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This article is cited in 12 scientific papers (total in 12 papers)
Quasidiffusion method realization for fast reactor critical parameters calculation in 3D hexagonal geometry
E. N. Aristovaab, D. F. Baydinb a Keldysh Institute of Applied Mathematics RAS
b Moscow Institute for Physics and Technology
Abstract:
Strategy for multigroup neutron transport equation calculation on the basis of quasi-diffusion
method, aimed at finding critical parameters of fast reactors, capable to operate in self-adjustable
mode, is described. The numerical method is based on Gol’din’s quasi-diffusion method for multigroup neutron transport equation solving. Approximation for all types of high and low orders
equations are suggested. The method of high order transport equation solving is based on developed earlier conservative method. Application of quasi-diffusion method for solving eigenvalues
problem of neutron transport leads to essential decreasing of required number of source iterations
with simultaneous increasing of the accuracy. Computations of parameters of active zone of uranium-plutonium fast reactor of BN-800 type are carried out for 3D $x-y-z$ hexagonal geometry, reflecting structure of the reactor active zone.
Keywords:
transport equation, quasi-diffusion method, self-adjustable neutron-nuclear regime, R-eigenvalue problem, iteration method.
Received: 26.09.2011
Citation:
E. N. Aristova, D. F. Baydin, “Quasidiffusion method realization for fast reactor critical parameters calculation in 3D hexagonal geometry”, Matem. Mod., 24:8 (2012), 65–80; Math. Models Comput. Simul., 5:2 (2013), 145–155
Linking options:
https://www.mathnet.ru/eng/mm3301 https://www.mathnet.ru/eng/mm/v24/i8/p65
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Abstract page: | 326 | Full-text PDF : | 109 | References: | 47 | First page: | 8 |
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