FID (GC-FID. Hasil Analisis tersebut dapat digunakan untuk menentukan yieldbiodiesel dari proses transesterifikasi. Hasil penelitian menunjukkan bahwa yield biodiesel meningkatsecara perlahan dengan meningkatnya waktu reaksi pada keadaan subkritis (210-230oC. Namun

Risks and opportunities of the liberalized electricity market. Partial project: BoFiT, an integrated decision support system for retaining the competitiveness of the cogeneration technology. Final report; Risiken und Chancen des liberalisierten Strommarktes. Teilprojekt: Integrierte Entscheidungsunterstuetzung durch BoFiT zur Erhaltung der Wettbewerbsfaehigkeit der Kraft-Waerme-Kopplung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Stock, G.; Scheidt, M.

2002-06-04

The energy management system called BoFiT and specific new applications are explained which have been developed as one project task of the coordinated research project sponsored by the German ministry of economics,(BMWi), entitled ''Risks and opportunities of the liberalized electricity market''. The major objective of the project is: Finding efficient strategies to ensure the competitiveness of the cogeneration technology in the deregulated power and gas markets, in particular for the purpose of enhancing the penetration of the ecologically beneficial, cogenerated district heating supply in those markets. The focus of this report is on a specific application of the integrated BoFiT decision support system, for which the ''model for microsimulation of spot transactions at the Power Exchange based on a multi-agent system'' has been developed and is explained in great detail. (orig./CB) [German] Mit dem Energiemanagementsystem BoFiT soll den Unternehmen eine effektive und operativ nutzbare Entscheidungsunterstuetzung angeboten werden. Wesentliche Ziele des Verbundprojektes des BMWi sind: Unterstuetzung der KWK und speziell der darauf basierenden oekologisch sinnvollen Fernwaermeversorgung durch Anpassung von Arbeitsablaeufen und Werkzeugen zur Findung betriebswirtschaftlich optimaler Einsatz- und Betriebsstrategien; Kostenoptimierung der Kraftwerke, Vertraege und Stromhandelsaktivitaeten unter den Randbedingungen der deregulierten Strom- und Gasmaerkte. Als Beispiel einer solchen integrierten Entscheidungsunterstuetzung wird das ''Modell zur Mikrosimulation des Spothandels von Strom auf der Basis eines Multi-Agenten-Systems'' ausfuehrlich beschrieben. (orig./CB)

Behavior of shut-down dose rate of recirculation piping of BWR under noble metal application

International Nuclear Information System (INIS)

Fuse, Motomasa; Nagase, Makoto; Aizawa, Motohiro; Wada, Yoichi; Ishida, Kazushige; Hosokawa, Hideyuki; Hettiarachchi, Samson; Weber, Christoph

2014-01-01

The cause of shut-down dose rate change of the recirculation piping observed in KKM (Kern Kraftwerk Mühleberg) after application of noble metal injection method is analyzed. The plant experienced the sharp decrease of piping dose rate in the cycle just after the application of noble metal(classic NobleChem TM ) and re-buildup of radioactivity in the subsequent several cycles. After the application of online noble metal injection (online NobleChem TM ), gradual decrease of dose rate has been observed. The presence of a certain amount of noble metal on the iron rich oxide film promotes the dissolution of the oxide under hydrogen addition, resulting in a decrease of deposited noble metal on the oxide film surface as well as of radioactive species in the film. Under the condition of lower amount of noble metal on the surface oxides, the oxidant species, especially hydrogen peroxide, slightly increases facilitating the re-growth of iron rich oxides along with re-buildup of radioactivity. After the application of online noble metal injection during each cycle, gradual dissolution of iron rich oxides and gradual decrease of radioactivity in the oxides proceed to decrease the piping dose rate. In the radioactivity decreasing phase, the presence of zinc is considered to assist the suppression of radioactivity buildup in the oxide film. From the analysis, treating piping surface with platinum after chemical decontamination process is expected to work well for suppression of the piping dose rate. (author)

Operation management systems in the energy economy in `97; Betriebsmanagement-Systeme in der Energiewirtschaft `97

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

VDI Report 1310 contains the lectures held at the congress on ``Operation management systems in the energy economy `97`` in Wuerzburg on 12 and 13 March 1997. Operation management systems, beside fulfilling several other functions, work with the input they receive from plant management systems. They analyse and condense characteristic values, facilitate optimal utilisation of all resources, and supply in-depth information for the preparation of the management`s strategic decisions. This information concerns the analysis of plant characteristics, monitoring of the service life of heavily loaded plant components, preparation of balances, planning of maintenance and repair measures, purchase, and materials management. The purpose of the congress was to point out developments and present and discuss practical examples from the following areas: power plant, energy network, energy supply for municipalities and industry. [Deutsch] Der VDI-Bericht 1310 enthaelt die Vortraege der gleichnamigen Tagung, die am 12. und 13. Maerz 1997 in Wuerzburg stattfand. Betriebsfuehrungssysteme basieren auf dem Input von Anlagenfuehrungssystemen und uebernehmen weitergehende Aufgaben. Sie analysieren und verdichten Kennwerte, ermoeglichen den optimalen Einsatz aller Betriebsmittel und stellen vertiefte Informationen zur Vorbereitung strategischer Entscheidungen fuer das Management zur Verfuegung. Dabei handelt es sich um die Analyse von Anlagenkennwerten, die Lebensdauerueberwachung hochbelasteter Anlagenteile, das Erstellen von Bilanzen, die Planung von Wartungs- und Instandhaltungsmassnahmen bis hin zum Einkauf und der Materialwirtschaft. Aufgabe der Tagung war es, Entwicklungen aufzuzeigen und praktische Beispiele aus den Sektoren Kraftwerk, Energienetze, kommunale Versorgung und Industrie darzustellen und zu diskutieren. (orig./RHM)

Radioactive waste management in the Federal Republic of Germany: Industrial practices and results

International Nuclear Information System (INIS)

Grabener, K.H.

1987-01-01

In the Federal Republic of Germany (FRG), the production and use of nuclear-generated electricity expanded steadily despite the fact that opposition from the environmentalists led to the impression of an upcoming moratorium for nuclear energy. With this increase in capacity--by the year 1990, nearly 25 000 MW will be on the line--there will be an increase in the volume of low-level (non-heat-generating) radwaste originating from nuclear power plants. Radwaste management has been influenced to a considerable extent by the requirements of the final repository. Following a period of trial storage in the Asse repository, preparations are now being made for storage in the Konrad ore mine. It is intended to begin storage in 1991. Requirements for the packages specify containers with a volume from 3.9 to 10.9 m/sup 3/ or cast iron safety drums. These drums are suitable for radioactive materials in powder form (resins, dried concentrates) without the need for embedding materials. Storage in standard 55-gal drums is no longer permitted. The costs for final storage will be very high so that volume reduction is of prime importance. Kraftwerk Union (KWU) as a supplier of nuclear power plants (NPPs) examined the radwaste market and decided to combine delivery of radwaste treatment systems to NPPs with service jobs including radwaste handling and conditioning in its own service and maintenance plant at Karlstein

START-3 calculations of SUPER-RAMP (FUMEX-III) cases

International Nuclear Information System (INIS)

Chulkin, D.; Kuznetsov, V.; Krupkin, A.; Bogatyr, S.; Novikov, V.

2011-01-01

The Studsvik SUPER-RAMP Project, an internationally sponsored research project, investigated the failure propensity of typical LWR fuel in the form of test rods when subjected to power ramps, after base irradiation. The Project power ramped 28 individual PWR rods and 16 BWR rods. The PWR rods were all tested using high ramp rates. Due to different objectives for the BWR subprogram, one set of the BWR rods was tested using a high ramp rate, and another set were tested with a very slow ramp rate. The rods were base irradiated in a power reactor environment KK Obrigheim or BR-3 at time averaged heat ratings mainly in the range 14-26 kW/m to peak bum-ups in the range 33-45 MWd/kgU and were subsequently ramp tested in the research reactor R2 at Studsvik, Sweden. In this presentation some calculations are made on the PK2 group fuel rods. The rods were standard rods manufactured by Kraftwerk Union AG/Combustion Engineering (KWU/CE). Calculations have shown reasonable coincidence of calculated and experimental FGR and reasonable prediction of dimensional behavior of fuel rod. Following the lead taken in the original FUMEX CRP, a number of simplified cases were constructed in order to investigate mathematical stability and more easily compare model and code predictions without the vagaries of real power histories. In this presentation, each case is outlined together with the reason for its inclusion before presenting the results and comparing the predictions

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

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.

Trend of CO{sub 2} emissions of the 30 largest power plants in Germany; Trendentwicklung der CO{sub 2}-Emissionen der 30 groessten Kraftwerke in Deutschland. Kurzanalyse basierend auf aktuellen Emissionshandelsdaten

Energy Technology Data Exchange (ETDEWEB)

Hermann, Hauke

2014-04-02

The brochure on the trend of CO{sub 2} emissions of the 30 largest power plants in Germany includes tables of the emissions of these power plants. The CO{sub 2} emissions of these power plants in 2013 (25% of the total German greenhouse gas emissions) have increased by 5% compared to 2012. The total CO{sub 2} emission sin Germany increased by 1.5%. The differences between brown coal and black coal fired power plants are discussed.

The building as a power plant. Net plus energy building with e-mobility; Das Gebaeude als Kraftwerk. Netto-Plusenergiegebaeude mit E-Mobilitaet

Energy Technology Data Exchange (ETDEWEB)

Fisch, M. Norbert [Technische Univ. Braunschweig (Germany). Inst. fuer Gebaeude- und Solartechnik

2011-07-01

Energy designers do not consider the building technology isolated from the architecture. Instead, sustainable, functional and innovative solutions are developed in an integrated process with all persons involved. The user comfort, the overall energy efficiency, the selection of ecologically compatible materials as well as the relation between building and sustainable mobility belong to the context of holistic planning.

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'.

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}.

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

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.

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.)

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.)

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.

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.

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

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.

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.

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.

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.

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.

Power engineering. Systems for energy conversion. Compact knowledge for study and profession. 4. upd. and enl. ed.; Energietechnik. Systeme zur Energieumwandlung. Kompaktwissen fuer Studium und Beruf

Energy Technology Data Exchange (ETDEWEB)

Zahoransky, Richard A.

2009-07-01

This textbook imparts to the reader a fundamental understanding for relations of energy conversion processes. It comprises the total spectra of energy engineering, starting with fundamentals of energy process engineering via description of operating power plants (all types) to energy distribution and - storage. Main topics are sustainable energy systems from renewable energy sources. combined systems (e.g. Gas/steam turbine power plants) and plants with cogeneration (e.g. modular cogeneration plants). A new chapter Kyoto-Protocol was created as a concept of emissions-free coal-fired power plants. A new wording for deregulation of energy markets was received. Numerous texts and graphs were been revised. Chapter 18 ''Deregulation of Energy Markets'' is newly revised. Due to its didactic concepts the book directs not only to students but also everybody, who is inerested into actual questions of energy engineering. (org./GL) [German] Dieses Lehrbuch vermittelt dem Leser ein grundlegendes Verstaendnis fuer die Zusammenhaenge der Energieumwandlungsprozesse. Es umfasst die gesamte Bandbreite der Energietechnik. Die Schwerpunkte reichen von nachhaltigen, erneuerbaren Energietechniken, Kombianlagen (z.B. Gas- und Dampfturbinen-Kraftwerke) ueber Anlagen mit Kraft-Waerme-Kaelte-Kopplung bis hin zum Kyoto-Protokoll. Die 4. Auflage beinhaltet erstmals Uebungsaufgaben mit ausfuehrlichen Loesungen zu den einzelnen Kapiteln. Mehrere Kapitel sind aktualisiert. Das Kapitel 18 ''Liberalisierung der Energiemaerkte'' ist neu gefasst. Aus dem Inhalt Energietechnische Grundlagen - Dampfkraftwerke - Kernkraftwerke - Gasturbinen - Kombinationskraftwerke - Stationaere Kolbenmotoren - Brennstoffzellen - Kraft-Waerme-Kaelte-Kopplung - Wasserkraft - Solartechnik - Windenergie - Biomasse - Geothermie - Energetische Muellverwertung - Energieverteilung und -speicherung - Liberalisierung der Energiemaerkte - Kyoto-Protokoll. (orig.)

Thermodynamics. An introduction into its bases and technical applications. 14. ed.; Thermodynamik. Grundlagen und technische Anwendungen

Energy Technology Data Exchange (ETDEWEB)

Baehr, Hans Dieter [Hannover Univ. (Germany). Inst. fuer Thermodynamik; Kabelac, Stephan [Helmut-Schmidt-Univ., Univ. der Bundeswehr Hamburg (Germany). Inst. fuer Thermodynamik

2009-07-01

The actualized 14th edition covers now a further chapter on energy conversion: the structure of energy demand in Germany is discussed and patterns of energy conversion highlighted. Furtheron practical application on combustion processes, thermal power plants, carbon dioxide and power generation, heating systems and refrigerating machinery are completed. The concepts of exergy and energy are introduced by postulates instead of being constructed on the basis of certain theorems; this is to give the students easier access to the fundamental balance equations which are the basic elements in the quantitative statements of the two basic laws of thermodynamics and are indispensable for their application. The balance equations are expressed in as general a form as possible taking account also of transient processes of open systems and of the special case of steady flow processes. (orig./GL) [German] die aktualisierte 14. Auflage des bewaehrten Lehrbuchs der Technischen Thermodynamik wurde das Kapitel ueber Waermekraftanlagen gruendlich bearbeitet und durch einen Abschnitt zur Energiewandlung ergaenzt: Die Energiebedarfsstruktur von Deutschland wird erlaeutert, und die moeglichen Energiewandlungspfade werden diskutiert. Schwerpunkt des Buches ist die ausfuehrliche und auch dem Anfaenger verstaendliche Darstellung der Grundlagen der Thermodynamik mit der sorgfaeltigen Einfuehrung der thermodynamischen Begriffe und den fundamentalen Bilanzgleichungen fuer Energie, Entropie und Exergie. Die thermodynamischen Eigenschaften reiner Fluide und fluider Gemische werden eingehend erlaeutert. Darauf aufbauend wird die Thermodynamik der Gemische und der chemischen Reaktionen entwickelt. Auch die thermodynamischen Aspekte wichtiger energie- und verfahrenstechnischer Anwendungen werden praxisnah behandelt: - Stroemungs- und Arbeitsprozesse, - thermische Stofftrennverfahren, - Verbrennungsprozesse und Verbrennungskraftanlagen, - thermische Kraftwerke, - CO2-Emissionen der Stromerzeugung

Design, analysis and construction of the prestressed concrete containment of the nuclear power station Gundremmingen

International Nuclear Information System (INIS)

Mueller, W.F.; Ick, U.

1977-01-01

Kraftwerk Union AG is presently constructing at Gundremmingen (Bavaria) on the River Danube a BWR twin-plant (KRB Units B and C) with a capacity of 2x1300 MWe. Owing to the wall thickness/diameter ratio the containment can be calculated as a thin-walled shell. Areas of discontinuity are subjected to three-dimensional investigations. For the design of the concrete structure different fracture safety margins are defined for the load conditions occurring in operation in the event of a loss-of-coolant accident and as a result of an aircraft or an earthquake. From this results that in the cross sectional areas without discontinuities of the prestressed outer cylinder no resultant tensions occur. For the steel liner different limits of strain are permitted for the various load conditions, bearing in mind that the integrity of the liner must remain ensured at any time. In order to keep the stresses resulting from the constraint of the containment outer cylinder in the foundation slab low, the cylindrical wall is placed on bearings. The suppression pool top slab is constrained at the containment outer cylinder and at the containment inner cylindrical wall. The inlets of the vent pipes are integrated in the slab in a way resulting in a double slab. The liner consists of 8 mm thick steel plate and is anchored in the concrete via steel sections. Mechanical equipment anchoring in the concrete is provided by welding anchor plates into the liner after the section concerned has been completed. The carcass work on the reactor building is scheduled to be completed within

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

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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

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

Energy Technology Data Exchange (ETDEWEB)

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

1965-11-15

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

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

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

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)

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.

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.)

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.)

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)

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

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. 

Preliminary study for the reactivation of a low-head hydropower scheme near Gwatt, Switzerland; Vorstudie Kleinwasserkraftwerk Schoeni, Hani bei Gwatt (Thun). Reaktivierung Niederdruck-Kraftwerk

Energy Technology Data Exchange (ETDEWEB)

Kunz, B.; Meng, H.

