Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method
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- 作者：Grzegorz Kępisty ; gkepisty@agh.edu.pl" class="auth_mail" title="E-mail the corresponding author ; Jerzy Cetnar ; Przemysław Stanisz
- 关键词：BOL ; beginning-of-life ; BWR ; Boiling Water Reactor ; CFD ; Computational Fluid Dynamics ; CRAM ; Chebyshew Rational Approximation Method ; ENDF ; Evaluated Nuclear Data File ; EOL ; end-of-life ; FA ; fuel assembly ; FIMA ; Fissions per Initial Metal Atom ; HTR ; High Temperature Reactor ; JEFF ; Joint Evaluated Fission and Fusion File ; JENDL ; Japanese Evaluated Nuclear Data Library ; LWR ; Light Water Reactor ; MC ; Monte Carlo ; PWR ; Pressurized Water Reactor ; RKG ; Runge&ndash ; Kutta method of Gauss type ; TTA ; Tran
- 刊名：Annals of Nuclear Energy
- 出版年：2016
- 出版时间：August 2016
- 年：2016
- 卷：94
- 期：Complete
- 页码：189-207
- 全文大小：2650 K
文摘
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The parametric study with Monte-Carlo burnup code MCB5 is performed.
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The impact of modeling factors on fuel assembly depletion is determined.
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Discrepancies of kinf, nuclides concentrations and conversion ratio are detected.
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Assumptions and simplifications of reactor modeling are discussed.
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Clear comparison of different factors is given on the basis of the results.