Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code
The recently released CENDL-3.2 nuclear data library is deemed as an important achievement in the field of nuclear data research in China. To verify the applicability of the library to the shielding calculation of PWR and analyze the influence of multigroup cross-section parameters on the shielding...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2021-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2021/6633366 |
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| author | Jiaju Hu Bin Zhang Zhiwei Zong Cong Liu Yixue Chen |
| author_facet | Jiaju Hu Bin Zhang Zhiwei Zong Cong Liu Yixue Chen |
| author_sort | Jiaju Hu |
| collection | DOAJ |
| description | The recently released CENDL-3.2 nuclear data library is deemed as an important achievement in the field of nuclear data research in China. To verify the applicability of the library to the shielding calculation of PWR and analyze the influence of multigroup cross-section parameters on the shielding calculation, ARES-MACXS module is used to process the MATXS format multigroup library based on CENDL-3.2 to generate multigroup working cross sections for PWR shielding calculation. VENUS-3 experimental facility has a clear and complete geometry. It is often used to test the ability of the advanced transport calculation method of calculating RPV fast neutron flux and to evaluate the accuracy of cross-section library. Different cross-section parameters are chosen for ARES to calculate VENUS-3 benchmark, and equivalent neutron flux of 58Ni(n,p)58Co, 115In(n,n′)115mIn and 27Al(n,α)24Na detectors is calculated according to the data provided by the benchmark report. The numerical results demonstrate that almost all the relative deviations between the calculated results and the experimental results are within 20%, which satisfies the requirement of shielding calculation. CENDL-3.2 is suitable for PWR shielding calculation. The comparison of various cross-section parameters results indicates that multigroup cross-section parameters have large effects on the transport calculation results. |
| format | Article |
| id | doaj-art-eb3e9460378f41f28860682523f833da |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2021-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-eb3e9460378f41f28860682523f833da2025-02-03T05:49:26ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832021-01-01202110.1155/2021/66333666633366Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport CodeJiaju Hu0Bin Zhang1Zhiwei Zong2Cong Liu3Yixue Chen4School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaSchool of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, ChinaThe recently released CENDL-3.2 nuclear data library is deemed as an important achievement in the field of nuclear data research in China. To verify the applicability of the library to the shielding calculation of PWR and analyze the influence of multigroup cross-section parameters on the shielding calculation, ARES-MACXS module is used to process the MATXS format multigroup library based on CENDL-3.2 to generate multigroup working cross sections for PWR shielding calculation. VENUS-3 experimental facility has a clear and complete geometry. It is often used to test the ability of the advanced transport calculation method of calculating RPV fast neutron flux and to evaluate the accuracy of cross-section library. Different cross-section parameters are chosen for ARES to calculate VENUS-3 benchmark, and equivalent neutron flux of 58Ni(n,p)58Co, 115In(n,n′)115mIn and 27Al(n,α)24Na detectors is calculated according to the data provided by the benchmark report. The numerical results demonstrate that almost all the relative deviations between the calculated results and the experimental results are within 20%, which satisfies the requirement of shielding calculation. CENDL-3.2 is suitable for PWR shielding calculation. The comparison of various cross-section parameters results indicates that multigroup cross-section parameters have large effects on the transport calculation results.http://dx.doi.org/10.1155/2021/6633366 |
| spellingShingle | Jiaju Hu Bin Zhang Zhiwei Zong Cong Liu Yixue Chen Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code Science and Technology of Nuclear Installations |
| title | Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code |
| title_full | Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code |
| title_fullStr | Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code |
| title_full_unstemmed | Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code |
| title_short | Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code |
| title_sort | verification of cendl 3 2 nuclear data on venus 3 shielding benchmark by ares transport code |
| url | http://dx.doi.org/10.1155/2021/6633366 |
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