Abstract
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.
Highlights
With the rapid development of computer science and technology and improved understanding of transport calculation theory, the discrete ordinates method (SN) becomes one of the most efficient and common tools for radiation shielding calculations, especially for neutron shielding calculations [1]
To verify the applicability of the Chinese Evaluated Nuclear Data Library (CENDL)-3.2 nuclear data library for PWR shielding calculation, VENUS-3 shielding benchmark is calculated by ARES with a detailed 3-D model. 199 neutron group structure multigroup cross-section library based on CENDL-3.2 is generated by NJOY
Multigroup cross-section library is processed using the ARES-MACXS module to generate multigroup working cross sections. e calculation results are compared with ENDF/B VII.0 nuclear data library results. e numerical results show that the equivalent fission flux rations satisfy the requirement of engineering shielding calculation
Summary
With the rapid development of computer science and technology and improved understanding of transport calculation theory, the discrete ordinates method (SN) becomes one of the most efficient and common tools for radiation shielding calculations, especially for neutron shielding calculations [1]. As a part of deterministic computation, the accuracy of the multigroup cross-section library becomes more and more important to improve the accuracy of transport calculation results. E latest version of the Chinese Evaluated Nuclear Data Library, CENDL3.2, was released on June 12, 2020. To verify the applicability of the evaluated nuclear data library for VENUS-3 international benchmark [3,4,5], NJOY [6] was used to generate 199 groups MATXS-format multigroup library based on CENDL-3.2. In order to analyze the influence of multigroup cross section on VENUS-3 benchmark, the calculation results of various cross-section parameters are compared. Science and Technology of Nuclear Installations compares the multigroup calculation results based on CENDL-3.2 with experimental results.
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