Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark-Reference-Cited by-同舟云学术

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Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark

Published:2023-12 Issue: Volume:194 Page:110092
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Clarno Kevin T.^ORCID,Barlow John E.^ORCID,Sawyer Tucker,Scherr Jonathan,Hearne Jason,Tsvetkov Pavel^ORCID

Funder

Texas A and M University

University of Texas at Austin

Oak Ridge National Laboratory

University of California Berkeley

Abilene Christian University

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Abilene Christian University Molten Salt Research Reactor Preliminary Safety Analysis Report,2022

2. Validation of SCALE for molten salt reactors using the MSRE benchmark;Barlow;Trans. Am. Nucl. Soc.,2020

3. Modeling of the molten salt reactor experiment with SCALE;Bostelmann;Nucl. Technol.,2022

4. SCALE 6: Comprehensive nuclear safety analysis code system;Bowman;Nucl. Technol.,2011

5. Fission Product Behavior in the Molten Salt Reactor Experiment;Compere,1975

Cited by 3 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. Assessing the benefit of thorium fuel in a once through molten salt reactor;Progress in Nuclear Energy;2024-11

2. CAD and constructive solid geometry modeling of the Molten Salt Reactor Experiment with OpenMC;Frontiers in Nuclear Engineering;2024-05-09

3. Comparative Assessment of Molten Salt Reactor Neutronic Performance with Various U-233 Purity;Engineering Journal;2024-05

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