Comparison of ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF 3.3 Nuclear Data Libraries on Criticality Calculation Using WIMS/CITVAP Code

Mohamed Elsaied, Ahmed Ali, Nader Abdelhaleem
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Abstract

This paper presents the work carried out during the first year of the research contract No. 24284 titled “accuracy evaluation of available fission yield data and updating” under the umbrella of the Coordinated Research Project (CRP): “updating fission yield data for applications” organized by the International Atomic Energy Agency (IAEA) with the main objective of updating the evaluated independent and cumulative fission yield data for U-235, U-238, and Cf-252. In this research, the latest ENDF/B-VIII.0 and JEFF3.3 data libraries that were released in 2018 and 2017, respectively, as well as the ENDF/B-VII.1 data library, were tested on the ETRR-2 using WIMS-5B/CITVAP computational codes. Since the reactor criticality calculations are very sensitive to the accuracy of the data libraries, criticality benchmarks were selected in the work for the evaluation of these libraries. The results showed that the JEFF3.3 library has better agreement with the measurements than the ENDF/B-VIII.0 library. But the ENDF/B-VIII.0 library result is within the accepted range.
ENDF/B-VII.1、ENDF/B-VIII.0 和 JEFF 3.3 核数据库在使用 WIMS/CITVAP 代码进行临界计算方面的比较
本文介绍了在国际原子能机构(IAEA)组织的协调研究项目(CRP)"更新应用裂变当量数据 "框架下,题为 "现有裂变当量数据的准确性评估和更新 "的第24284号研究合同第一年开展的工作,主要目标是更新已评估的铀235、铀238和锎252的独立和累积裂变当量数据。在这项研究中,使用 WIMS-5B/CITVAP 计算代码在 ETRR-2 上测试了分别于 2018 年和 2017 年发布的最新 ENDF/B-VIII.0 和 JEFF3.3 数据库,以及 ENDF/B-VII.1 数据库。由于反应堆临界计算对数据文库的准确性非常敏感,工作中选择了临界基准对这些文库进行评估。结果表明,与ENDF/B-VIII.0库相比,JEFF3.3库与测量结果的一致性更好。但ENDF/B-VIII.0库的结果在可接受范围内。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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