| Autor: |
WU Jun, LIU Shichang, CHEN Yixue |
| Jazyk: |
čínština |
| Rok vydání: |
2022 |
| Předmět: |
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| Zdroj: |
He jishu, Vol 45, Iss 6, Pp 060601-060601 (2022) |
| Druh dokumentu: |
article |
| ISSN: |
0253-3219 |
| DOI: |
10.11889/j.0253-3219.2022.hjs.45.060601&lang=zh |
| Popis: |
BackgroundCENDL-3.2 was released in June 2020. Compared with CENDL-3.1, data type and quality has been greatly improved in CENDL-3.2,and most important isotopes including 235U, 238U, 239Pu, 56Fe and others have been re-evaluated and supplemented. Due to its large scattering cross section and small absorption cross section, Be is often used as one of the fuel carrier salt components of molten salt reactor (MSR). The accuracy of reaction cross section data of Be in MSR design cannot be ignored.PurposeThis study aims to examine and analyze the adaptability of the cross section data of Be in CENDL-3.2 to the calculation of MSR problems by the discrete-ordinate method.MethodsBased on CENDL-3.2,the MATXS format multi-group cross section library of 199 neutron groups and 42 photon groups was generated by NJOY, and 35 fast critical benchmarks were selected for its inspection and analysis. Then, results were compared with those of multi-group cross section library based on ENDF/B-7.1 and JENDL-4.0.ResultsThe deviation between the calculated results of the multi-group cross section library based on CENDL-3.2 and the experimental values is less than 0.5% in 26 benchmark cases which is 74.29% of total, outperform those of ENDF/B-7.1 and JENDL-4.0.ConclusionsThe results of this study indicate that the data of Be and the multi-group cross section library based on CENDL-3.2 and its processing method are reliable and can be used in the design of molten salt reactor. |
| Databáze: |
Directory of Open Access Journals |
| Externí odkaz: |
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