2000-07-01

This final report for the Swiss Federal Office of Energy presents the results of a preliminary study on the reactivation of an old sawmill power station in the hamlet of Hani, near Gwatt in Switzerland. Details are given on the history of the installation, which dates back to 1891. The report describes the original equipment installed and discusses the ideas of the site's present owner concerning the reactivation of the power station. The legal situation as far as operational rights are concerned and the hydrological data of the site are discussed. The results of measurements made on water flow, the available water-head heights and the resulting power generation potential are presented. A project is proposed for a 58 kW turbine and estimates are presented for total yearly energy production. The report also discusses environmental and flood-protection aspects. Finally, the economics of the proposed power station are discussed and recommendations concerning the implementation of the project are made.

CH{sub 4} dehydrogenation on Cu(1 1 1), Cu@Cu(1 1 1), Rh@Cu(1 1 1) and RhCu(1 1 1) surfaces: A comparison studies of catalytic activity

Energy Technology Data Exchange (ETDEWEB)

Zhang, Riguang; Duan, Tian [Key Laboratory of Coal Science and Technology of Ministry of Education and Shanxi Province, Taiyuan University of Technology, Taiyuan 030024, Shanxi (China); Ling, Lixia [Key Laboratory of Coal Science and Technology of Ministry of Education and Shanxi Province, Taiyuan University of Technology, Taiyuan 030024, Shanxi (China); Research Institute of Special Chemicals, Taiyuan University of Technology, Taiyuan 030024, Shanxi (China); Wang, Baojun, E-mail: wangbaojun@tyut.edu.cn [Key Laboratory of Coal Science and Technology of Ministry of Education and Shanxi Province, Taiyuan University of Technology, Taiyuan 030024, Shanxi (China)

2015-06-30

Highlights: • Adsorbed Rh atom on Cu catalyst exhibits better catalytic activity for CH{sub 4} dehydrogenation. • The adsorbed Rh atom is the reaction active center for CH{sub 4} dehydrogenation. • The morphology of Cu substrate has negligible effect on CH{sub 4} dehydrogenation. - Abstract: In the CVD growth of graphene, the reaction barriers of the dehydrogenation for hydrocarbon molecules directly decide the graphene CVD growth temperature. In this study, density functional theory method has been employed to comparatively probe into CH{sub 4} dehydrogenation on four types of Cu(1 1 1) surface, including the flat Cu(1 1 1) surface (labeled as Cu(1 1 1)) and the Cu(1 1 1) surface with one surface Cu atom substituted by one Rh atom (labeled as RhCu(1 1 1)), as well as the Cu(1 1 1) surface with one Cu or Rh adatom (labeled as Cu@Cu(1 1 1) and Rh@Cu(1 1 1), respectively). Our results show that the highest barrier of the whole CH{sub 4} dehydrogenation process is remarkably reduced from 448.7 and 418.4 kJ mol{sup −1} on the flat Cu(1 1 1) and Cu@Cu(1 1 1) surfaces to 258.9 kJ mol{sup −1} on RhCu(1 1 1) surface, and to 180.0 kJ mol{sup −1} on Rh@Cu(1 1 1) surface, indicating that the adsorbed or substituted Rh atom on Cu catalyst can exhibit better catalytic activity for CH{sub 4} complete dehydrogenation; meanwhile, since the differences for the highest barrier between Cu@Cu(1 1 1) and Cu(1 1 1) surfaces are smaller, the catalytic behaviors of Cu@Cu(1 1 1) surface are very close to the flat Cu(1 1 1) surface, suggesting that the morphology of Cu substrate does not obviously affect the dehydrogenation of CH{sub 4}, which accords with the reported experimental observations. As a result, the adsorbed or substituted Rh atom on Cu catalyst exhibit a better catalytic activity for CH{sub 4} dehydrogenation compared to the pure Cu catalyst, especially on Rh-adsorbed Cu catalyst, we can conclude that the potential of synthesizing high-quality graphene with the

Training to NDT construction experts (ZFPBau). Developments in recent years; Ausbildung zum ZfPBau-Experten. Entwicklungen der letzten Jahre

Energy Technology Data Exchange (ETDEWEB)

Taffe, Alexander [Hochschule fuer Technik und Wirtschaft, Berlin (Germany); Feistkorn, Sascha [SVTI Schweizerischer Verein fuer technische Inspektionen, Wallisellen (Switzerland). Nuklearinspektorat; Dauberschmidt, Christoph [Hochschule Muenchen (Germany)

2016-05-01

Classical destructive test methods are fixed part of industrial sectors for decades such as aerospace, automotive, railway and power plants. A high degree of standardization of procedures, and training in form of an ISO standard are present, but not in non-destructive testing of civil engineering (ZfPBau). Except for the rebound hammer NDT methods in civil engineering are not standardized. Also of personnel qualifications can be found in regulations very few requirements, although it is obvious that this is an indispensable prerequisite for the proper application of the procedures and reliable inspection results. In this contribution experiences with a presented training concept in which the construction inspector will trained to DIN 1076 in a two-day course. Here are the necessary conditions worked out, such as the creation of suitable test bodies or the definition of necessary course content for establishing training courses. [German] Klassische zerstoerungsfreie Pruefverfahren sind seit Jahrzehnten fester Bestandteil industrieller Bereiche wie Luftfahrt, Automotive, Eisenbahn und Kraftwerke. Ein hoher Normungsgrad der Verfahren und Ausbildungsstandards in Form einer ISO-Norm liegen vor. Bei der zerstoerungsfreien Pruefung im Bauwesen (ZfPBau) ist das anders. Bis auf den Rueckprallhammer sind ZfPBau-Verfahren nicht genormt. Auch zur Personalqualifikation finden sich in Regelwerken nur sehr wenige Anforderungen, obwohl es offensichtlich ist, dass dies eine unverzichtbare Voraussetzung fuer die richtige Anwendung der Verfahren und zuverlaessige Pruefaussagen ist. In diesem Beitrag werden Erfahrungen mit einem Ausbildungskonzept vorgestellt, bei dem Bauwerkspruefer nach DIN 1076 in einem zweitaegigen Lehrgang ausgebildet werden. Dabei werden die notwendigen Voraussetzungen heraus gearbeitet, wie z.B. die Erstellung von geeigneten Testkoerpern oder die Festlegung notwendiger Kursinhalte, die zum Etablieren von Ausbildungskursen erforderlich sind.

Wind energy. From the garage workshop to a global market. 25 years scientific accompaniment; Windenergie - von der Garagen-Werkstatt zum Weltmarkt. 25 Jahre wissenschaftliche Begleitung

Energy Technology Data Exchange (ETDEWEB)

Hahn, Berthold; Stuebig, Cornelia [Fraunhofer Institut fuer Windenergie und Energiesystemtechnik (IWES), Kassel (Germany); Ponick, Bernd [Fraunhofer Institut fuer Windenergie und Energiesystemtechnik (IWES), Kassel (Germany); Hannover Univ. (Germany); Keller, Sarina [DLR Deutsches Zentrum fuer Luft- und Raumfahrt e.V., Koeln (Germany); Felder, Martin; Jachmann, Henning [Zentrum fuer Sonnenenergie- und Wasserstoff-Forschung Baden-Wuerttemberg (ZSW), Stuttgart (Germany)

2015-04-15

The plant technology for the use of wind energy on land is so sophisticated that the WEA can be operated as ''normal'' power plants to the grid. Of course, there are still potential for development, for example, in terms of improved reliability, or concerning the fledgling offshore use, always with an emphasis on the simultaneous reduction in costs. Although from the former garages workshops is little remaining, the production techniques are another major issue in terms of quality and costs. The cost of electricity from wind energy is taking account of external costs are already competitive with conventional power generation. To limit the costs of the energy transition one to expect from the wind energy as of the other technologies cost reduction. Various studies show that the wind energy supply in the balance is sufficient several times to provide the expected contribution to supply. [German] Die Anlagentechnologie fuer die Windenergienutzung an Land ist so ausgereift, dass die WEA als ''normale'' Kraftwerke am Netz betrieben werden koennen. Selbstverstaendlich bestehen weiterhin Entwicklungspotenziale, z. B. hinsichtlich verbesserter Zuverlaessigkeit oder bezueglich der noch jungen Offshore Nutzung, immer mit einem Augenmerk auf die gleichzeitige Kostenreduktion. Auch wenn von den ehemaligen Garagen Werkstaetten wenig uebrig geblieben ist, sind die Produktionstechniken ein weiteres wesentliches Thema bezueglich Qualitaet und Kosten. Die Kosteneffizienz der Stromerzeugung aus Windenergie ist unter Beruecksichtigung externer Kosten heute schon konkurrenzfaehig zur konventionellen Stromerzeugung. Zur Begrenzung der Kosten der Energiewende wird aber von der Windenergie wie von den anderen Technologien weiterhin eine Kostenreduktion erwartet. Diverse Studien zeigen, dass das Windenergieangebot in der Bilanz mehrfach ausreicht, um den erwarteten Beitrag zur Versorgung leisten zu koennen.

Hot gas filtration: Investigations to remove gaseous pollutant components out of flue gas during hot gas filtration. Final report; HGR: Untersuchung zur Minimierung von gasfoermigen Schadstoffen aus Rauchgasen bei der Heissgasfiltration. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Christ, A; Gross, R; Renz, U

1998-07-01

Power plants with gas and steam turbines in pressurized fluidized bed or pressurized gasification processes enable power generation of coal with high efficiency and little emissions. To run these plants the cleaning of the flue gas is necessary before entering the turbines under the conditions of high temperature and pressure. Ceramic filter elements are the most probable method for hot gas cleaning. A simultaneous reduction of gaseous pollutant components under these conditions could help to make the whole process more efficient. The aim of the project is to integrate the catalytic reduction of carbon monoxide, hydrocarbons and nitric oxides into the hot gas filtration with ceramic filter elements as a one step mecanism. The project is focused on: - the catalytic behaviour of ferruginous ashes of brown coal, - the effectiveness of calcinated aluminates as a catalyst to remove uncombusted hydrocarbons in a hot gas filtration unit, - numerical simulation of the combined removal of particles and gaseous pollutant components out of the flue gas. (orig.) [Deutsch] Gas- und Dampfturbinen-Kraftwerke mit Druckwirbelschicht- oder mit Druckvergasungsverfahren ermoeglichen die Verstromung von Kohle mit hohem Wirkungsgrad und niedrigen Emissionen. Eine Voraussetzung fuer den Betrieb dieser Anlagen ist die Entstaubung der Rauchgase bei hohen Temperaturen und Druecken. Abreinigungsfilter mit keramischen Elementen werden dazu eingesetzt. Eine Reduzierung gasfoermiger Schadstoffe unter den gleichen Bedingungen koennte die Rauchgaswaesche ersetzen. Ziel des Gesamtvorhabens ist es, die Integration von Heissgasfiltration und katalytischem Abbau der Schadstoffe Kohlenmonoxid, Kohlenwasserstoffe und Stickoxide in einem Verfahrensschritt zu untersuchen. Die Arbeitsschwerpunkte dieses Teilvorhabens betreffen - die katalytische Wirkung eisenhaltiger Braunkohlenaschen, - die Wirksamkeit des Calciumaluminats als Katalysator des Abbaus unverbrannter Kohlenwasserstoffe im Heissgasfilter

Fuel cell technology; Brennstoffzellen-Technologie

Energy Technology Data Exchange (ETDEWEB)

Stimming, U; Friedrich, K A; Cappadonia, M; Vogel, R

1999-12-31

Hydrogen from fossil or renewable sources is an important fuel for low-emission power generation in fuel cells. Methanol and maybe also ethanol can also be produced by direct electrochemical processes in low-temperature fuel cells (PEMFC, PAFC). Fuel cell systems with high operating temperatures are highly flexible with regard to fuel but tend to have material problems. On the other hand, rapid developments in materials development and the possibility of production technology transfer from the electronics industry lead one to expect a breakthrough in the near future. But in spite of this, niche market applications will prevail. Since power stations have a longer life than motor vehicles and fuel cells in mobile applications, emission reductions from fuel cell applications in road vehicles are more probable on a medium-term basis than from applications in power stations. (orig.) [Deutsch] Wasserstoff, der sowohl aus fossilen wie auch aus regenerativen Quellen erschlossen werden kann, ist ein wesentlicher Brennstoff fuer die emissionsarme Elektrizitaetsproduktion in Brennstoffzellen. Methanol und eventuell Ethanol koennen auch direkt elektrochemisch in Niedertemperaturbrennstoffzellen (PEMFC, PAFC) umgesetzt werden. Brennstoffzellensysteme mit hohen Betriebstemperaturen erlauben eine hohe Flexibilitaet bezueglich der verwendeten Brennstoffe, sind aber nach wie vor durch starke Materialprobleme belastet. Die enormen Fortschritte in der Materialentwicklung einerseits sowie ein moeglicher Transfer von Fertigungstechnologien aus der Elektronikindustrie andererseits lassen eine zukuenftige grosstechnische Nutzung von Brennstoffzellen erwarten. Die technische Einfuehrung wird dennoch nur ueber Nischenmaerkte moeglich sein. Da die mittlere Lebensdauer eines Kraftwerks deutlich hoeher ist als die eines Strassenfahrzeugs, ausserdem Brennstoffzellen auch in staerkerem Masse in Fahrzeugen eingesetzt werden koennen, sind mittelfristig Emissionen eher durch

Competitive effects and instruments of power sector reforms. International reform concepts blockade structures, risk distribution. A political economy analysis; Wettbewerbseffekte und Instrumente von Stromsektorreformen. Internationale Reformkonzepte, Blockadestrukturen, Risikoverteilung. Eine politoekonomische Analyse

Energy Technology Data Exchange (ETDEWEB)

Liebchen, Armin [Liebchen Consulting, Berlin (Germany)

2014-07-01

Power sectors with weak or inadequate competition structures are the rule, despite numerous attempts at reform. But can afford modern economies this defect for a long time? Why can the implementation of competition are blocked so effectively? The author studied international reform experiences and opens up interesting insights that can also reflect on problems of the German energy turnaround: The difficulty of timing and coordination of the reform components, the development of resistance levels of individual interest groups, breach of contract as a rational alternative, causes unwanted price effects, shifting interest situations of major stakeholders, change dynamics impending regulatory risks, pending financing risks, stranded cost-conflict situations for power stations disconnected from the grid and facilities and instruments of a political and regulatory risk management for reforms. With numerous examples, background analyzes and instruments to reform analysis, this book is aimed at investors, policy planners and analysts. [German] Stromsektoren mit schwachen oder unzulaenglichen Wettbewerbsstrukturen sind trotz zahlreicher Reformversuche die Regel. Aber koennen sich moderne Volkswirtschaften diesen Mangel dauerhaft leisten? Warum kann die Einfuehrung von Wettbewerb so wirksam blockiert werden? Der Autor untersucht internationale Reformerfahrungen und eroeffnet interessante Einsichten, die sich auch auf Problemlagen der deutschen Energiewende spiegeln lassen: Die Schwierigkeit des richtigen Timings und der Abstimmung der Reformteile, dem Aufbau von Widerstandslinien einzelner Interessensgruppen, Vertragsbruch als rationaler Alternative, Ursachen unerwuenschter Preiseffekte, sich verschiebenden Interessenslagen wichtiger Akteure, Veraenderungsdynamik drohender Regulierungsrisiken, schwebenden Finanzierungsrisiken, stranded-cost-Konfliktlagen fuer vom Netz genommene Kraftwerke und Moeglichkeiten und Instrumenten eines politisch-regulatorischen Risikomanagements

Pentacene on Au(1 1 1), Ag(1 1 1) and Cu(1 1 1): From physisorption to chemisorption.

Science.gov (United States)

Lu, Meng-Chao; Wang, Rong-Bin; Yang, Ao; Duhm, Steffen

2016-03-09

We measured the electronic and the molecular surface structure of pentacene deposited on the (1 1 1)-surfaces of coinage metals by means of ultraviolet photoelectron spectroscopy (UPS) and low-energy electron diffraction (LEED). Pentacene is almost flat-lying in monolayers on all three substrates and highly ordered on Au(1 1 1) and on Cu(1 1 1). On Ag(1 1 1), however, weak chemisorption leads to almost disordered monolayers, both, at room temperature and at 78 K. On Cu(1 1 1) pentacene is strongly chemisorbed and the lowest unoccupied molecular orbital becomes observable in UPS by a charge transfer from the substrate. On Ag(1 1 1) and Cu(1 1 1) multilayers adopt a tilted orientation and a high degree of crystallinity. On Au(1 1 1), most likely, also in multilayers the molecular short and long axes are parallel to the substrate, leading to a distinctively different electronic structure than on Ag(1 1 1) and Cu(1 1 1). Overall, it could be demonstrated that the substrate not only determines the geometric and electronic characteristics of molecular monolayer films but also plays a crucial role for multilayer film growth.

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)

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.

Metabolism of 1-fluoro-1,1,2-trichloroethane, 1,2-dichloro-1,1-difluoroethane, and 1,1,1-trifluoro-2-chloroethane.

