Development and verification of the transient fission matrix combination method for the efficient neutron kinetic simulations-Reference-Cited by-同舟云学术

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Development and verification of the transient fission matrix combination method for the efficient neutron kinetic simulations

Published:2024-08 Issue: Volume:173 Page:105265
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Li Yuehang^ORCID,He Donghao,Pan Qingquan,Liu Xiaojing

Funder

National Natural Science Foundation of China

Science and Technology Commission of Shanghai Municipality

Publisher

Elsevier BV

Reference25 articles.

1. MCNP version 5;Brown;Trans. Am. Nucl. Soc.,2002

2. Transient capability for a MOC-based whole core transport code DeCART;Cho;Trans. Am. Nucl. Soc.,2005

3. Generalized quasi-static method for nuclear reactor space-time kinetics;Devooght;Nucl. Sci. Eng.,1980

4. Discrete-ordinates solutions of the radiative transport equation for rectangular enclosures;Fiveland,1984

5. A local fission matrix correction method for heterogeneous whole core transport with RAPID;He;Ann. Nucl. Energy,2019

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