Development of RAPID transport calculation with heterogeneous temperature distribution-Reference-Cited by-同舟云学术

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Development of RAPID transport calculation with heterogeneous temperature distribution

Published:2020-12 Issue: Volume:148 Page:107685
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

He Donghao^ORCID,Walters William J.^ORCID

Funder

NRC Faculty Development

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference30 articles.

1. Criticality calculations by monte carlo methods, Tech. rep.;Morton,1956

2. Monte Carlo methods for equilibrium solutions in neutron multiplication;Kaplan,1958

3. Monte carlo criticality calculations for thermal reactors;Mendelson;Nucl. Sci. Eng.,1968

4. Source convergence in monte carlo calculations;Carter;Nucl. Sci. Eng.,1969

5. Iterative acceleration methods for monte carlo and deterministic criticality calculations, Tech. rep;Urbatsch,1995

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3. A Novel Hybrid Deterministic and Monte Carlo Neutron Transport Formulation and Algorithm (tRAPID) for Accurate and Fast 3-D Reactor Kinetics;Nuclear Science and Engineering;2023-05-26

4. The development of the combined fission matrix method in small advanced reactor design and optimization;Annals of Nuclear Energy;2023-01

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