Science.gov (United States)

Yin, H; Jones, J P; Anders, M W

1995-03-01

1-Fluoro-1,1,2-trichloroethane (HCFC-131a), 1,2-dichloro-1,1-difluoroethane (HCFC-132b), and 1,1,1-trifluoro-2-chloroethane (HCFC-133a) were chosen as models for comparative metabolism studies on 1,1,1,2-tetrahaloethanes, which are under consideration as replacements for ozone-depleting chlorofluorocarbons (CFCs). Male Fischer 344 rats were given 10 mmol/kg ip HCFC-131a or HCFC-132b or exposed by inhalation to 1% HCFC-133a for 2 h. Urine collected in the first 24 h after exposure was analyzed by 19F NMR and GC/MS and with a fluoride-selective ion electrode for the formation of fluorine-containing metabolites. Metabolites of HCFC-131a included 2,2-dichloro-2-fluoroethyl glucuronide, 2,2-dichloro-2-fluoroethyl sulfate, dichlorofluoroacetic acid, and inorganic fluoride. Metabolites of HCFC-132b were characterized as 2-chloro-2,2-difluoroethyl glucuronide, 2-chloro-2,2-difluoroethyl sulfate, chlorodifluoroacetic acid, chlorodifluoroacetaldehyde hydrate, chlorodifluoroacetaldehyde-urea adduct, and inorganic fluoride. HCFC-133a was metabolized to 2,2,2-trifluoroethyl glucuronide, trifluoroacetic acid, trifluoroacetaldehyde hydrate, trifluoroacetaldehyde-urea adduct, inorganic fluoride, and a minor, unidentified metabolite. With HCFC-131a and HCFC-132b, glucuronide conjugates of 2,2,2-trihaloethanols were the major urinary metabolites, whereas with HCFC-133a, a trifluoroacetaldehyde-urea adduct was the major urinary metabolite. Analysis of metabolite distribution in vivo indicated that aldehydic metabolites increased as fluorine substitution increased in the order HCFC-131a < HCFC-132b < HCFC-133a. With NADPH-fortified rat liver microsomes, HCFC-133a and HCFC-132b were biotransformed to trifluoroacetaldehyde and chlorodifluoroacetaldehyde, respectively, whereas HCFC-131a was converted to dichlorofluoroacetic acid. No covalently bound metabolites were detected by 19F NMR spectroscopy.(ABSTRACT TRUNCATED AT 250 WORDS)

A good working comfort in the power plant. Activation of the surface of concrete in the administration building; Gutes Arbeitsklima im Kraftwerk. Betonoberflaechenaktivierung im Verwaltungsgebaeude

Energy Technology Data Exchange (ETDEWEB)

Hetzel, Michaela [Uponor GmbH, Hassfurt (Germany)

2010-07-01

The target of the establishment of a new administration building was the transformation of a noticeable improvement of the job conditions for 45 co-workers of the power station in the Upper Bavarian Zolling. With an unusual and innovative architecture with an optimized daylight concept and sophisticated facility management, the new building at the east border of the existing power station in Zolling developed.

Compulsory procurement of emission allowances. How will things will continue after the Copenhagen conference?; Emissionszertifikatepflichten fuer Kraftwerke. Wie geht es weiter nach der Kopenhagen-Konferenz?

Energy Technology Data Exchange (ETDEWEB)

Telke, Juergen [Kiel Univ. (Germany). Rechtswissenschaftliche Fakultaet

2010-03-15

German power plants are obliged to hold emission allowances for their carbon dioxide emissions. This obligation is largely established by the Kyoto Protocol, which was approved in 1997 and entered into force in 2005 and which specifies binding emission reduction goals for 37 industrial states. Because this agreement is only valid until the end of 2012, negotiations were held for a follow-on agreement in Copenhagen in mid-December 2009. This article explains the current legal situation as laid down in the Kyoto Protocol and the EU Emission Trade Directive that followed from it. It goes on to analyse the impact of the Copenhagen conference on the emission allowance trade and gives appropriate recommendations for action for German power plants.

Investigations on forecast-based operating strategies for solar thermal power plants with integrated storage capacity; Untersuchungen zu vorhersagebasierten Betriebsstrategien fuer solarthermische Kraftwerke mit integrierter Speicherkapazitaet

Energy Technology Data Exchange (ETDEWEB)

Wittmann, Michael Karl

2012-07-01

This publication describes a method for scheduling the operation of a power plant storage. The purpose of operation scheduling is to determine the economically optimum yield achievable in the course of daily power plant operation. The optimum operation schedule for the storage is determined based on Dynamic Programming Algorithms. Besides its focus on operation scheduling the publication investigates the effects of imperfect weather and price forecasts on electricity production and thus on the operator's economic results. It assesses the current Spanish legislation as well as other incentive scenarios in terms of their impact on operators' feed-in behaviour.

Educational Modelling Language 1.1 (EML 1.1)

NARCIS (Netherlands)

Koper, Rob; Vogten, Hubert; Martens, Harrie

2003-01-01

Package contains the EML 1.1 dtd, schema and documentation as is created for the Edubox Player. It is slightly different from IMS Learning Design and provides an intermediate solution between EML 1.0 and IMD Learning Design. The Edubox Player 3.x works on EML 1.1. This package is stored for

Liquid-air partition coefficients of 1,1-difluoroethane (HFC152a), 1,1,1-trifluoroethane (HFC143a), 1,1,1,2-tetrafluoroethane (HFC134a), 1,1,1,2,2-pentafluoroethane (HFC125) and 1,1,1,3,3-pentafluoropropane (HFC245fa).

Science.gov (United States)

Ernstgård, Lena; Lind, Birger; Andersen, Melvin E; Johanson, Gunnar

2010-01-01

Blood-air and tissue-blood coefficients (lambda) are essential to characterize the uptake and disposition of volatile substances, e.g. by physiologically based pharmacokinetic (PBPK) modelling. Highly volatile chemicals, including many hydrofluorocarbons (HFC) have low solubility in liquid media. These characteristics pose challenges for determining lambda values. A modified head-space vial equilibrium method was used to determine lambda values for five widely used HFCs. The method is based on automated head-space gas chromatography and injection of equal amount of chemical in two head-space vials with identical air phase volumes but different volumes of the liquid phase. The liquids used were water (physiological saline), fresh human blood, and olive oil. The average lambda values (n = 8) were as follows: 1,1-difluoroethane (HFC152a) - 1.08 (blood-air), 1.11 (water-air) and 5.6 (oil-air); 1,1,1-trifluoroethane (HFC143a) - 0.15, 0.15 and 1.90; 1,1,1,2-tetrafluoroethane (HFC134a) - 0.36, 0.35 and 3.5; 1,1,1,2,2-pentafluoroethane (HFC125) - 0.083, 0.074 and 1.71; and 1,1,1,3,3-pentafluoropropane (HFC245fa) - 0.62, 0.58 and 12.1. The lambda values appeared to be concentration-independent in the investigated range (2-200 ppm). In spite of the low lambda values, the method errors were modest, with coefficients of variation of 9, 11 and 10% for water, blood and oil, respectively.

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)

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.

A comparative study of the adsorption and hydrogenation of acrolein on Pt(1 1 1), Ni(1 1 1) film and Pt Ni Pt(1 1 1) bimetallic surfaces

Science.gov (United States)

Murillo, Luis E.; Chen, Jingguang G.

In this study we have investigated the reaction pathways for the decomposition and hydrogenation of acrolein (CH 2dbnd CH-CH dbnd O) on Ni/Pt(1 1 1) surfaces under ultra-high vacuum (UHV) conditions using temperature programmed desorption (TPD) and high-resolution electron energy loss spectroscopy (HREELS). While gas-phase hydrogenation products are not observed from clean Pt(1 1 1), the subsurface Pt-Ni-Pt(1 1 1), with Ni residing below the first layer of Pt, is active for the self-hydrogenation of the C dbnd O bond to produce unsaturated alcohol (2-propenol) and the C dbnd C bond to produce saturated aldehyde (propanal), with the latter being the main hydrogenation product without the consecutive hydrogenation to saturated alcohol. For a thick Ni(1 1 1) film prepared on Pt(1 1 1), the self-hydrogenation yields for both products are lower than that from the Pt-Ni-Pt(1 1 1) surface. The presence of pre-adsorbed hydrogen further enhances the selectivity toward C dbnd O bond hydrogenation on the Pt-Ni-Pt(1 1 1) surface. In addition, HREELS studies of the adsorption of the two hydrogenation products, 2-propenol and propanal, are performed on the Pt-Ni-Pt(1 1 1) surface to identify the possible surface intermediates during the reaction of acrolein. The results presented here indicate that the hydrogenation activity and selectivity of acrolein on Pt(1 1 1) can be significantly modified by the formation of the bimetallic surfaces.

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

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.

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.

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

6,6'-(1E,1'E-((1R,2R-1,2-Diphenylethane-1,2-diylbis(azan-1-yl-1-ylidenebis(methan-1-yl-1-ylidenebis(2-tert-butyl-4-((trimethylsilylethynylphenol

Directory of Open Access Journals (Sweden)

David Díaz Díaz

2013-03-01

Full Text Available Functionalizable salen derivative, 6,6'-(1E,1'E-((1R,2R-1,2-diphenylethane-1,2-diylbis(azan-1-yl-1-ylidenebis(methan-1-yl-1-ylidenebis(2-tert-butyl-4-((trimethylsilyl ethyn-ylphenol (3, was synthesized by condensation between (1R,2R-1,2-diphenylethane-1,2-diamine (2 and 3-tert-butyl-2-hydroxy-5-((trimethylsilylethynyl benzaldehyde (1 under refluxing conditions. The title compound was characterized by 1H-NMR, 13C-NMR, FT-IR, high-resolution mass spectrometry, optical rotation and melting point determination.

Construction and cost experience regarding the 2nd pool house for spent fuel storage facility in the Atucha Power Station

International Nuclear Information System (INIS)

Barbosa, C.A.

1980-01-01

The Atucha I second pool house storage for spent fuel is designed as an extension of the Atucha I power station. The two are linked by civil structure, controlling circuits, electrical and compressed air and water supplies, low level wastes disposal, ventilation under pressure maintenance, and, most important, the ability to transfer spent and new fuel in both directions. Because the second pool house is, by location and design, an extension of the existing installation, and since there is no design departure, regarding storage and transfer of fuel from that of the original installation, the rules and regulations applied for its construction were the same as those valid for the Atucha I construction. The requirement not to exceed a four-year period for construction and commissioning was determined by the need to have storage room for the Atucha I fuel. Argentina will meet the 1982 target by having the installation available during the second half of 1981. The second pool house is a wet storage location with a capacity of 1000 tons metallic uranium. It was designed by the Kraftwerk Union of West Germany along the same lines as the 440-ton storage location originally built with the station. The Atomic Energy Commission of Argentina has managed the construction and participated in project and design stages. As in the original pool, the 6 m long assemblies are stacked in double tiers. The cost figures which are mentioned differ from previously released figures and are not the final ones. With civil construction almost finished and mechanical erection started, the present estimates should not differ by more than 10% from the final figures. The installation has an investment cost of 61 million dollars, (1980), and, depending on the amortization time span considered, a total yearly cost per kg of capacity of metallic uranium, ranging between 5.5 and 9.3 dollars per kg

7. Kassel symposium on energy systems technology: Renewable energy sources and efficient utilization of energy; 7. Kasseler Symposium Energie-Systemtechnik: Erneuerbare Energien und rationelle Energieverwendung

Energy Technology Data Exchange (ETDEWEB)

Caselitz, P. (comp.)

2002-07-01

This proceedings volume comprises 17 papers on the following subjects: Methane hydrates, compounds of gas and water; Compressed air stroage gas turbine power plants / Scheduled application for load levelling between varying wind power production and power demand; Modern pumped storage power stations in the GW range - the PSW Goldisthal example; Lead batteries - new developments and future applications; Alkaline battery systems for hybrid electric road vehicles; Lighium systems and their applications; Zinc/air cells; Hydrogen storage - metal hydride storage, compressed gas storage, LNG storage; Carbon nanofibres for hydrogen storage; Double-layer condensers - technology, cost, perslpectives; Supercondensers in motor vehicles; Superconducting magnetic energy stores; Flywheel storage - status report; Decentralized energy storage in the European integrated supply grid - the EU project DISPOWER; Intercontinental integration of power supply - perspectives of full-scale power supply on the basis of renewable energy sources in Europe; High-volgate direct-current transmission in the European power suppply grid; Superconductivity and energy transport - status and perspectives. [German] Dieser Tagungsband enthaelt 17 Vortraege mit folgenden Themen: Methanhydrate: Verbindung aus Gas und Wasser (Erwin Suess); Druckluftspeicher-Gasturbinen-Kraftwerke / Geplanter Einsatz beim Ausgleich flukturierender Windenergie-Produktion und aktuellem Strombedarf (Fritz Crotogino); Moderne Pumpspeicherwerke im Gigawattbereich - PSW Goldisthal (Wolfgang Bogenrieder); Bleibatterien - neue Entwicklungen und zukuenftige Einsatzbereiche (Reiner Wagner); Alkalische Batteriesysteme fuer Hybrid-Elektrostrassenfahrzeuge (Detlef Ohms, Gunter Schaedlich); Lithiumsysteme - Einsatzbereiche (Dietmar Rahner); Zink/Luft-Zellen (Michael Bruesewitz); Wasserstoffspeicher - Metallhydridspeicher, Druckgasspeicher, Fluessiggasspeicher (Andreas Otto); Kohlenstoff-Nanofasern zur Wasserstoffspeicherung (Juergen Garche

Structure dynamics with regard to non-linear support behavior; Dynamische Strukturberechnung unter Beruecksichtigung nichtlinearen Lagerverhaltens

Energy Technology Data Exchange (ETDEWEB)

Driessen, W. [Technischer Ueberwachungs-Verein Nord e.V., Hamburg (Germany)

2000-07-01

hier anhand eines Vergleiches mit einer der im Rahmen der In-Betrieb-Setzung des Kraftwerks gemessenen Verschiebungen aufgezeigt. (orig.)

The role of nuclear power in external and internal communications at Siemens

International Nuclear Information System (INIS)

Breyer, Wolfgang

1999-01-01

'Der Spiegel', quotes Siemens CEO as saying that the nuclear business accounts for 2 percent of the business but for 95 percent of his troubles. The communications organization at Siemens is rather complex. As a consequence of the political relevance of energy technology, KWU has a public relations department addressing a broad spectrum of stake holders, runs a quarterly magazine on energy and environmental policy called Standpunkt, (Viewpoint) and has, the largest press office of all Siemens Groups. These entities also contribute to the corporate media for internal and external communications. When the nuclear controversy in Germany reached its first culmination in the mid-1970s, Kraftwerk Union, the forerunner of what is now the Siemens Power Generation Group (KWU), automatically became a leading voice on the pro-nuclear side because, as turnkey contractor for most of Germany's NPPs, it had the deepest knowledge of the technology whereas the owner/operator side was and is organized in several utilities. From the German experience with anti-nuke campaign one could draw the following conclusions: (1) A political,, technology like nuclear necessarily leads to a high profile in the public. As the No. nuclear supplier in Germany Siemens doesn't have the option of a low profile; (2) As a consequence, the nuclear business gets unproportional attention in the public. Siemens has to take this into account in order to assure its other business areas enough visibility; (3) For public relations on nuclear power, the internal audience is as important as the external one. Because of the large work-force of Siemens, internal communications have a significant multiplication effect for the external audience; (4) A broad spectrum of non-nuclear activities doesn't make a company like Siemens more vulnerable to public pressure than a mono-structured company. On the contrary: The high prestige gained in its other business fields makes it easier to defend the nuclear business as

Juba teine "1+1 = 1"

Index Scriptorium Estoniae

2004-01-01

15. III Okupatsioonimuuseumis toimuva "1+1=1" teise ürituse kavast. Presentatsioonide õhtu keskendub konkreetse ruumikogemuse vahendamisele kunstis (helis, slaidi-installatsioonis, tänava-aktsioonis, skulptuuris, videos, filmis). Esinevad Cevdet Erek, Andres Lõo, Andres Kurg (arhitektuur ja interjöörid Marko Raadi filmis "Agent Sinikael") jt.

CO adsorption on PdGa(1 0 0), (1 1 1) and (1{sup ¯}1{sup ¯}1{sup ¯}) surfaces: A DFT study

Energy Technology Data Exchange (ETDEWEB)

Bechthold, P.; Ardhengi, J.S.; Juan, A., E-mail: cajuan@uns.edu.ar; González, E.A.; Jasen, P.V.

