Neutronic and burnup analysis of OECD-NEA MOX fuel benchmark with Dragon5 lattice code

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes Pub Date : 2025-01-04 DOI:10.1016/j.apradiso.2025.111661

Zelong Zhao, Yaping Guo, Gu Hu

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引用次数: 0

Abstract

This paper presents a comprehensive and detailed analysis of the OECD-NEA MOX fuel benchmark based on different nuclear data libraries to investigate the reliability and accuracy of the Dragon5 lattice code developed by École Polytechnique de Montréal for the neutronic analysis of mixed uranium-plutonium oxide (MOX) fuel. The neutronics and burn-up calculations for rectangular pin and assembly geometries filled with different compositions of MOX fuel are computed. The performance of different nuclear data libraries is evaluated. Parameters such as infinite multiplication factor, reactivity change agree very well with the averaged reference values provided by the other institutions when the JEF2.2 library is used. Inventories of major actinides and fission product nuclides at different burn-up depths are also compared with published values at the MOX pin cell and assembly level, results of the Dragon5 lattice code are in agreement with averaged values provided by other codes. Furthermore, the deviation between newer libraries and reference solutions of the benchmark should be attributed to the differences in neutron data. Therefore, the Dragon5 lattice code is reliable for neutronics and burn-up analysis of MOX fuel and can be applied to the neutronic analysis of mixed uranium-plutonium oxide fuel.

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用Dragon5晶格代码对OECD-NEA MOX燃料基准进行中子和燃耗分析。

本文基于不同的核数据库，对OECD-NEA MOX燃料基准进行了全面和详细的分析，以研究École Polytechnique de montracei开发的用于混合铀-钚氧化物（MOX）燃料中子分析的Dragon5晶格代码的可靠性和准确性。计算了填充不同成分MOX燃料的矩形引脚和装配几何形状的中子子学和燃耗计算。对不同核数据库的性能进行了评价。当使用JEF2.2库时，无限乘法因子、反应性变化等参数与其他机构提供的平均参考值非常吻合。在不同燃烧深度下，主要锕系元素和裂变产物核素的库存也与MOX引脚细胞和组装水平的公布值进行了比较，Dragon5晶格代码的结果与其他代码提供的平均值一致。此外，新库和基准参考解决方案之间的偏差应归因于中子数据的差异。因此，Dragon5晶格码对MOX燃料的中子分析和燃耗分析是可靠的，可以应用于铀-钚氧化物混合燃料的中子分析。

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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来源期刊

Applied Radiation and Isotopes 工程技术-核科学技术

CiteScore

3.00

自引率

12.50%

发文量

406

审稿时长

13.5 months

期刊介绍： Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.