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
• 来源期刊: 核技术（英文版）
• 年，卷（期）: 2022,（1）
• 所属期刊栏目: NUCLEAR ENERGY SCIENCE AND ENGINEERING
• 页码范围: 81-97
• 页数: 17页
• 语种: 英文

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 compre-hensively evaluate the criticality computing performance of these newly released evaluated nuclear libraries.In this study,we used the NJOY2016 code to generate ACE for-mat libraries based on the latest neutron data libraries(including CENDL-3.2,JEFF3.3,ENDF/B-IⅧ.0,and JENDL4.0).The MCNP code was used to conduct a detailed analysis of fission nuclides,including 235U,233U,and 239pu,in different evaluated nuclear data libraries based on 100 benchmarks.The criticality calculation per-formance of each library was evaluated using three statis-tical parameters:δk/σ,x2,and <|Δ|>.Analysis of the δk/σ parameter showed that CENDL-3.1 and JENDL-4.0 both had ＞ 10 benchmarks that exceeded 3σr,whereas CENDL-3.2,ENDFB-Ⅷ.0,and JEFF-3.3 had,7,5,and 4 bench-marks,respectively,exceeding 3σ.The ENDF/B-Ⅶ.1 library performed best,with only two benchmarks exceeding 3σ.Compared to CENDL-3.1,CENDL-3.2 offers an improvement in criticality calculations.Com-pared to the JEFF-3.3 and ENDF/B-Ⅷ.0 libraries,CENDL3.2 performs better in the calculation of the 233U assemblies,but it performs poorly in the pusl11 series case calculation of the 239pu assemblies,and thus further improvement is needed.