Validation of neutron current formulations for the response matrix method based on the SP3 theory-Reference-Cited by-同舟云学术

Validation of neutron current formulations for the response matrix method based on the SP3 theory

Published:2010-01 Issue:1 Volume:37 Page:22-27
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Tada Kenichi,Yamamoto Akio,Yamane Yoshihiro,Kosaka Shinya,Hirano Gou

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. Asymptotic derivation of the multigroup P1 and simplified PN equations with anisotropic scattering;Larsen;Nucl. Sci. Eng.,1996

2. Computational methods of neutron transport;Lewis,1984

3. Okuno, H., Naito, Y., Sayama, K., 2002. OECD/NEA burnup credit criticality benchmarks phase IIIB: burnup calculations of BWR fuel assemblies for storage and transport. JAERI-Research 2002-001. p. 68.

4. Accuracy comparisons for variational R, T and T−1 response matrix formulations;Olvey;Ann. Nucl. Energy,1987

5. Applicability of the diffusion and simplified P3 theories for pin-by-pin geometry of BWR;Tada;J. Nucl. Sci. Technol.,2008

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Hybrid finite-element-based numerical solution of the multi-group SP3 equations and its application on hexagonal reactor problems;Annals of Nuclear Energy;2021-06

2. Semi-analytical methods for SP3 equations solver verification including third-order scattering anisotropy;Annals of Nuclear Energy;2020-12

3. Preconditioned Krylov Solution of Response Matrix Equations;Nuclear Science and Engineering;2013-03

4. A boundary element–response matrix method for the multigroup criticality problems in the SP3 approximation;Annals of Nuclear Energy;2012-04