2014-10-01

Graphical abstract: - Highlights: • CO adsorption is top on Pd sites for all surfaces. • Our results agree with TDS peak at 210 K for PdGa (1{sup ¯}1{sup ¯}1{sup ¯}) attributed to CO-Pd bond. • Pd-CO bond is formed at expenses of metal-metal bond. No Ga-CO interaction is found. • A back-donation for all surfaces was detected. After adsorption Pd PDOS shift towards lower energies. • IR frequencies for the C-O adsorbed presents a red shift compared to gas phase. - Abstract: CO adsorption on (1 0 0), (1 1 1) and (1{sup ¯}1{sup ¯}1{sup ¯}) planes is analyzed using density functional theory (DFT) calculations. Changes in the electronic structure of these surfaces and CO bond after adsorption are also addressed here. CO is located on Pd atop geometry with a tilted configuration of 7.8° in the (1 0 0) plane, while in the (1 1 1) and (1{sup ¯}1{sup ¯}1{sup ¯}) are perpendicular to the surface. No direct interaction of CO with Ga is detected. The overlap population (OP) of Pd-Pd and Pd-Ga bond decreases as the new Pd-CO bond is formed. In all cases, the C-O bond length changes less than 1% compared to the vacuum but its strength decrease about 50% as determined by the changes in the OP. The effect of CO is limited to its first Pd neighbor. Analysis of orbital interaction reveals that Pd-CO bond mainly involves s-s and s-p orbitals with less participation of Pd 4d orbitals. Computed CO vibration frequencies after adsorption shows a red shift from vacuum towards 1972.9, 1990.4 and 1988.6 cm{sup −1} on (1 0 0), (1 1 1) and (1{sup ¯}1{sup ¯}1{sup ¯}) planes respectively, following the same trend that experimental data on the PdGa intermetallic compound.

Density functional study of hypophosphite adsorption on Ni (1 1 1) and Cu (1 1 1) surfaces

International Nuclear Information System (INIS)

Zeng Yue; Liu Shubin; Ou Lihui; Yi Jianlong; Yu Shanci; Wang Huixian; Xiao Xiaoming

2006-01-01

Surface structures and electronic properties of hypophosphite, H 2 PO 2 - , molecularly adsorbed on Ni(1 1 1) and Cu(1 1 1) surfaces are investigated in this work by density functional theory at B3LYP/6-31++g(d, p) level. We employ a four-metal-atom cluster as the simplified model for the surface and have fully optimized the geometry and orientation of H 2 PO 2 - on the metal cluster. Six stable orientations have been discovered on both Ni (1 1 1) and Cu (1 1 1) surfaces. The most stable orientation of H 2 PO 2 - was found to have its two oxygen atoms interact the surface with two P-O bonds pointing downward. Results of the Mulliken population analysis showed that the back donation from 3d orbitals of the transition metal substrate to the unfilled 3d orbital of the phosphorus atom in H 2 PO 2 - and 4s orbital's acceptance of electron donation from one lone pair of the oxygen atom in H 2 PO 2 - play very important roles in the H 2 PO 2 - adsorption on the transition metals. The averaged electron configuration of Ni in Ni 4 cluster is 4s 0.63 4p 0.02 3d 9.35 and that of Cu in Cu 4 cluster is 4s 1.00 4p 0.03 3d 9.97 . Because of this subtle difference of electron configuration, the adsorption energy is larger on the Ni surface than on the Cu surface. The amount of charge transfers due to above two donations is larger from H 2 PO 2 - to the Ni surface than to the Cu surface, leading to a more positively charged P atom in Ni n H 2 PO 2 - than in Cu n H 2 PO 2 - . These results indicate that the phosphorus atom in Ni n H 2 PO 2 - complex is easier to be attacked by a nucleophile such as OH - and subsequent oxidation of H 2 PO 2 - can take place more favorably on Ni substrate than on Cu substrate

CYP1A1, CYP1A2, SULT1A1 AND SULT1E1 ALLELIC POLYMORPHISM IN CASE OF GENITAL ENDOMETRIOSIS

Directory of Open Access Journals (Sweden)

Konstantin Sergeevich Kublinskiy

2016-02-01

Up-to-date molecular and genetic analyses reveal that women predisposed to genital endometriosis possess Allele G and Genotypes AG and GG of the polymorphic option A-4889G of the CYP1A1 gene and Allele A and Genotypes CA and AA of the polymorphic option C-734A of the CYP1A2 gene. The polymorphism of the promoter regions of the SULT1A1 (G-638A and SULT1E1 (C-174T genes is not associated with genital endometriosis in women.

WOOD 1:1

DEFF Research Database (Denmark)

2013-01-01

Report from 1:1 workshop at Virserum Konsthall in May 2013 with a team of Master's students from Royal Academy of Fine Arts, School of Architecture, Dpt. 3.......Report from 1:1 workshop at Virserum Konsthall in May 2013 with a team of Master's students from Royal Academy of Fine Arts, School of Architecture, Dpt. 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.

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

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)

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

Polymorphisms of UGT1A1*6, UGT1A1*27 & UGT1A1*28 in three major ethnic groups from Malaysia.

Science.gov (United States)

Teh, L K; Hashim, H; Zakaria, Z A; Salleh, M Z

2012-08-01

Genetic polymorphisms of uridine diphosphate glucuronyltransferase 1A1 (UGT1A1) have been associated with a wide variation of responses among patients prescribed with irinotecan. Lack of this enzyme is known to be associated with a high incidence of severe toxicity. The objective of this study was to investigate the prevalence of three different variants of UGT1A1 (UGT1A1*6, UGT1A1*27 and UGT1A1*28), which are associated with reduced enzyme activity and increased irinotecan toxicity, in the three main ethnic groups in Malaysia (Malays, Chinese and Indians). A total of 306 healthy unrelated volunteers were screened for UGT1A1*28, UGT1A1*6 and UGT1A1*27. Blood samples (5 ml) were obtained from each subject and DNA was extracted. PCR based methods were designed and validated for detection of UGT1A1*, UUGT1A1*27 and UUGT1A1*28. Direct DNA sequencing was performed to validate the results of randomly selected samples. Malays and Indian have two-fold higher frequency of homozygous of UGT1A1*28 (7TA/7TA) which was 8 and 8.8 per cent, respectively compared to the Chinese (4.9%). However, the distribution of UGT1A1*6 and UGT1A1*27 showed no significant differences among them. UGT1A1*27 which has not been detected in Caucasian and African American population, was found in the Malaysian Malays (3.33%) and Malaysian Chinese (2.0%). There was interethnic variability in the frequency of UGT1A1*28 in the Malaysian population. Our results suggest that genotyping of UUGT1A1*6, UGT1A1*28 and UGT1A1*27 need to be performed before patients are prescribed with irinotecan due to their high prevalence of allelic variant which could lead to adverse drug reaction.

Oxygen transport and degradation properties of high-temperature membranes for CO{sub 2}-free power plants; Sauerstofftransport und Degradationsverhalten von Hochtemperaturmembranen fuer CO{sub 2}-freie Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Schlehuber, Dominic

2010-07-01

This thesis deals with membranes for oxygen separation from air for high temperature application in fossil power plants within the scope of the oxyfuel-process. Different perovskite membrane materials (ABO3-ae) were investigated concerning the oxygen transport and their chemical stability under operation condition. The association between oxygen transport properties and both the thermodynamic boundary conditions as well as the material properties (membrane thickness and surface properties) was studied. One possibility to achieve higher oxygen fluxes through the membrane is to reduce the thickness. In this case the influence of surface processes on the overall permeation becomes noteworthy. The effect of different membrane surface modifications on the permeation rate was investigated. For example it could be confirmed, that a porous layer on the membrane surface significantly increases the permeation flux due to the compensation of surface exchange limitations. Beyond that, degradation processes during the operation under power plant condition were investigated. Special attention was attached to the influence of degradation on the permeation flux during long term operation. Thereby kinetic demixing of the membrane material was observed. (orig.)

Marketing opportunities for CHP electricity in a virtual power plant. Direct and indirect marketing of flexibility; Vermarktungschancen fuer KWK-Strom im virtuellen Kraftwerk. Direkte und indirekte Flexibilitaetsvermarktung

Energy Technology Data Exchange (ETDEWEB)

Otto, Achim; Baumgart, Bastian [Trianel GmbH, Aachen (Germany). Abt. Virtuelle Kraftwerke

2013-07-15

The increasingly fluctuating feed-in of electricity by means of a rapid expansion of renewable energies results in an increasing demand for flexible performance for the regulation of production and consumption. An important part of the necessary flexibility could be provided by CHP plants. Their potential of flexibility is not always fully exploited.

Trends during operation and maintenance in power plants. Alarm management and 3D-simulation; Trends bei Bedienung und Wartung im Kraftwerk. Alam-Management und 3D-Simulation

Energy Technology Data Exchange (ETDEWEB)

Langlotz, Kati; Brandt, Gerhard [ABB AG, Mannheim (Germany). Div. Energietechnik

2009-11-16

Two manifestations of overburdening can be observed in staff of modern, highly complex power plants with numerous components that need to be monitored from the control station and maintenanced by the service department: The operators of the control station often have to deal with too much information at the same time, while the service staff often have too little information. The operating staff are often swamped with messages and information, while the repair staff has a hard time identifying the relevant components in the vast arsenal of equipment. New ergonomic concepts are needed in order to ensure an efficient and cost-effective operation of power plants.

New EC Directive on the limitation of emissions from large combustion plants. Implications for German power plants; Neue EG-Richtlinie ueber nationale Emissionshoechstmengen. Folgerung fuer deutsche Kraftwerke

Energy Technology Data Exchange (ETDEWEB)

Hildebrand, M. [VDEW - e.V., Frankfurt am Main (Germany). Bereich Recht und Umwelt

2002-03-25

The Directive 2001/80/EC of the European Parliament and of the Council, on the limitation of emissions of certain pollutants into the air from large combustion plants uses a regulatory instrument for limiting emissions at the national levels of EU member states. This approach is completely new and the author of this article therefore expects problems to arise in the context of transfer of this EC Directive into national law. Another aspect discussed is the assessment of implications for the operating power plants in Germany. (orig./CB) [German] Mit der im Herbst 2001 durch das Europaeische Parlament und durch den Umweltministerrat verabschiedeten Richtlinie ueber nationale Emissionshoechstmengen wurde vom europaeischen Vorschriftengeber ein in Deutschland bislang systemfremdes Regelungsinstrument geschaffen, dessen Umsetzung in nationales Recht und dessen anlagenspezifische Konsequenzen - zumindest hierzulande -bislang noch reichlich unklar sind. (orig.)

First status seminar `Druckflamm`. Development of a coal-fuelled combined cycle process with liquid ash separation. Conference report; Erstes Statusseminar `Druckflamm`. Entwicklung eines kohlegefeuerten Gas- und Dampfturbinenprozesses mit Fluessigascheabscheidung. Tagungsband

Energy Technology Data Exchange (ETDEWEB)

Hannes, K. [ed.

1999-09-01

werden kann. Dabei muss das Rauchgas soweit von Partikeln und materialschaedlichen Daempfen gereinigt werden, dass es gasturbinenvertraeglich wird. Nach Angaben der Turbinenhersteller bedeutet dies einen Partikelgehalt <3mg/m{sup 3} i.N. bei einem Partikeldurchmesser < 3 {mu}m und einem Alkaligehalt < 1 ppm. Zur praktischen Erprobung dieser Entwicklung wird in Dorsten auf dem Gelaende eines frueheren STEAG-Kraftwerkes eine Versuchsanlage gefahren. Mit ihr wollen die Betreiber den Gas-Dampfturbinenprozess, der mit Heizoel oder Gas Wirkungsgrade von z.Z. 57 % erreicht, auch fuer Kohle nutzbar machen. Die in Dorsten errichtete Versuchsanlage besitzt eine thermische Leistung von 1 MW und kann bis zu einem Druck von 20 bar betrieben werden. Ein Ueberblick ueber die bisher erzielten Ergebnisse und gewonnenen Erkenntnisse zu Einsatzkohle, Verbrennung und Rauchgasreinigung wird der schematischen Darstellung der Anlage folgend gegeben. Ueber Materialverhalten und Messtechnik wird gesondert berichtet. Als Brennstoff wurden Kohlen unterschiedlicher Zusammensetzung mit Schlackefliesspunkten zwischen ca. 1200 bis 1400 C eingesetzt. (orig.AKF)

Human kidney anion exchanger 1 interacts with adaptor-related protein complex 1 μ1A (AP-1 mu1A)

International Nuclear Information System (INIS)

Sawasdee, Nunghathai; Junking, Mutita; Ngaojanlar, Piengpaga; Sukomon, Nattakan; Ungsupravate, Duangporn; Limjindaporn, Thawornchai; Akkarapatumwong, Varaporn; Noisakran, Sansanee; Yenchitsomanus, Pa-thai

2010-01-01

Research highlights: → Trafficking defect of kAE1 is a cause of dRTA but trafficking pathway of kAE1 has not been clearly described. → Adaptor-related protein complex 1 μ1A (AP-1 mu1A) was firstly reported to interact with kAE1. → The interacting site for AP-1 mu1A on Ct-kAE1 was found to be Y904DEV907, a subset of YXXO motif. → AP-1 mu1A knockdown showed a marked reduction of kAE1 on the cell membrane and its accumulation in endoplasmic reticulum. → AP-1 mu1A has a critical role in kAE1 trafficking to the plasma membrane. -- Abstract: Kidney anion exchanger 1 (kAE1) mediates chloride (Cl - ) and bicarbonate (HCO 3 - ) exchange at the basolateral membrane of kidney α-intercalated cells. Impaired trafficking of kAE1 leads to defect of the Cl - /HCO 3 - exchange at the basolateral membrane and failure of proton (H + ) secretion at the apical membrane, causing a kidney disease - distal renal tubular acidosis (dRTA). To gain a better insight into kAE1 trafficking, we searched for proteins physically interacting with the C-terminal region of kAE1 (Ct-kAE1), which contains motifs crucial for intracellular trafficking, by a yeast two-hybrid (Y2H) system. An adaptor-related protein complex 1 μ1A (AP-1 mu1A) subunit was found to interact with Ct-kAE1. The interaction between either Ct-kAE1 or full-length kAE1 and AP-1 mu1A were confirmed in human embryonic kidney (HEK) 293T by co-immunoprecipitation, affinity co-purification, co-localization, yellow fluorescent protein (YFP)-based protein fragment complementation assay (PCA) and GST pull-down assay. The interacting site for AP-1 mu1A on Ct-kAE1 was found to be Y904DEV907, a subset of YXXO motif. Interestingly, suppression of endogenous AP-1 mu1A in HEK 293T by small interfering RNA (siRNA) decreased membrane localization of kAE1 and increased its intracellular accumulation, suggesting for the first time that AP-1 mu1A is involved in the kAE1 trafficking of kidney α-intercalated cells.

Human kidney anion exchanger 1 interacts with adaptor-related protein complex 1 {mu}1A (AP-1 mu1A)

Energy Technology Data Exchange (ETDEWEB)

Sawasdee, Nunghathai; Junking, Mutita [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Ngaojanlar, Piengpaga [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Department of Immunology and Graduate Program in Immunology, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Sukomon, Nattakan; Ungsupravate, Duangporn [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Limjindaporn, Thawornchai [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Department of Anatomy, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Akkarapatumwong, Varaporn [Institute of Molecular Biosciences, Mahidol University at Salaya Campus, Nakorn Pathom 73170 (Thailand); Noisakran, Sansanee [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand); Yenchitsomanus, Pa-thai, E-mail: grpye@mahidol.ac.th [Division of Medical Molecular Biology and BIOTEC-Medical Biotechnology Unit, Department of Research and Development, Faculty of Medicine Siriraj Hospital, Mahidol University, Bangkok 10700 (Thailand)

2010-10-08

Research highlights: {yields} Trafficking defect of kAE1 is a cause of dRTA but trafficking pathway of kAE1 has not been clearly described. {yields} Adaptor-related protein complex 1 {mu}1A (AP-1 mu1A) was firstly reported to interact with kAE1. {yields} The interacting site for AP-1 mu1A on Ct-kAE1 was found to be Y904DEV907, a subset of YXXO motif. {yields} AP-1 mu1A knockdown showed a marked reduction of kAE1 on the cell membrane and its accumulation in endoplasmic reticulum. {yields} AP-1 mu1A has a critical role in kAE1 trafficking to the plasma membrane. -- Abstract: Kidney anion exchanger 1 (kAE1) mediates chloride (Cl{sup -}) and bicarbonate (HCO{sub 3}{sup -}) exchange at the basolateral membrane of kidney {alpha}-intercalated cells. Impaired trafficking of kAE1 leads to defect of the Cl{sup -}/HCO{sub 3}{sup -} exchange at the basolateral membrane and failure of proton (H{sup +}) secretion at the apical membrane, causing a kidney disease - distal renal tubular acidosis (dRTA). To gain a better insight into kAE1 trafficking, we searched for proteins physically interacting with the C-terminal region of kAE1 (Ct-kAE1), which contains motifs crucial for intracellular trafficking, by a yeast two-hybrid (Y2H) system. An adaptor-related protein complex 1 {mu}1A (AP-1 mu1A) subunit was found to interact with Ct-kAE1. The interaction between either Ct-kAE1 or full-length kAE1 and AP-1 mu1A were confirmed in human embryonic kidney (HEK) 293T by co-immunoprecipitation, affinity co-purification, co-localization, yellow fluorescent protein (YFP)-based protein fragment complementation assay (PCA) and GST pull-down assay. The interacting site for AP-1 mu1A on Ct-kAE1 was found to be Y904DEV907, a subset of YXXO motif. Interestingly, suppression of endogenous AP-1 mu1A in HEK 293T by small interfering RNA (siRNA) decreased membrane localization of kAE1 and increased its intracellular accumulation, suggesting for the first time that AP-1 mu1A is involved in the kAE1

Cs_7Sm_1_1[TeO_3]_1_2Cl_1_6 and Rb_7Nd_1_1[TeO_3]_1_2Br_1_6, the new tellurite halides of the tetragonal Rb_6LiNd_1_1[SeO_3]_1_2Cl_1_6 structure type

International Nuclear Information System (INIS)

Charkin, Dmitri O.; Black, Cameron; Downie, Lewis J.; Sklovsky, Dmitry E.; Berdonosov, Peter S.; Olenev, Andrei V.; Zhou, Wuzong; Lightfoot, Philip; Dolgikh, Valery A.

