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

Bin Zhang; Xu-Bo Ma; Kui Hu; Teng Zhang; Xuan Ma; Yi-Xue Chen

doi:10.1007/s41365-022-00994-3

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

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2022-02-17

- Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations
- Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations
- Nuclear Science and Techniques 2022年33卷第1期文章编号：8
- Affiliations：
  
  1.School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
- Author bio：
  
  E-mail address: maxb@ncepu.edu.cn
- Funds：
  
  National Natural Science Foundation of China(11875128)
- DOI：10.1007/s41365-022-00994-3
  中图分类号：
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Bin Zhang, Xu-Bo Ma, Kui Hu, 等. Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations[J]. Nuclear Science and Techniques, 2022,33(1):8

Bin Zhang, Xu-Bo Ma, Kui Hu, et al. Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations[J]. Nuclear Science and Techniques, 2022,33(1):8
Bin Zhang, Xu-Bo Ma, Kui Hu, 等. Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations[J]. Nuclear Science and Techniques, 2022,33(1):8 DOI： 10.1007/s41365-022-00994-3.

Bin Zhang, Xu-Bo Ma, Kui Hu, et al. Performance of the CENDL-3.2 and other major neutron data libraries for criticality calculations[J]. Nuclear Science and Techniques, 2022,33(1):8 DOI： 10.1007/s41365-022-00994-3.

摘要

Abstract

Nuclear data are the cornerstones of reactor physics and shielding calculations. Recently, China released CENDL-3.2 in 2020, and the United States 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: , $δ k / σ$ , $χ^{2}$ , and , $〈 | Δ | 〉$ ,. Analysis of the , $δ k / σ$ , parameter showed that CENDL-3.1 and JENDL-4.0 both had ,>,10 benchmarks that exceeded 3σ, whereas CENDL-3.2, ENDFB-VIII.0, and JEFF-3.3 had, 7, 5, and 4 benchmarks, respectively, exceeding 3σ. The ENDF/B-VII.1 library performed best, with only two benchmarks exceeding 3σ. Compared with CENDL-3.1, CENDL-3.2 offers an improvement in criticality calculations. Compared with 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

Keywords

Criticality calculationsCENDL-3.2ENDF/B-VIII.0NeutronACE library

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