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Verification of CENDL-3.2 Nuclear Data on VENUS-3 Shielding Benchmark by ARES Transport Code
Science and Technology of Nuclear Installations ( IF 1.1 ) Pub Date : 2021-02-05 , DOI: 10.1155/2021/6633366 Jiaju Hu 1 , Bin Zhang 1 , Zhiwei Zong 1 , Cong Liu 1 , Yixue Chen 1
Science and Technology of Nuclear Installations ( IF 1.1 ) Pub Date : 2021-02-05 , DOI: 10.1155/2021/6633366 Jiaju Hu 1 , Bin Zhang 1 , Zhiwei Zong 1 , Cong Liu 1 , Yixue Chen 1
Affiliation
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.
更新日期：2021-02-05
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