2015-01-01

Two new rare-earth – alkali – tellurium oxide halides were synthesized by a salt flux technique and characterized by single-crystal X-ray diffraction. The structures of the new compounds Cs_7Sm_1_1[TeO_3]_1_2Cl_1_6 (I) and Rb_7Nd_1_1[TeO_3]_1_2Br_1_6 (II) (both tetragonal, space group I4/mcm) correspond to the sequence of [MLn_1_1(TeO_3)_1_2] and [M_6X_1_6] layers and bear very strong similarities to those of known selenite analogs. We discuss the trends in similarities and differences in compositions and structural details between the Se and Te compounds; more members of the family are predicted. - Graphical abstract: Two new rare-earth – alkali – tellurium oxide halides were predicted and synthesized. - Highlights: • Two new rare-earth – alkali – tellurium oxide halides were synthesized. • They adopt slab structure of rare earth-tellurium-oxygen and CsCl-like slabs. • The Br-based CsCl-like slabs have been observed first in this layered family.

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

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

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

Thermochemistry of 1,1,3,3-tetramethylguanidine and 1,1,3,3-tetramethylguanidinium nitrate

International Nuclear Information System (INIS)

Vitorino, Joana; Agapito, Filipe; Piedade, M. Fátima M.; Bernardes, Carlos E.S.; Diogo, Hermínio P.; Leal, João P.

2014-01-01

Graphical abstract: - Highlights: • The enthalpy of formation of 1,1,3,3-tetramethylguanidinium nitrate was determined by combustion calorimetry. • The cohesive energy of liquid 1,1,3,3-tetramethylguanidinium nitrate was evaluated. • The crystal structure of 1,1,3,3-tetramethylguanidinium nitrate was determined by single crystal X-ray diffraction. • Δ f H m o (l/g) of 1,1,3,3-tetramethylguanidine (tmg) were obtained by solution and Calvet calorimetry. • Δ f H m o (g) calculated by the W1-F12 procedure was in excellent agreement with the corresponding experimental value. - Abstract: Considerable efforts have recently been made to investigate how the structure of protic ionic liquids determines some of their most important properties for technological applications (e.g. low vapour pressure, conductivity). In contrast, the assessment of cohesive energies (which are also linked to those properties) based on thermodynamic results is still practically unexplored. This problem is addressed here for 1,1,3,3-tetramethylguanidinium nitrate, [Htmg][NO 3 ], through a combination of experimental and computational chemistry results at the reference temperature of 298.15 K. The standard molar enthalpies of formation, Δ f H m o ([Htmg][NO 3 ],cr)=-(311.8±2.3)kJ·mol -1 , and fusion, Δ fus H m o ([Htmg][NO 3 ])=16.2±3.8kJ·mol -1 , of solid 1,1,3,3-tetramethylguanidinium nitrate (form I polymorph) were obtained by combustion and differential scanning calorimetry, respectively. From these results Δ f H m o ([Htmg][NO 3 ],l)=-(295.6±4.4)kJ·mol -1 could be derived. Also determined were the standard molar enthalpies of formation, Δ f H m o (tmg, l)=7.7±2.8kJ·mol -1 , and vaporisation, Δ vap H m o (tmg,l)=50.0±1.2kJ·mol -1 , of 1,1,3,3-tetramethylguanidine, by reaction solution and Calvet-drop microcalorimetry, respectively, leading to Δ f H m o (tmg,g)=57.7±3.0kJ·mol -1 . This result is in excellent agreement with Δ f H m o (tmg,g)=58.4±4.0kJ·mol -1

Studio 1:1

Index Scriptorium Estoniae

2011-01-01

Projekteerimis- ja disainistuudiost STUDIO 1:1 (Eindhoven), mis tegeleb avaliku ruumi loomise ja selle kasutamise kujundamisega. Projektidest "Linnulinn - linn lindude segakogukonna jaoks" ja ICT kogemuskeskus "De Verdieping"

Cloning and tissue expression of cytochrome P450 1B1 and 1C1 ...

African Journals Online (AJOL)

Cytochrome P450 1 (CYP1) is widely used as an indicator of exposure to environmental contaminants. In the study, two full-length complementary DNAs encode for CYP1B1 and CYP1C1 were cloned from medaka liver exposed to 500 ppb β-naphthoflavone for 24 h. CYP1B1, having 1984 bp, contains an open reading ...

Improving surface smoothness and photoluminescence of CdTe(1 1 1)A on Si(1 1 1) substrates grown by molecular beam epitaxy using Mn atoms

International Nuclear Information System (INIS)

Wang, Jyh-Shyang; Tsai, Yu-Hsuan; Chen, Chang-Wei; Dai, Zi-Yuan; Tong, Shih-Chang; Yang, Chu-Shou; Wu, Chih-Hung; Yuan, Chi-Tsu; Shen, Ji-Lin

2014-01-01

Highlights: • CdTe(1 1 1)A epilayers were grown on Si(1 1 1) substrates by molecular beam epitaxy. • We report an enhanced growth using Mn atoms. • The significant improvements in surface quality and optical properties were found. - Abstract: This work demonstrates an improvement of the molecular beam epitaxial growth of CdTe(1 1 1)A epilayer on Si(1 1 1) substrates using Mn atoms. The reflection high-energy electron diffraction patterns show that the involvement of some Mn atoms in the growth of CdTe(1 1 1)A is even more effective than the use of a buffer layer with a smooth surface for forming good CdTe(1 1 1)A epilayers. 10 K Photoluminescence spectra show that the incorporation of only 2% Mn significantly reduced the intensity of defect-related emissions and considerably increased the integral intensity of exciton-related emissions by a large factor of about 400

Determination of taste receptor type 1 member 1 (TAS1R1) gene ...

African Journals Online (AJOL)

Jane

2011-10-10

Oct 10, 2011 ... 1Institute of Cellular and Molecular Biology, College of Life Science, Xuzhou Normal University, ... TAS1R1 and TAS1R3 form an L-amino acid sensor, ... 0.5 × TBE buffer (89 mM tris–borate, 2 mM EDTA, pH 8.3) for 2 h at.

Polarity driven morphology of CeO2(1 0 0) islands on Cu(1 1 1)

International Nuclear Information System (INIS)

Stetsovych, O.; Beran, J.; Dvořák, F.; Mašek, K.; Mysliveček, J.; Matolín, V.

2013-01-01

Thin ceria films supported by metal substrates represent important model systems for reactivity studies in heterogeneous catalysis. Here we report the growth study of the polar CeO 2 (1 0 0) phase as part of a mixed CeO 2 (1 1 1)–CeO 2 (1 0 0) thin film supported by Cu(1 1 1). The two ceria phases grow on different areas of the substrate, what allows a reliable growth characterization of the CeO 2 (1 0 0) islands on Cu(1 1 1). Scanning tunneling microscopy measurements reveal CeO 2 (1 0 0) to grow in the form of highly dispersed three dimensional (3D) islands on a CeO 2 (1 0 0) interfacial layer. The CeO 2 (1 0 0) islands exhibit a 2 × 2 surface reconstruction. The presence of the surface reconstruction together with the highly dispersed growth of CeO 2 (1 0 0) islands corresponds to the requirement for compensation of the surface dipole moment on the CeO 2 (1 0 0). CeO 2 (1 0 0) islands are further characterized by reflection high energy electron diffraction yielding their epitaxial relations with respect to the Cu(1 1 1) substrate. The growth of well characterized CeO 2 (1 0 0) islands supported by Cu(1 1 1) represents a starting point for developing a novel template for structure-related reactivity studies of ceria based model catalysts.

A comparative study on GM (1,1) and FRMGM (1,1) model in forecasting FBM KLCI

Science.gov (United States)

Ying, Sah Pei; Zakaria, Syerrina; Mutalib, Sharifah Sakinah Syed Abd

2017-11-01

FTSE Bursa Malaysia Kuala Lumpur Composite Index (FBM KLCI) is a group of indexes combined in a standardized way and is used to measure the Malaysia overall market across the time. Although composite index can give ideas about stock market to investors, it is hard to predict accurately because it is volatile and it is necessary to identify a best model to forecast FBM KLCI. The objective of this study is to determine the most accurate forecasting model between GM (1,1) model and Fourier Residual Modification GM (1,1) (FRMGM (1,1)) model to forecast FBM KLCI. In this study, the actual daily closing data of FBM KLCI was collected from January 1, 2016 to March 15, 2016. GM (1,1) model and FRMGM (1,1) model were used to build the grey model and to test forecasting power of both models. Mean Absolute Percentage Error (MAPE) was used as a measure to determine the best model. Forecasted value by FRMGM (1,1) model do not differ much than the actual value compare to GM (1,1) model for in-sample and out-sample data. Results from MAPE also show that FRMGM (1,1) model is lower than GM (1,1) model for in-sample and out-sample data. These results shown that FRMGM (1,1) model is better than GM (1,1) model to forecast FBM KLCI.

Epitaxial growth of Co(0 0 0 1)hcp/Fe(1 1 0)bcc magnetic bi-layer films on SrTiO3(1 1 1) substrates

International Nuclear Information System (INIS)

Ohtake, Mitsuru; Shikada, Kouhei; Kirino, Fumiyoshi; Futamoto, Masaaki

2008-01-01

Co(0 0 0 1) hcp /Fe(1 1 0) bcc epitaxial magnetic bi-layer films were successfully prepared on SrTiO 3 (1 1 1) substrates. The crystallographic properties of Co/Fe epitaxial magnetic bi-layer films were investigated. Fe(1 1 0) bcc soft magnetic layer grew epitaxially on SrTiO 3 (1 1 1) substrate with two type variants, Nishiyama-Wasserman and Kurdjumov-Sachs relationships. An hcp-Co single-crystal layer is obtained on Ru(0 0 0 1) hcp interlayer, while hcp-Co layer formed on Au(1 1 1) fcc or Ag(1 1 1) fcc interlayer is strained and may involve fcc-Co phase. It has been shown possible to prepare Co/Fe epitaxial magnetic bi-layer films which can be usable for patterned media application

APPLICATION OF PHYTOREMEDIATION FOR HERBAL MEDICINE WASTE AND ITS UTILIZATION FOR PROTEIN PRODUCTION

Directory of Open Access Journals (Sweden)

Danny Soetrisnanto

2012-11-01

bertujuan untuk mengevaluasi penggunaan tanaman air (enceng gondok dan teratai untukmereduksi kontaminan dalam limbah obat jamu. Phytoremediasi dilakukan selama 4-8 hari dan tinggicairan dalam reaktor dijaga pada 5 cm. Keluaran dari phytoremediasi pertama menggunakantanaman air digunakan sebagai medium di phytoremediasi menggunakan mikroalga Spirulina. Untukmendapakan pertumbuhan yang optimum, maka ditambahakan juga nutrient dan menunjukkan bahwaSpirulina tumbuh dengan sangat baik dalam medium ini. Pertumbuhan terbaik diperoleh dariphytoremediasi menggunakan teratai selama 3 hari dan kecepatan pertumbuhan 0,271/hari denganperbandingan C:N:P = 57,790:9,28:1.

PSA LEVEL 3 DAN IMPLEMENTASINYA PADA KAJIAN KESELAMATAN PWR

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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

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.)

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

Crystal structure of 4,4′-bis[3-(piperidin-1-ylprop-1-yn-1-yl]-1,1′-biphenyl

Directory of Open Access Journals (Sweden)

Anqi Walbaum

2017-06-01

Full Text Available The title compound, C28H32N2, (I, is one of a second generation of compounds designed and synthesized based on a very potent and selective α9α10 nicotinic acetylcholine receptor antagonist ZZ161C {1,1′-[[1,1′-biphenyl]-4,4′-diylbis(prop-2-yne-3,1-diyl]bis(3,4-dimethylpyridin-1-ium bromide}, which has shown analgesic effects in a chemotherapy-induced neuropathy animal model. Compound (I was synthesized by the reaction of 4,4′-bis(3-bromoprop-1-yn-1-yl-1,1′-biphenyl with piperidine at room temperature in acetonitrile. The single-crystal used for X-ray analysis was obtained by dissolving (I in a mixture of dichloromethane and methanol, followed by slow evaporation of the solvent. In the crystal of (I, the biphenyl moiety has a twisted conformation, with a dihedral angle of 25.93 (4° between the benzene rings. Both piperidine head groups in (I are in the chair conformation and are oriented so that the N-atom lone pairs of each piperidine group point away from the central biphenyl moiety.

Microwave assisted synthesis and antimicrobial activity of novel 1-[1/2-(1-Benzyl-1H-[1,2,3]triazol-4-ylmethoxy-naphthalen-2/1-yl]-3-(1-phenyl-3-aryl-1H-pyrazol-4-yl-propenones

Directory of Open Access Journals (Sweden)

Dongamanti Ashok

2015-06-01

Full Text Available A series of novel 1-[1/2-(1-Benzyl-1H-[1,2,3]triazol-4-ylmethoxy-naphthalen-2/1-yl]-3-(1-phenyl-3-aryl-1H-pyrazol-4-yl-propenones were design and synthesized by Click reaction followed by Claisen-Schmidt condensation under microwave irradiation and conventional heating methods. The structures of newly synthesized compounds have been established on the basis of elemental analysis, IR, 1H & 13C NMR and mass spectral data. All the compounds were screened for their antimicrobial activity.

Dimensionality effects on magnetic properties of FexCo1-x nanoclusters on Pt(1 1 1)

Science.gov (United States)

Miranda, I. P.; Igarashi, R. N.; Klautau, A. B.; Petrilli, H. M.

2017-11-01

The behavior of local magnetic moments and exchange coupling parameters of FexCo1-x nanostructures (nanowires and compact clusters) on the fcc Pt(1 1 1) surface is here investigated using the first-principles real-space RS-LMTO-ASA method, in the framework of the DFT. Different configurations of FexCo1-x trimers and heptamers on Pt(1 1 1) are considered, varying the positions and the concentration of Fe or Co atoms. We discuss the influence of dimensionality and stoichiometry changes on the magnetic properties, specially on the orbital moments, which are very important in establishing a nanoscopic understanding of delocalized electron systems. We demonstrate the existence of a strictly decreasing nonlinear trend of the average orbital moments with the Fe concentration for the compact clusters, different from what was found for FexCo1-x nanowires on Pt(1 1 1) and also for corresponding higher-dimensional systems (FexCo1-x monolayer on Pt(1 1 1) and FexCo1-x bulk). The average spin moments, however, are invariably described by a linear function with respect to stoichiometry. In all studied cases, the nearest neighbors exchange couplings have shown to be strongly ferromagnetic.

Transformation of 1,1,1-trichloroethane in an anaerobic packed-bed reactor at various concentrations of 1,1,1-trichloroethane, acetate and sulfate

NARCIS (Netherlands)

deBest, JH; Jongema, H; Weijling, A; Doddema, HJ; Janssen, DB; Harder, W

Biotransformation of 1,1,1-trichloroethane (CH3CCl3) was observed in an anaerobic packed-bed reactor under conditions of both sulfate reduction and methanogenesis. Acetate (1 mM) served as an electron donor. CH3CCl3 was completely converted up to the highest investigated concentration of 10 mu M.

On Euclidean connections for su(1,1), suq(1,1) and the algebraic approach to scattering

International Nuclear Information System (INIS)

Ionescu, R.A.

