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This article is cited in 8 scientific papers (total in 8 papers)
Low-cost calculation of multigroup neutron transport equations for time-to-time recalculation of averaged over spectrum cross-sections
E. N. Aristova, V. Ya. Gol'din Institute for Mathematical Modelling, Russian Academy of Sciences
Abstract:
Methodology for multigroup neutron transport equation calculation for 2D r-z geometry on the basis of quasi-diffusion method is described. The application of quasi-diffusion method for solving eigenvalues problem of neutron transport leads to essential decreasing of needed amount of source iterations with simultaneous increasing of the accuracy. Results for determining of parameters of active zone of uranium-plutonium fast reactor of BN-800 type which can operate in self-adjustable mode are posted.
Received: 23.10.2006
Citation:
E. N. Aristova, V. Ya. Gol'din, “Low-cost calculation of multigroup neutron transport equations for time-to-time recalculation of averaged over spectrum cross-sections”, Matem. Mod., 20:11 (2008), 41–54; Math. Models Comput. Simul., 1:5 (2009), 561–572
Linking options:
https://www.mathnet.ru/eng/mm2703 https://www.mathnet.ru/eng/mm/v20/i11/p41
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Abstract page: | 585 | Full-text PDF : | 236 | References: | 69 | First page: | 21 |
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