使用ENDF/B-VIII.0库的ν-TRAC对MOX燃料VVER-1000针形电池进行研究

Q2 Physics and Astronomy Physics Open Pub Date : 2024-04-03 DOI:10.1016/j.physo.2024.100212

Anmol Singh , Usha Pal , R. Karthikeyan , V. Harikrishnan

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引用次数: 0

摘要

本文使用ν-TRAC 代码对用于 MOX 燃料 VVER-1000 针形电池基准的ENDF/B-VIII.0 库与ENDF/B-VII.0 库进行了比较，并展示了该代码的建模能力。ν-TRAC 是一种基于 MOC 的代码，用于模拟燃料组件晶格中的中子输运，具有电池异质性建模能力。材料截面对中子输运计算有重大影响；因此，使用最新版本的 ENDF/B-VIII.0 和开源 NJOY-2016 代码生成了 172 多组截面库。该核数据文件包括对主要锕系元素和其他轻核素截面的修改。使用最新的库，研究了燃料同位素组成不同的五种 MOX 燃料变体，以及燃料温度、慢化剂和慢化剂中毒物不同的五种状态。研究了新释放对无限倍增因子的影响以及不同运行状态引起的反应性变化。使用基于ENDF/B-VIII.0和ENDF/B-VII.0的多组数据库的ν-TRAC代码结果与SCALE/SAS2H、HELIOS和MCU的相应结果进行了比较。

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Study of MOX-fueled VVER-1000 pin cell using ν-TRAC with ENDF/B-VIII.0 library

This paper compares the ENDF/B-VIII.0 library for the MOX-fueled VVER-1000 pin cell benchmark with ENDF/B-VII.0 library using the $ν$ -TRAC code and demonstrates the modeling capability of the code. $ν$ -TRAC is a MOC-based code for simulating neutron transport in fuel assembly lattices, with the ability to model cell heterogeneities. The material cross-section significantly impacts neutron transport calculations; therefore, a 172 multigroup cross-section library has been generated using the most recent version of ENDF/B-VIII.0 and the open-source NJOY-2016 code. This nuclear data file includes modifications to the cross-section of major actinides and other light nuclides. Five MOX fuel variants differing in fuel isotopic composition and five states differing in fuel temperature, the moderator, and poison in the moderator are investigated using the most recent library. The impact of new release on the infinite multiplication factor and reactivity change due to the different operating states is studied. Results of $ν$ -TRAC code using multigroup data libraries based on ENDF/B-VIII.0 and ENDF/B-VII.0 are compared with corresponding results from SCALE/SAS2H, HELIOS, and MCU.

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