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Evolution of the Number of Accreting White Dwarfs with Shell Nuclear Burning and the SNe Ia RateYUNGELSON, L. R.Astronomy letters (Print). 2010, Vol 36, Num 11, pp 780-787, issn 1063-7737, 8 p.Article

Effect of void-fraction on characteristics of several thorium fuel cycles in BWRWARIS, Abdul; ALI SHAFII, Mohamad; PRAMUDITYA, Syeilendra et al.Energy conversion and management. 2012, Vol 63, pp 11-16, issn 0196-8904, 6 p.Article

Burnup importance function introduced to give an insight into the end effectOKUNO, Hiroshi; SAKAI, Tomohiro.Nuclear technology. 2002, Vol 140, Num 3, pp 255-265, issn 0029-5450, 11 p.Article

Application of candle burnup strategy for future nuclear energy utilizationSEKIMOTO, Hiroshi.Progress in nuclear energy (New series). 2005, Vol 47, Num 1-4, pp 91-98, issn 0149-1970, 8 p.Conference Paper

Burnup determination of high burnup and dry processed fuels based on isotope dilution mass spectrometric measurementsKIM, Jung Suk; JEON, Young Shin; PARK, Soon Dal et al.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 7, pp 1015-1023, issn 0022-3131, 9 p.Article

Numerical solution of stiff burnup equation with short half lived nuclides by the Krylov subspace methodYAMAMOTO, Akio; TATSUMI, Masahiro; SUGIMURA, Naoki et al.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 2, pp 147-154, issn 0022-3131, 8 p.Article

Liquidus temperature of irradiated mixed oxide fuels for fast reactorsKONNO, Koichi.Journal of Nuclear Science and Technology. 2002, Vol 39, Num 12, pp 1299-1302, issn 0022-3131, 4 p.Article

Effects of fuel and coolant temperatures and neutron fluence on CANDLE burnup calculationSEKIMOTO, Hiroshi; UDAGAWA, Yutaka.Journal of Nuclear Science and Technology. 2006, Vol 43, Num 2, pp 189-197, issn 0022-3131, 9 p.Article

Effect of neutron induced reactions of neodymium-147 and 148 on burnup evaluationSUYAMA, Kenya; MOCHIZUKI, Hiroki.Journal of Nuclear Science and Technology. 2005, Vol 42, Num 7, pp 661-669, issn 0022-3131, 9 p.Article

How the Sine-Cordon equation enters reactor physicsSEIFRITZ, Walter.Kerntechnik (1987). 2006, Vol 71, Num 4, pp 238-239, issn 0932-3902, 2 p.Article

Hydrogen and helium shell flashes on massive accreting white dwarfsJOSE, J; HERNANZ, M; ISERN, J et al.Astronomy and astrophysics (Berlin. Print). 1993, Vol 269, Num 1-2, pp 291-300, issn 0004-6361Article

Development of a fusion and fission power system based on direct-action microtargets and a high-power heavy-ion driverALEKSEEV, N. N; BASKO, M. M; MASLENNIKOV, M. V et al.Atomic energy (New York, N.Y.). 2004, Vol 97, Num 3, pp 632-640, issn 1063-4258, 9 p.Article

A tritium catalytic fusion reactor conceptMARTINEZ-VAL, J. M; ELIEZER, S; HENIS, Z et al.Nuclear fusion. 1998, Vol 38, Num 11, pp 1651-1664, issn 0029-5515Article

Quantitative accuracy analysis of burnup calculations for BNPP fuel assemblies using FFTBM methodHADAD, Kamal; AYOBIAN, Navid; PIROOZMAND, Ahmad et al.Progress in nuclear energy (New series). 2009, Vol 51, Num 1, pp 170-176, issn 0149-1970, 7 p.Article

Liquid chromatographic determination of the number of fissions in uranium/aluminium nuclear fuelsCASSIDY, R. M; ELCHUK, S; GREEN, L. W et al.Journal of radioanalytical and nuclear chemistry. 1990, Vol 139, Num 1, pp 55-64, issn 0236-5731, 10 p.Article

Avantages et inconvénients pour le cycle de l'accroissement du taux de combustion (Paris, 16 janvier 2002)Avantages et inconvénients pour le cycle de l'accroissement du taux de combustion . Journée. 2002, 145 p.Conference Proceedings

Feasibility studies on iterative methods of fuel burnup estimation using gamma-ray spectrometryTIEN-KO WANG; DE-CHIUN HSU; CHIA-LIAN TSENG et al.Applied radiation and isotopes. 1990, Vol 41, Num 1, pp 41-47, issn 0969-8043, 7 p.Article

Optimum in-core power sharing with multicycle coupling effectYAMAMOTO, Akio; IWATA, Tomoki; YAMANE, Yoshihiro et al.Progress in nuclear energy (New series). 2011, Vol 53, Num 6, pp 593-599, issn 0149-1970, 7 p.Conference Paper

Optimum discharge burnup and cycle length for PWRsSECKER, Jeffrey R; JOHANSEN, Baard J; STUCKER, David L et al.Nuclear technology. 2005, Vol 151, Num 2, pp 109-119, issn 0029-5450, 11 p.Conference Paper

CONSERVATIVE WIDTH OF HIGH-BURNUP STRUCTURE IN LIGHT WATER REACTOR UO2 FUEL AS A FUNCTION OF PELLET AVERAGE BURNUPKOO, Yang-Hyun; LEE, Byung-Ho; OH, Jae-Yong et al.Nuclear technology. 2008, Vol 164, Num 3, pp 337-347, issn 0029-5450, 11 p.Article

Effect of highly enriched/highly burnt UO2 fuels on fuel cycle costs, radiotoxicity, and nuclear design parametersGREGG, Robert; WORRALL, Andrew.Nuclear technology. 2005, Vol 151, Num 2, pp 126-132, issn 0029-5450, 7 p.Conference Paper

Simulation study on candle burnup applied to block-type high temperature gas cooled reactorOHOKA, Yasunori; WATANABE, Takashi; SEKIMOTO, Hiroshi et al.Progress in nuclear energy (New series). 2005, Vol 47, Num 1-4, pp 292-299, issn 0149-1970, 8 p.Conference Paper

Development of fission source acceleration method for slow convergence in criticality analyses by using matrix eigenvector applicable to spent fuel transport cask with axial burnup profileKUROISHI, Takeshi; NOMURA, Yasushi.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 6, pp 433-440, issn 0022-3131, 8 p.Article

Neutronic performance comparation of MOX, nitride and metallic fuel based 25-100 MWe Pb-Bi cooled long life fast reactors without on-site refuellingSU'UD, Zaki.Progress in nuclear energy (New series). 2008, Vol 50, Num 2-6, pp 276-278, issn 0149-1970, 3 p.Conference Paper

Principles, design and fuel performance characteristics of gas cooled thermal reactorsBOOCOCK, P. M; EATON, J. R. P.Nuclear energy (1978). 1989, Vol 28, Num 1, pp 29-34, issn 0140-4067, 6 p.Article

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