1994-11-01

We obtain a general Euclidean connection for su(1,1) and suq(1,1) algebras. Our Euclidean connection allows an algebraic derivation for the S matrix. These algebraic S matrices reduce to the known ones in suitable circumstances. Also, we obtain a map between su(1,1) and su q (1,1) representations. (author). 8 refs

16 CFR 1.1 - Policy.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Policy. 1.1 Section 1.1 Commercial Practices FEDERAL TRADE COMMISSION ORGANIZATION, PROCEDURES AND RULES OF PRACTICE GENERAL PROCEDURES Industry... substantial or novel question of fact or law and there is no clear Commission or court precedent; or (2) The...

1+1 Gaudin Model

Directory of Open Access Journals (Sweden)

Andrei V. Zotov

2011-07-01

Full Text Available We study 1+1 field-generalizations of the rational and elliptic Gaudin models. For sl(N case we introduce equations of motion and L-A pair with spectral parameter on the Riemann sphere and elliptic curve. In sl(2 case we study the equations in detail and find the corresponding Hamiltonian densities. The n-site model describes n interacting Landau-Lifshitz models of magnets. The interaction depends on position of the sites (marked points on the curve. We also analyze the 2-site case in its own right and describe its relation to the principal chiral model. We emphasize that 1+1 version impose a restriction on a choice of flows on the level of the corresponding 0+1 classical mechanics.

S1P in HDL promotes interaction between SR-BI and S1PR1 and activates S1PR1-mediated biological functions: calcium flux and S1PR1 internalization.

Science.gov (United States)

Lee, Mi-Hye; Appleton, Kathryn M; El-Shewy, Hesham M; Sorci-Thomas, Mary G; Thomas, Michael J; Lopes-Virella, Maria F; Luttrell, Louis M; Hammad, Samar M; Klein, Richard L

2017-02-01

HDL normally transports about 50-70% of plasma sphingosine 1-phosphate (S1P), and the S1P in HDL reportedly mediates several HDL-associated biological effects and signaling pathways. The HDL receptor, SR-BI, as well as the cell surface receptors for S1P (S1PRs) may be involved partially and/or completely in these HDL-induced processes. Here we investigate the nature of the HDL-stimulated interaction between the HDL receptor, SR-BI, and S1PR1 using a protein-fragment complementation assay and confocal microscopy. In both primary rat aortic vascular smooth muscle cells and HEK293 cells, the S1P content in HDL particles increased intracellular calcium concentration, which was mediated by S1PR1. Mechanistic studies performed in HEK293 cells showed that incubation of cells with HDL led to an increase in the physical interaction between the SR-BI and S1PR1 receptors that mainly occurred on the plasma membrane. Model recombinant HDL (rHDL) particles formed in vitro with S1P incorporated into the particle initiated the internalization of S1PR1, whereas rHDL without supplemented S1P did not, suggesting that S1P transported in HDL can selectively activate S1PR1. In conclusion, these data suggest that S1P in HDL stimulates the transient interaction between SR-BI and S1PRs that can activate S1PRs and induce an elevation in intracellular calcium concentration.

Preliminary study on the 'Haegler-Muehle' small hydropower station in Lausen - Revitalisation of a historic power station; Vorstudie Kleinwasserkraftwerk Haegler-Muehle, Lausen. Revitalisierung des historischen Kraftwerkes

Energy Technology Data Exchange (ETDEWEB)

Wohlfender, M.; Bretscher, A.; Gutzwiller, S.

2002-07-01

This report for the Swiss Federal Office of Energy (SFOE) presents the results of a study made on the revitalisation of a 62 kW power station on the river Ergolz in Lausen in north-western Switzerland. The waters of this river have been used here for driving turbines since 1898. The report describes the proposed reactivation of the existing turbine, built in 1948, that has now been out of service for several years. Various enhancements including measures to cope with flooding and to reduce noise are described. The particular problems of reactivating this hydropower plant, whose turbine house is a listed building, and of operation next to the adjacent old mill - also listed and now converted to apartments - are examined. Also, the possible construction of a fish pass as a prerequisite for green-power certification of the plant is discussed.

40 CFR 721.10086 - Ethane, 2-(difluoromethoxy)-1,1,1-trifluoro-.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 30 2010-07-01 2010-07-01 false Ethane, 2-(difluoromethoxy)-1,1,1... Specific Chemical Substances § 721.10086 Ethane, 2-(difluoromethoxy)-1,1,1-trifluoro-. (a) Chemical substance and significant new uses subject to reporting. (1) The chemical substance identified as ethane, 2...

Shikonin regulates C-MYC and GLUT1 expression through the MST1-YAP1-TEAD1 axis

Energy Technology Data Exchange (ETDEWEB)

Vališ, Karel, E-mail: karel.valis@biomed.cas.cz [Laboratory of Structural Biology and Cell Signaling, Institute of Microbiology, v.v.i., The Czech Academy of Sciences, Prague (Czech Republic); Faculty of Science, Charles University, Prague (Czech Republic); Talacko, Pavel; Grobárová, Valéria [Laboratory of Structural Biology and Cell Signaling, Institute of Microbiology, v.v.i., The Czech Academy of Sciences, Prague (Czech Republic); Faculty of Science, Charles University, Prague (Czech Republic); Černý, Jan [Faculty of Science, Charles University, Prague (Czech Republic); Novák, Petr, E-mail: pnovak@biomed.cas.cz [Laboratory of Structural Biology and Cell Signaling, Institute of Microbiology, v.v.i., The Czech Academy of Sciences, Prague (Czech Republic); Faculty of Science, Charles University, Prague (Czech Republic)

2016-12-10

The general mechanism underlying the tumor suppressor activity of the Hippo signaling pathway remains unclear. In this study, we explore the molecular mechanisms connecting the Hippo signaling pathway with glucose metabolism. We have found that two key regulators of glycolysis, C-MYC and GLUT1, are targets of the Hippo signaling pathway in human leukemia cells. Our results revealed that activation of MST1 by the natural compound shikonin inhibited the expression of GLUT1 and C-MYC. Furthermore, RNAi experiments confirmed the regulation of GLUT1 and C-MYC expression via the MST1-YAP1-TEAD1 axis. Surprisingly, YAP1 was found to positively regulate C-MYC mRNA levels in complex with TEAD1, while it negatively regulates C-MYC levels in cooperation with MST1. Hence, YAP1 serves as a rheostat for C-MYC, which is regulated by MST1. In addition, depletion of MST1 stimulates lactate production, whereas the specific depletion of TEAD1 has an opposite effect. The inhibition of lactate production and cellular proliferation induced by shikonin also depends on the Hippo pathway activity. Finally, a bioinformatic analysis revealed conserved TEAD-binding motifs in the C-MYC and GLUT1 promoters providing another molecular data supporting our observations. In summary, regulation of glucose metabolism could serve as a new tumor suppressor mechanism orchestrated by the Hippo signaling pathway. - Highlights: • Shikonin inhibits C-MYC and GLUT1 expression in MST1 and YAP1 dependent manner. • YAP1-TEAD1 interaction activates C-MYC and GLUT1 expression. • MST1 in cooperation with YAP1 inhibits C-MYC and GLUT1 expression. • MST1-YAP1-TEAD1 axis regulates lactate production by leukemic cells. • MST1 and YAP1 proteins block proliferation of leukemic cells.

Calculated trends and the atmospheric abundance of 1,1,1,2-tetrafluoroethane, 1,1-dichloro-1-fluoroethane, and 1-chloro-1,1-difluoroethane using automated in-situ gas chromatography-mass spectrometry measurements recorded at Mace Head, Ireland, from October 1994 to March 1997

Science.gov (United States)

Simmonds, P. G.; O'Doherty, S.; Huang, J.; Prinn, R.; Derwent, R. G.; Ryall, D.; Nickless, G.; Cunnold, D.

1998-01-01

The first in-situ measurements by automated gas chromatograph-mass spectrometer are reported for 1,1,1,2-tetrafluoroethane (HFC-134a), 1,1-dichloro-1-fluoroethane, (HCFC-141b), and 1-chloro-1,1-difluoroethane, (HCFC-142b). These compounds are steadily replacing the chlorofluorocarbons (CFCs) as refrigerants, foam-blowing agents, and solvents. The concentrations of all three compounds are shown to be rapidly increasing in the atmosphere, with 134a increasing at a rate of 2.05±0.02 ppt yr-1 over the 30 months of observations. Similarly, 141b and 142b increased at rates of 2.49±0.03 and 1.24±0.02 ppt yr-1, respectively, over the same period. The concentrations recorded at the atmospheric research station at Mace Head, Ireland, on January 1, 1996, the midpoint of the time series, were 3.67 ppt (134a), 7.38 ppt (141b), and 8.78 ppt (142b). From these observations we optimally estimate the HCFC and HFC emissions using a 12-box global model and OH concentrations derived from global 1,1,1-trichloroethane (CCl3CH3) measurements. Comparing two methods of estimating emissions with independent industry estimates shows satisfactory agreement for 134a and 141b, while for 142b, industry estimates are less than half those required to explain our observations.

Polarity driven morphology of CeO{sub 2}(1 0 0) islands on Cu(1 1 1)

Energy Technology Data Exchange (ETDEWEB)

Stetsovych, O., E-mail: stetsovycholeksandr@gmail.com; Beran, J.; Dvořák, F.; Mašek, K.; Mysliveček, J., E-mail: Josef.Myslivecek@mff.cuni.cz; Matolín, V.

2013-11-15

Thin ceria films supported by metal substrates represent important model systems for reactivity studies in heterogeneous catalysis. Here we report the growth study of the polar CeO{sub 2}(1 0 0) phase as part of a mixed CeO{sub 2}(1 1 1)–CeO{sub 2}(1 0 0) thin film supported by Cu(1 1 1). The two ceria phases grow on different areas of the substrate, what allows a reliable growth characterization of the CeO{sub 2}(1 0 0) islands on Cu(1 1 1). Scanning tunneling microscopy measurements reveal CeO{sub 2}(1 0 0) to grow in the form of highly dispersed three dimensional (3D) islands on a CeO{sub 2}(1 0 0) interfacial layer. The CeO{sub 2}(1 0 0) islands exhibit a 2 × 2 surface reconstruction. The presence of the surface reconstruction together with the highly dispersed growth of CeO{sub 2}(1 0 0) islands corresponds to the requirement for compensation of the surface dipole moment on the CeO{sub 2}(1 0 0). CeO{sub 2}(1 0 0) islands are further characterized by reflection high energy electron diffraction yielding their epitaxial relations with respect to the Cu(1 1 1) substrate. The growth of well characterized CeO{sub 2}(1 0 0) islands supported by Cu(1 1 1) represents a starting point for developing a novel template for structure-related reactivity studies of ceria based model catalysts.

Genetic regulation of IL1RL1 methylation and IL1RL1-a protein levels in asthma.

Science.gov (United States)

Dijk, F Nicole; Xu, Chengjian; Melén, Erik; Carsin, Anne-Elie; Kumar, Asish; Nolte, Ilja M; Gruzieva, Olena; Pershagen, Goran; Grotenboer, Neomi S; Savenije, Olga E M; Antó, Josep Maria; Lavi, Iris; Dobaño, Carlota; Bousquet, Jean; van der Vlies, Pieter; van der Valk, Ralf J P; de Jongste, Johan C; Nawijn, Martijn C; Guerra, Stefano; Postma, Dirkje S; Koppelman, Gerard H

2018-03-01

Interleukin-1 receptor-like 1 ( IL1RL1 ) is an important asthma gene. (Epi)genetic regulation of IL1RL1 protein expression has not been established. We assessed the association between IL1RL1 single nucleotide polymorphisms (SNPs), IL1RL1 methylation and serum IL1RL1-a protein levels, and aimed to identify causal pathways in asthma.Associations of IL1RL1 SNPs with asthma were determined in the Dutch Asthma Genome-wide Association Study cohort and three European birth cohorts, BAMSE (Children/Barn, Allergy, Milieu, Stockholm, an Epidemiological survey), INMA (Infancia y Medio Ambiente) and PIAMA (Prevention and Incidence of Asthma and Mite Allergy), participating in the Mechanisms of the Development of Allergy study. We performed blood DNA IL1RL1 methylation quantitative trait locus (QTL) analysis (n=496) and (epi)genome-wide protein QTL analysis on serum IL1RL1-a levels (n=1462). We investigated the association of IL1RL1 CpG methylation with asthma (n=632) and IL1RL1-a levels (n=548), with subsequent causal inference testing. Finally, we determined the association of IL1RL1-a levels with asthma and its clinical characteristics (n=1101). IL1RL1 asthma-risk SNPs strongly associated with IL1RL1 methylation (rs1420101; p=3.7×10 -16 ) and serum IL1RL1-a levels (p=2.8×10 -56 ). IL1RL1 methylation was not associated with asthma or IL1RL1-a levels. IL1RL1-a levels negatively correlated with blood eosinophil counts, whereas there was no association between IL1RL1-a levels and asthma.In conclusion, asthma-associated IL1RL1 SNPs strongly regulate IL1RL1 methylation and serum IL1RL1-a levels, yet neither these IL1RL1- methylation CpG sites nor IL1RL1-a levels are associated with asthma. Copyright ©ERS 2018.

S1P in HDL promotes interaction between SR-BI and S1PR1 and activates S1PR1-mediated biological functions: calcium flux and S1PR1 internalization[S

Science.gov (United States)

Lee, Mi-Hye; Appleton, Kathryn M.; El-Shewy, Hesham M.; Sorci-Thomas, Mary G.; Thomas, Michael J.; Lopes-Virella, Maria F.; Luttrell, Louis M.; Hammad, Samar M.; Klein, Richard L.

2017-01-01

HDL normally transports about 50–70% of plasma sphingosine 1-phosphate (S1P), and the S1P in HDL reportedly mediates several HDL-associated biological effects and signaling pathways. The HDL receptor, SR-BI, as well as the cell surface receptors for S1P (S1PRs) may be involved partially and/or completely in these HDL-induced processes. Here we investigate the nature of the HDL-stimulated interaction between the HDL receptor, SR-BI, and S1PR1 using a protein-fragment complementation assay and confocal microscopy. In both primary rat aortic vascular smooth muscle cells and HEK293 cells, the S1P content in HDL particles increased intracellular calcium concentration, which was mediated by S1PR1. Mechanistic studies performed in HEK293 cells showed that incubation of cells with HDL led to an increase in the physical interaction between the SR-BI and S1PR1 receptors that mainly occurred on the plasma membrane. Model recombinant HDL (rHDL) particles formed in vitro with S1P incorporated into the particle initiated the internalization of S1PR1, whereas rHDL without supplemented S1P did not, suggesting that S1P transported in HDL can selectively activate S1PR1. In conclusion, these data suggest that S1P in HDL stimulates the transient interaction between SR-BI and S1PRs that can activate S1PRs and induce an elevation in intracellular calcium concentration. PMID:27881715

resources 1..1

Indian Academy of Sciences (India)

http://www.ias.ac.in/jgenet/OnlineResources/90/e34.pdf. Morinha F., Carvalho M., Ferro A., Guedes-Pinto H., Rodrigues R. and Bastos E. 2011 Molecular sexing and analysis of CHD1-Z and. CHD1-W sequence variations in wild common quail (Coturnix c. coturnix) and domesticated Japanese quail (Coturnix c. japonica).

Helium diffraction study of pentacene films on Au(1 1 1)

Energy Technology Data Exchange (ETDEWEB)

Albayrak, E. [Department of Materials and Metallurgical Engineering, Ahi Evran University, Kırşehir 40000 (Turkey); Danışman, M.F., E-mail: danisman@metu.edu.tr [Department of Chemistry, Middle East Technical University, Ankara 06531 (Turkey)

2014-03-01

Highlights: • Pentacene films were grown by supersonic molecular beam deposition on Au(1 1 1). • Simultaneous helium scattering and quartz crystal resonance frequency shift measurements were performed. • Helium diffraction results were consistent with a (6 × 3) monolayer structure. • No ordered multilayers could be observed. - Abstract: Here we present a helium atom diffraction study of pentacene films on Au(1 1 1) surface prepared by supersonic molecular beam deposition. Though investigated parameter space was limited no significant difference between the films prepared by different deposition energies was observed. Completion of monolayer coverage was confirmed by simultaneous helium scattering and quartz crystal resonance frequency shift measurements during pentacene film growth on the gold electrode of a quartz resonator. Monolayer films were found to adopt a (6 × 3) unit cell which was also observed for pentacene monolayers on Ag(1 1 1). However no ordered multilayer film structure could be observed which is in contrast with the previous Ag(1 1 1) studies.

