Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations  

作　　者：Bin Zhang Xu-Bo Ma Kui Hu Teng Zhang Xuan Ma Yi-Xue Chen 

机构地区：[1]School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China

出　　处：《Nuclear Science and Techniques》2022年第1期81-97,共17页核技术（英文）

基　　金：supported by the National Natural Science Foundation of China(No.11875128).

摘　　要：Nuclear data are the cornerstones of reactor physics and shielding calculations.Recently,China released CENDL-3.2 in 2020,and the US released ENDF/B-VIII.0 in 2018.Therefore,it is necessary to comprehensively evaluate the criticality computing performance of these newly released evaluated nuclear libraries.In this study,we used the NJOY2016 code to generate ACE format libraries based on the latest neutron data libraries(including CENDL-3.2,JEFF3.3,ENDF/B-VIII.0,and JENDL4.0).The MCNP code was used to conduct a detailed analysis of fission nuclides,including^(235)U,^(233)U,and^(239)Pu,in different evaluated nuclear data libraries based on 100 benchmarks.The criticality calculation performance of each library was evaluated using three statistical parameters:δk/σ,χ^(2),and<|Δ|>.Analysis of theδk/σparameter showed that CENDL-3.1 and JENDL-4.0 both had>10 benchmarks that exceeded 3r,whereas CENDL3.2,ENDFB-VIII.0,and JEFF-3.3 had,7,5,and 4 benchmarks,respectively,exceeding 3r.The ENDF/B-VII.1 library performed best,with only two benchmarks exceeding 3r.Compared to CENDL-3.1,CENDL-3.2 offers an improvement in criticality calculations.Compared to the JEFF-3.3 and ENDF/B-VIII.0 libraries,CENDL3.2 performs better in the calculation of the^(233)U assemblies,but it performs poorly in the pusl11 series case calculation of the^(239)Pu assemblies,and thus further improvement is needed.

关 键 词：Criticality calculations CENDL-3.2 ENDF/B-VIII.0 Neutron ACE library 

分 类 号：TL32[核科学技术—核技术及应用]