RELAP/MOD3 code manual: User`s guidelines. Volume 5, Revision 1
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Cited by 34 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. Neutronic and thermal-hydraulic assessment of the TRR with new core designed based on tubular fuels;Kerntechnik;2023-11-09
2. Transient characteristics of typical design basis accidents in integrated small reactor NHR200-II using RELAP5 model;Annals of Nuclear Energy;2023-11
3. Streamlined best estimate plus uncertainty analysis of a GEN III + BWR for a bottom drain line small break LOCA;Annals of Nuclear Energy;2023-04
4. Loss of flow accident analysis in Atucha II nuclear power plant using RELAP5 model;Nuclear Engineering and Design;2023-02
5. Investigation of a Steam Line Break Accident in Respect of the Critical Safety Function “Subcriticality”;CR ACAD BULG SCI;2020-10-28
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