Myeloid cell leukemia-1 (Mc1-1 is a candidate target gene of hypoxia-inducible factor-1 (HIF-1 in the testis

Directory of Open Access Journals (Sweden)

Palladino Michael A

2012-12-01

Full Text Available Abstract Background Spermatic cord torsion can lead to testis ischemia (I and subsequent ischemia-reperfusion (I/R causing germ cell-specific apoptosis. Previously, we demonstrated that the hypoxia-inducible factor-1 (HIF-1 transcription factor, a key regulator of physiological responses to hypoxia, is abundant in Leydig cells in normoxic and ischemic testes. We hypothesize that testicular HIF-1 activates the expression of antiapoptotic target genes to protect Leydig cells from apoptosis. In silico analysis of testis genes containing a consensus hypoxia response element (HRE, 5’-RCGTG-3’ identified myeloid cell leukemia-1 (Mcl-1 as a potential HIF-1 target gene. The purpose of this study was to determine whether HIF-1 shows DNA-binding activity in normoxic and ischemic testes and whether Mcl-1 is a target gene of testicular HIF-1. Methods The testicular HIF-1 DNA-binding capacity was analyzed in vitro using a quantitative enzyme-linked immunosorbent assay (ELISA and electrophoretic mobility shift assays (EMSA. MCL-1 protein expression was evaluated by immunoblot analysis and immunohistochemistry. The binding of testicular HIF-1 to the Mcl-1 gene was examined via chromatin immunoprecipitation (ChIP analysis. Results The ELISA and EMSA assays demonstrated that testicular HIF-1 from normoxic and ischemic testes binds DNA equally strongly, suggesting physiological roles for HIF-1 in the normoxic testis, unlike most tissues in which HIF-1 is degraded under normoxic conditions and is only activated by hypoxia. MCL-1 protein was determined to be abundant in both normoxic and ischemic testes and expressed in Leydig cells. In a pattern identical to that of HIF-1 expression, the steady-state levels of MCL-1 were not significantly affected by I or I/R and MCL-1 co-localized with HIF-1α in Leydig cells. Chromatin immunoprecipitation (ChIP analysis using a HIF-1 antibody revealed sequences enriched for the Mcl-1 promoter. Conclusions The results

Asymmetric oxidation of 1,3-dithianes to 1,3-dithiane 1-oxides

OpenAIRE

Yoshihiko, Watanabe; Yojiro, Ono; Yoshio, Ueno; Takeshi, Toru

1998-01-01

Oxidation of 2-(1-hydroxy-1-methylethyl)-1,3-dithiane with the Sharpless reagent has been examined under various reaction conditions. Oxidation of 2-(1-hydroxy-1-methylethyl)-1,3-dithiane with Ti(OPri)4-diethyl L-(+)-tartrate-tert-butyl hydroperoxide (1:2:1.5) in CH2Cl2 in the presence of 4 A molecular sieves gives (1S,2S)-2-(1-hydroxy-1-methylethyl)-1,3-dithiane 1-oxide with high trans selectivity and with moderate enantioselectivity. The enantioselectivity depends upon the substituent at t...

30 CFR 1.1 - Official emblem.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Official emblem. 1.1 Section 1.1 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR OFFICIAL EMBLEM AND OMB CONTROL NUMBERS... OFFICIAL EMBLEM § 1.1 Official emblem. The following emblem is established and shall be used as the...

Blocking S1P interaction with S1P1 receptor by a novel competitive S1P1-selective antagonist inhibits angiogenesis

International Nuclear Information System (INIS)

Fujii, Yasuyuki; Ueda, Yasuji; Ohtake, Hidenori; Ono, Naoya; Takayama, Tetsuo; Nakazawa, Kiyoshi; Igarashi, Yasuyuki; Goitsuka, Ryo

2012-01-01

Highlights: ► The effect of a newly developed S1P 1 -selective antagonist on angiogenic responses. ► S1P 1 is a critical component of VEGF-related angiogenic responses. ► S1P 1 -selective antagonist showed in vitro activity to inhibit angiogenesis. ► S1P 1 -selective antagonist showed in vivo activity to inhibit angiogenesis. ► The efficacy of S1P 1 -selective antagonist for anti-cancer therapies. -- Abstract: Sphingosine 1-phosphate receptor type 1 (S1P 1 ) was shown to be essential for vascular maturation during embryonic development and it has been demonstrated that substantial crosstalk exists between S1P 1 and other pro-angiogenic growth factors, such as vascular endothelial growth factor (VEGF) and basic fibroblast growth factor. We developed a novel S1P 1 -selective antagonist, TASP0277308, which is structurally unrelated to S1P as well as previously described S1P 1 antagonists. TASP0277308 inhibited S1P- as well as VEGF-induced cellular responses, including migration and proliferation of human umbilical vein endothelial cells. Furthermore, TASP0277308 effectively blocked a VEGF-induced tube formation in vitro and significantly suppressed tumor cell-induced angiogenesis in vivo. These findings revealed that S1P 1 is a critical component of VEGF-related angiogenic responses and also provide evidence for the efficacy of TASP0277308 for anti-cancer therapies.

1,1′-{1,4-Phenylene bis[3-(6-chloro-2-methyl-4-phenylquinolin-3-yl-4,5-dihydro-1H-pyrazole-5,1-diyl]}dibutan-1-one

Directory of Open Access Journals (Sweden)

Allaoua Kedjadja

2015-10-01

Full Text Available A new polycyclic compound, 1,1′-{1,4-phenylene bis[3-(6-chloro-2-methyl-4-phenylquinolin-3-yl-4,5-dihydro-1H-pyrazole-5,1-diyl]}dibutan-1-one (3 has been synthesized by cyclocondensation of (2E,2′E-1,1′-bis(6-chloro-2-methyl-4-phenylquinolin-3-yl-3,3′-(1,4-phenylenediprop-2-en-1-one (2 and hydrazine hydrate in butanoic acid. The structure of this compound was established by elemental analysis, 1H-NMR, 13C-NMR, mass and IR spectroscopy.

PENINGKATAN KUALITAS DAN PROSES PEMBUATAN BIODIESEL DARI BLENDING MINYAK KELAPA SAWIT (PALM OIL DAN MINYAK KELAPA (COCONUT OIL DAN BANTUAN GELOMBANG ULTRASONIK

Directory of Open Access Journals (Sweden)

Hantoro Satriadi

2015-01-01

Full Text Available Keterbatasan solar sebagai sumber energi bahan bakunya tidak dapat diperbaharui menuntut adanya bahan baku alternatif yang dapat diperbaharui dan ramah lingkungan untuk pembuatan biodiesel. Reaksi utama produksi biodiesel adalah esterifikasi dan transestirifikasi yang berlangsung lambat dan membutuhkan banyak katalis dan alkohol. Reaksi yang terjadi belum sempurna dan belum memenuhi standar SNI dan ASTM. Untuk memperbaiki mutu biodiesel serta menghasilkan yield maksimal, maka dilakukan blending bahan baku antara minyak kelapa sawit dan minyak kelapa dan dengan bantuan gelombang ultrasonic. Penelitian ini bertujuan untuk mempelajari pengaruh variabel perbandingan volume minyak kelapa sawit dan minyak kelapa, perbandingan volume methanolminyak, dan persentase berat katalis terhadap minyak terhadap hasil atau yield biodiesel. Alat utama yang digunakan adalah reaktor yang dilengkapi pembangkit gelombang ultrasonic dengan temperature 60 oC, tekanan 1 atm, volume 3 liter, dan frekuensi 28 kHz. Variabel proses pada penelitian ini adalah perbandingan volume minyak sawit dan kelapa 2:1, 3:1, dan 4:1, pebandingan volume metanol-minyak 0,2:1, 0,25:1, dan 0,3:1, dan persentase berat katalis KOH terhadap minyak 0,3%, 0,5%, dan 0,7%. Hasil penelitian didapat konversi tertinggi dicapai pada variabel perbandingan volume minyak sawit dan kelapa 3:1, perbandingan volume metanol/minyak 0,25:1, dan persentase berat katalis terhadap minyak dengan yield 97,26%.[A Improvement of Quality and Process for Biodiesel Production from Palm Oil and Coconut Oil Blends with Ultrasound Assisted] Limitations of solar energy as a source of raw material cannot be renewed demands for alternative raw materials that are renewable and environmentally friendly for the manufacture of biodiesel. The main production of biodiesel reaction is esterification and transestirifikasi which runs slow and requires a lot of alcohol and a catalyst. Reactions that happen yet perfect, and has not met

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

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

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

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.

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

Abiotic and biotic transformations of 1,1,1-trichloroethane under methanogenic conditions

International Nuclear Information System (INIS)

Vogel, T.M.; McCarty, P.L.

1987-01-01

A common industrial solvent, 1,1,1-trichloroethane (TCA), is one of the most frequently found contaminants in ground water. The fate of TCA in ground water is complicated by the different possible abiotic and biotic transformations that it may undergo. Abiotic transformation of TCA can result in a mixture of 1,1-dichloro-ethylene (1,1-DCE) and acetic acid, as shown by others. This study confirms that TCA can be biotransformed by reductive dehalogenation to 1,1-dichloroethane (1,1-DCA) and chloroethane (CA) under methanogenic conditions. Also, reductive dehalogenation of 1,1-DCE to vinyl chloride (VC) is confirmed. This study demonstrates that these transformations can occur stoichiometrically. In addition, [ 14 C]TCA, [ 14 C]-1,1-DCA, [ 14 C]-1,1-DCE, [ 14 C]CA, and [ 14 C]VC were at least partially mineralized to 14 CO 2 under similar methanogenic conditions.23 references, 3 figures, 4 tables

Soil and Terrain Database for Upper Tana River Catchment (version 1.1) - scale 1:250,000 (SOTER_UT_v1.1)

NARCIS (Netherlands)

Dijkshoorn, J.A.; Macharia, P.; Kempen, B.

2014-01-01

The Soil and Terrain database for the Upper Tana River Catchment (version 1.1) (SOTER_UT_v1.1) at scale 1:250,000 was compiled to support the Green Water Credits (GWC) programme by creating a primary SOTER dataset for a hydrology assessment of the basin. The Kenya Soil Survey of the Kenya

Protective efficacy of an inactivated Eurasian avian-like H1N1 swine influenza vaccine against homologous H1N1 and heterologous H1N1 and H1N2 viruses in mice.

Science.gov (United States)

Sui, Jinyu; Yang, Dawei; Qiao, Chuanling; Xu, Huiyang; Xu, Bangfeng; Wu, Yunpu; Yang, Huanliang; Chen, Yan; Chen, Hualan

2016-07-19

Eurasian avian-like H1N1 (EA H1N1) swine influenza viruses are prevalent in pigs in Europe and Asia, but occasionally cause human infection, which raises concern about their pandemic potential. Here, we produced a whole-virus inactivated vaccine with an EA H1N1 strain (A/swine/Guangxi/18/2011, SW/GX/18/11) and evaluated its efficacy against homologous H1N1 and heterologous H1N1 and H1N2 influenza viruses in mice. A strong humoral immune response, which we measured by hemagglutination inhibition (HI) and virus neutralization (VN), was induced in the vaccine-inoculated mice upon challenge. The inactivated SW/GX/18/11 vaccine provided complete protection against challenge with homologous SW/GX/18/11 virus in mice and provided effective protection against challenge with heterologous H1N1 and H1N2 viruses with distinctive genomic combinations. Our findings suggest that this EA H1N1 vaccine can provide protection against both homologous H1N1 and heterologous H1N1 or H1N2 virus infection. As such, it is an excellent vaccine candidate to prevent H1N1 swine influenza. Copyright © 2016 Elsevier Ltd. All rights reserved.

Closed expressions for $\\int_{0}^{1} t^{-1} log^{n-1}t log^{p}(1 - t) dt$

CERN Document Server

Kölbig, Kurt Siegfried

1982-01-01

Closed expressions for the integral integral /sub 0//sup 1/ t/sup -1/ log/sup n-1/t log/sup p/(1-t)dt, whose general form is given elsewhere, are listed for n=1(1)9, p=1(1)9. A formula is derived which allows an easy evaluation of these expressions by formula manipulation on a computer. The majority of the above expressions are given in a microfiche supplement to the paper.

26 CFR 1.72-1 - Introduction.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Introduction. 1.72-1 Section 1.72-1 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE TREASURY (CONTINUED) INCOME TAX (CONTINUED) INCOME TAXES (CONTINUED) Items Specifically Included in Gross Income § 1.72-1 Introduction. (a) General...

Sigma-1 receptor agonists directly inhibit Nav1.2/1.4 channels.

Directory of Open Access Journals (Sweden)

Xiao-Fei Gao

Full Text Available (+-SKF 10047 (N-allyl-normetazocine is a prototypic and specific sigma-1 receptor agonist that has been used extensively to study the function of sigma-1 receptors. (+-SKF 10047 inhibits K(+, Na(+ and Ca2+ channels via sigma-1 receptor activation. We found that (+-SKF 10047 inhibited Na(V1.2 and Na(V1.4 channels independently of sigma-1 receptor activation. (+-SKF 10047 equally inhibited Na(V1.2/1.4 channel currents in HEK293T cells with abundant sigma-1 receptor expression and in COS-7 cells, which barely express sigma-1 receptors. The sigma-1 receptor antagonists BD 1063,BD 1047 and NE-100 did not block the inhibitory effects of (+-SKF-10047. Blocking of the PKA, PKC and G-protein pathways did not affect (+-SKF 10047 inhibition of Na(V1.2 channel currents. The sigma-1 receptor agonists Dextromethorphan (DM and 1,3-di-o-tolyl-guanidine (DTG also inhibited Na(V1.2 currents through a sigma-1 receptor-independent pathway. The (+-SKF 10047 inhibition of Na(V1.2 currents was use- and frequency-dependent. Point mutations demonstrated the importance of Phe(1764 and Tyr(1771 in the IV-segment 6 domain of the Na(V1.2 channel and Phe(1579 in the Na(V1.4 channel for (+-SKF 10047 inhibition. In conclusion, our results suggest that sigma-1 receptor agonists directly inhibit Na(V1.2/1.4 channels and that these interactions should be given special attention for future sigma-1 receptor function studies.

45 CFR 1220.1-1 - Introduction.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Introduction. 1220.1-1 Section 1220.1-1 Public Welfare Regulations Relating to Public Welfare (Continued) CORPORATION FOR NATIONAL AND COMMUNITY SERVICE PAYMENT OF VOLUNTEER LEGAL EXPENSES General § 1220.1-1 Introduction. Section 419 of the Domestic Volunteer...

26 CFR 1.545-1 - Definition.

Science.gov (United States)

2010-04-01

... TAXES (CONTINUED) Personal Holding Companies § 1.545-1 Definition. (a) Undistributed personal holding company income is the amount which is subject to the personal holding company tax imposed under section... 26 Internal Revenue 7 2010-04-01 2010-04-01 true Definition. 1.545-1 Section 1.545-1 Internal...

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

26 CFR 1.556-1 - Definition.

Science.gov (United States)

2010-04-01

... TAXES (CONTINUED) Foreign Personal Holding Companies § 1.556-1 Definition. Undistributed foreign personal holding company income is the amount which is to be included in the gross income of the United... 26 Internal Revenue 7 2010-04-01 2010-04-01 true Definition. 1.556-1 Section 1.556-1 Internal...

26 CFR 1.801-1 - Definitions.

Science.gov (United States)

2010-04-01

... TAXES Life Insurance Companies § 1.801-1 Definitions. (a) Life insurance company. The term life.... For the definition of an “insurance company”, see paragraph (b) of this section. In determining... 26 Internal Revenue 8 2010-04-01 2010-04-01 false Definitions. 1.801-1 Section 1.801-1 Internal...

26 CFR 1.165-1 - Losses.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Losses. 1.165-1 Section 1.165-1 Internal Revenue... (CONTINUED) Itemized Deductions for Individuals and Corporations § 1.165-1 Losses. (a) Allowance of deduction. Section 165(a) provides that, in computing taxable income under section 63, any loss actually sustained...

A universal concept for IV-supported operation management; Ein universelles Konzept fuer die IV-gestuetzte Betriebsfuehrung

Energy Technology Data Exchange (ETDEWEB)

Sturm, A.

