Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests-Reference-Cited by-同舟云学术

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Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

Published:2022-10 Issue:10 Volume:54 Page:3897-3908
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Guo Hui^ORCID,Huo Xingkai,Feng Kuaiyuan^ORCID,Gu Hanyang

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference15 articles.

1. Fast Reactor Database 2006 Update (No. IAEA-TECDOC-1531),2006

2. 4 - gas-cooled fast reactors;Tsvetkov,2016

3. 6 - lead-cooled fast reactor;Smith,2016

4. Safety assessment of the molten salt fast reactor (SAMOFAR);Kloosterman,2017

5. Technical Specifications for Neutronics Benchmark of CEFR Start-Up Tests (No. IAEA CRP-I31032);Huo,2019

Cited by 6 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. OpenMC interpretation and analysis of two series highly-enriched-uranium thermal-spectrum benchmarks for nuclear data validation;Annals of Nuclear Energy;2023-11

2. Core design and neutronic analysis of a long-life LBE-cooled fast reactor NCLFR-Oil;Progress in Nuclear Energy;2023-10

3. Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system;Nuclear Engineering and Technology;2023-07

4. Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark;Progress in Nuclear Energy;2022-12

5. Investigation of the Effect of Rod Worth Uncertainty on the Reactivity Measurements of CEFR Start-Up Tests via McCARD Monte Carlo Calculations;Energies;2022-11-04

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