1997-12-31

The continuing rise in cost pressure calls for measures for enhancing the efficiency of operation management and maintenance. At the same time it is necessary to maintain the requisite reliability of production and keep abreast of the ever more stringent requirements of working safety and environment protection. This paper presents an integral operation management system for production plants which does justice to both the productive and the and the conserving function of operation management. The development and introduction of this system to conventional power plants has meanwhile begun. The system consistently gives consideration to the fact that operation management depends on processing data and information of different properties. Whereas process data can show strong fluctuations, there are many kinds of information on the plant concerning, for example, plant installations, processes, damage, and maintenance which hardly fluctuate at all or only change over long time periods. These latter include plant and installation addresses, technical data on the system or on maintenance. In operation management systems designed for production plants it can therefore be useful to organise the handling of process data (dynamic data) and plant data (static data) separately. [Deutsch] Der immer staerkere Kostendruck erfordert Massnahmen zur Effizienzsteigerung der Betriebsfuehrung und der Instandhaltung bei Erhaltung der erforderlichen Zuverlaessigkeit der Produktion, steigenden Anforderungen an Arbeitssicherheit und Umweltschutz. Ein Gesamtbetriebsfuehrungssystem, das sowohl die Produktionsfunktion, als auch die Erhaltungsfunktion abdeckt, wurde fuer Produktionsanlagen konzipiert. Fuer konventionelle Kraftwerke wurde die Entwicklung und Einfuehrung begonnen. Dieses System beruecksichtigt konsequent, dass bei der Betriebsfuehrung Daten und Informationen mit unterschiedlichen Eigenschaften zu verarbeiten sind. Waehrend die Prozessdaten hoch fluktuierende Daten sein koennen

Transparency and efficiency through plant operations management systems; Transparenz und Effizienz durch Betriebsfuehrungssysteme

Energy Technology Data Exchange (ETDEWEB)

Ladage, L. [RWE Power AG, Essen (Germany). Informationsmanagement

2001-04-01

. Diese werden mit ca. 4 Minuten bzw. 10 DM pro Arbeitsschritt angegeben, entsprechend einigen Dutzend Mannjahren bzw. mehreren Mio. DM pro Jahr bei der betrachteten Anlage KKE, wobei das Ergebnis auf andere Kraftwerke uebertragbar ist. (orig.)

Interaction of environmental contaminants with zebrafish organic anion transporting polypeptide, Oatp1d1 (Slco1d1)

Energy Technology Data Exchange (ETDEWEB)

Popovic, Marta; Zaja, Roko [Laboratory for Molecular Ecotoxicology, Division for Marine and Environmental Research, Rudjer Boskovic Institute, Bijenicka 54, 10 000 Zagreb (Croatia); Fent, Karl [University of Applied Sciences Northwestern Switzerland, School of Life Sciences, Gründenstrasse 40, CH-4132 Muttenz (Switzerland); Swiss Federal Institute of Technology (ETH Zürich), Department of Environmental System Sciences, Institute of Biogeochemistry and Pollution Dynamics, CH-8092 Zürich (Switzerland); Smital, Tvrtko, E-mail: smital@irb.hr [Laboratory for Molecular Ecotoxicology, Division for Marine and Environmental Research, Rudjer Boskovic Institute, Bijenicka 54, 10 000 Zagreb (Croatia)

2014-10-01

Polyspecific transporters from the organic anion transporting polypeptide (OATP/Oatp) superfamily mediate the uptake of a wide range of compounds. In zebrafish, Oatp1d1 transports conjugated steroid hormones and cortisol. It is predominantly expressed in the liver, brain and testes. In this study we have characterized the transport of xenobiotics by the zebrafish Oatp1d1 transporter. We developed a novel assay for assessing Oatp1d1 interactors using the fluorescent probe Lucifer yellow and transient transfection in HEK293 cells. Our data showed that numerous environmental contaminants interact with zebrafish Oatp1d1. Oatp1d1 mediated the transport of diclofenac with very high affinity, followed by high affinity towards perfluorooctanesulfonic acid (PFOS), nonylphenol, gemfibrozil and 17α-ethinylestradiol; moderate affinity towards carbaryl, diazinon and caffeine; and low affinity towards metolachlor. Importantly, many environmental chemicals acted as strong inhibitors of Oatp1d1. A strong inhibition of Oatp1d1 transport activity was found by perfluorooctanoic acid (PFOA), chlorpyrifos-methyl, estrone (E1) and 17β-estradiol (E2), followed by moderate to low inhibition by diethyl phthalate, bisphenol A, 7-acetyl-1,1,3,4,4,6-hexamethyl-1,2,3,4 tetrahydronapthalene and clofibrate. In this study we identified Oatp1d1 as a first Solute Carrier (SLC) transporter involved in the transport of a wide range of xenobiotics in fish. Considering that Oatps in zebrafish have not been characterized before, our work on zebrafish Oatp1d1 offers important new insights on the understanding of uptake processes of environmental contaminants, and contributes to the better characterization of zebrafish as a model species. - Highlights: • We optimized a novel assay for determination of Oatp1d1 interactors • Oatp1d1 is the first SLC characterized fish xenobiotic transporter • PFOS, nonylphenol, diclofenac, EE2, caffeine are high affinity Oatp1d1substrates • PFOA, chlorpyrifos

Interaction of environmental contaminants with zebrafish organic anion transporting polypeptide, Oatp1d1 (Slco1d1)

International Nuclear Information System (INIS)

Popovic, Marta; Zaja, Roko; Fent, Karl; Smital, Tvrtko

2014-01-01

Polyspecific transporters from the organic anion transporting polypeptide (OATP/Oatp) superfamily mediate the uptake of a wide range of compounds. In zebrafish, Oatp1d1 transports conjugated steroid hormones and cortisol. It is predominantly expressed in the liver, brain and testes. In this study we have characterized the transport of xenobiotics by the zebrafish Oatp1d1 transporter. We developed a novel assay for assessing Oatp1d1 interactors using the fluorescent probe Lucifer yellow and transient transfection in HEK293 cells. Our data showed that numerous environmental contaminants interact with zebrafish Oatp1d1. Oatp1d1 mediated the transport of diclofenac with very high affinity, followed by high affinity towards perfluorooctanesulfonic acid (PFOS), nonylphenol, gemfibrozil and 17α-ethinylestradiol; moderate affinity towards carbaryl, diazinon and caffeine; and low affinity towards metolachlor. Importantly, many environmental chemicals acted as strong inhibitors of Oatp1d1. A strong inhibition of Oatp1d1 transport activity was found by perfluorooctanoic acid (PFOA), chlorpyrifos-methyl, estrone (E1) and 17β-estradiol (E2), followed by moderate to low inhibition by diethyl phthalate, bisphenol A, 7-acetyl-1,1,3,4,4,6-hexamethyl-1,2,3,4 tetrahydronapthalene and clofibrate. In this study we identified Oatp1d1 as a first Solute Carrier (SLC) transporter involved in the transport of a wide range of xenobiotics in fish. Considering that Oatps in zebrafish have not been characterized before, our work on zebrafish Oatp1d1 offers important new insights on the understanding of uptake processes of environmental contaminants, and contributes to the better characterization of zebrafish as a model species. - Highlights: • We optimized a novel assay for determination of Oatp1d1 interactors • Oatp1d1 is the first SLC characterized fish xenobiotic transporter • PFOS, nonylphenol, diclofenac, EE2, caffeine are high affinity Oatp1d1substrates • PFOA, chlorpyrifos

Sphingosine-1-phosphate (S1P) displays sustained S1P1 receptor agonism and signaling through S1P lyase-dependent receptor recycling.

Science.gov (United States)

Gatfield, John; Monnier, Lucile; Studer, Rolf; Bolli, Martin H; Steiner, Beat; Nayler, Oliver

2014-07-01

The sphingosine-1-phosphate (S1P) type 1 receptor (S1P1R) is a novel therapeutic target in lymphocyte-mediated autoimmune diseases. S1P1 receptor desensitization caused by synthetic S1P1 receptor agonists prevents T-lymphocyte egress from secondary lymphoid organs into the circulation. The selective S1P1 receptor agonist ponesimod, which is in development for the treatment of autoimmune diseases, efficiently reduces peripheral lymphocyte counts and displays efficacy in animal models of autoimmune disease. Using ponesimod and the natural ligand S1P, we investigated the molecular mechanisms leading to different signaling, desensitization and trafficking behavior of S1P1 receptors. In recombinant S1P1 receptor-expressing cells, ponesimod and S1P triggered Gαi protein-mediated signaling and β-arrestin recruitment with comparable potency and efficiency, but only ponesimod efficiently induced intracellular receptor accumulation. In human umbilical vein endothelial cells (HUVEC), ponesimod and S1P triggered translocation of the endogenous S1P1 receptor to the Golgi compartment. However, only ponesimod treatment caused efficient surface receptor depletion, receptor accumulation in the Golgi and degradation. Impedance measurements in HUVEC showed that ponesimod induced only short-lived Gαi protein-mediated signaling followed by resistance to further stimulation, whereas S1P induced sustained Gαi protein-mediated signaling without desensitization. Inhibition of S1P lyase activity in HUVEC rendered S1P an efficient S1P1 receptor internalizing compound and abrogated S1P-mediated sustained signaling. This suggests that S1P lyase - by facilitating S1P1 receptor recycling - is essential for S1P-mediated sustained signaling, and that synthetic agonists are functional antagonists because they are not S1P lyase substrates. Copyright © 2014 Elsevier Inc. All rights reserved.

USEEIO v1.1 - Matrices

Data.gov (United States)

U.S. Environmental Protection Agency — This dataset provides the basic building blocks for the USEEIO v1.1 model and life cycle results per $1 (2013 USD) demand for all goods and services in the model in...

Phenazine–naphthalene-1,5-diamine–water (1/1/2

Directory of Open Access Journals (Sweden)

Maria Gdaniec

2009-12-01

Full Text Available The asymmetric unit of the title compound, C12H8N2·C10H10N2·2H2O, contains one half-molecule of phenazine, one half-molecule of naphthalene-1,5-diamine and one water molecule. The phenazine and naphthalene-1,5-diamine molecules are located on inversion centers. The water molecules serve as bridges between the naphthalene-1,5-diamine molecules and also between the naphthalene-1,5-diamine and phenazine molecules. The naphthalene-1,5-diamine and water molecules are connected via N—H...O and O—H...N hydrogen bonds, forming a T4(2 motif. They are arranged into a two-dimensional polymeric structure parallel to (10overline{1} in which the water molecule is a single donor and a double acceptor, whereas the amino group is a double donor and a single acceptor in the hydrogen bonding. These two-dimensional assemblies alternate with the layers of phenazine molecules arranged into a herringbone motif. Each phenazine molecule is hydrogen bonded to two water molecules and thus a three-dimensional framework of hydrogen-bonded molecules is generated.

26 CFR 1.1053-1 - Property acquired before March 1, 1913.

Science.gov (United States)

2010-04-01

... chapter 1 of the Code, without reference to the fair market value as of March 1, 1913. (c) Example. The... the fair market value of $94,500 as of March 1, 1913, adjusted for depreciation allowed or allowable... other applicable provisions of chapter 1 of the Code, or its fair market value as of March 1, 1913...

Synthesis of dimethyl-1,1 guanylguanidine-{sup 14}C-2,4 (dimethyl-1-1 biguanide) hydrochloride; Synthese du chlorhydrate de dimethyl-1,1 guanylguanidine {sup 14}C-2,4 (dimethyl-1-1 biguanide)

Energy Technology Data Exchange (ETDEWEB)

Herbert, M; Pichat, L [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1961-07-01

A description of the synthesis of dimethyl-1,1 guanylguanidine-{sup 14}C-2,4 hydrochloride passing through the {sup 14}C{sub 2} dicyandiamide. The overall yield with respect to Ba{sup 14}CO{sub 3} is 38 per cent. (author) [French] Description de la synthese du chlorhydrate de dimethyl-1,1 guanylguanidine {sup 14}C-2,4 par l'intermediaire de la dicyandiamide {sup 14}C{sub 2}. Le rendement global par rapport a {sup 14}CO{sub 3}Ba est de 38 pour cent. (auteur)

Apurinic/apyrimidinic endonuclease1/redox factor-1 (Ape1/Ref-1) is essential for IL-21-induced signal transduction through ERK1/2 pathway

International Nuclear Information System (INIS)

Juliana, Farha M.; Nara, Hidetoshi; Onoda, Tadashi; Rahman, Mizanur; Araki, Akemi; Jin, Lianjin; Fujii, Hodaka; Tanaka, Nobuyuki; Hoshino, Tomoaki; Asao, Hironobu

2012-01-01

Highlights: ► IL-21 induces nuclear accumulation of Ape1/Ref-1 protein. ► Ape1/Ref-1 is indispensable in IL-21-induced cell proliferation and survival signal. ► Ape1/Ref-1 is required for IL-21-induced ERK1/2 activation. -- Abstract: IL-21 is a pleiotropic cytokine that regulates T-cell and B-cell differentiation, NK-cell activation, and dendritic cell functions. IL-21 activates the JAK-STAT, ERK, and PI3K pathways. We report here that Ape1/Ref-1 has an essential role in IL-21-induced cell growth signal transduction. Overexpression of Ape1/Ref-1 enhances IL-21-induced cell proliferation, but it is suppressed by overexpressing an N-terminal deletion mutant of Ape1/Ref-1 that lacks the redox domain. Furthermore, knockdown of the Ape1/Ref-1 mRNA dramatically compromises IL-21-induced ERK1/2 activation and cell proliferation with increasing cell death. These impaired activities are recovered by the re-expression of Ape1/Ref-1 in the knockdown cells. Our findings are the first demonstration that Ape1/Ref-1 is an indispensable molecule for the IL-21-mediated signal transduction through ERK1/2 activation.

48 CFR 1.602-1 - Authority.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Authority. 1.602-1 Section... ACQUISITION REGULATIONS SYSTEM Career Development, Contracting Authority, and Responsibilities 1.602-1 Authority. (a) Contracting officers have authority to enter into, administer, or terminate contracts and...

In vitro characterization of gE negative bovine herpesvirus types 1.1 (BHV-1.1 and 1.2a (BHV-1.2a Caracterização in vitro de herpes vírus bovino tipos 1.1 (BHV-1.1 e 1.2a (BHV-1.2a gE negativos

Directory of Open Access Journals (Sweden)

Fernando R. Spilki

2004-09-01

Full Text Available This study aimed the in vitro growth characterization of a previously constructed Brazilian bovine herpesvirus 1.2a with a deletion in the glycoprotein E gene (BHV-1.2a gE-. The plaque sizes, penetration and growth kinetics of the Brazilian BHV-1.2a gE- were studied and compared with the parental virus, as well as with a BHV-1.1 gE- recombinant derived from an European BHV-1.1 strain. No statistical differences were observed between the gE- recombinants and the respective parental viruses penetration assays were performed. When single step growth curves were studied, no statistical differences were observed between gE- and parental viruses. However, it was observed that both gE- viruses were excreted from cells in significantly higher titres at 11 hours post infection in comparison with parental viruses. No statistical differences were observed when plaque sizes of parental viruses or gE- viruses we analyzed separately in each cell type. However, both gE- recombinants displayed a significantly reduced plaque areas on three different cell cultures, in comparison with parental viruses, indicating that the lack of gE had the same effect on both BHV-1 subtypes, manifested by a restricted cell-to-cell spread in infected cells.O presente estudo teve como objetivo a caracterização das propriedades de crescimento in vitro de uma amostra brasileira de herpesvírus bovino tipo 1.2a que apresenta uma deleção no gene que codifica a glicoproteína E (BHV-1.2a gE-. Os tamanhos de placa, cinética de penetração e cinética de multiplicação do vírus BHV-1.2a gE- foram estudados e comparados com o vírus parental, bem como com um vírus BHV-1.1 gE- recombinante, o qual é derivado de uma amostra européia de BHV-1.1. Em termos de cinética de penetração, não foram observadas diferenças significativas quando comparados os vírus gE- com os parentais. A determinação da cinética de multiplicação não demonstrou diferenças significativas entre os

1 CFR 10.1 - Publication required.

Science.gov (United States)

2010-01-01

... 1 General Provisions 1 2010-01-01 2010-01-01 false Publication required. 10.1 Section 10.1 General Provisions ADMINISTRATIVE COMMITTEE OF THE FEDERAL REGISTER SPECIAL EDITIONS OF THE FEDERAL REGISTER PRESIDENTIAL PAPERS Regular Publication § 10.1 Publication required. The Director publishes a special edition...

Regional gene expression of LOX-1, VCAM-1, and ICAM-1 in aorta of HIV-1 transgenic rats

DEFF Research Database (Denmark)

Hag, Anne Mette Fisker; Kristoffersen, Ulrik Sloth; Pedersen, Sune Folke

2009-01-01

endpoints, studies in animal models could be attractive alternatives. METHODOLOGY/PRINCIPAL FINDINGS: We evaluated gene expression of lectin-like oxidized-low-density-lipoprotein receptor-1 (LOX-1), vascular cell adhesion molecule-1 (VCAM-1), and intercellular adhesion molecule-1 (ICAM-1) in HIV-1...... transgenic (HIV-1Tg) rats; these genes are all thought to play important roles in early atherogenesis. Furthermore, the plasma level of sICAM-1 was measured. We found that gene expressions of LOX-1 and VCAM-1 were higher in the aortic arch of HIV-1Tg rats compared to controls. Also, the level of sICAM-1......-infection per se may cause atherosclerosis. This transgenic rat model may be a very promising model for further studies of the pathophysiology behind HIV-associated cardiovascular disease....