Software-Based automation of burnup calculations for the NUR research reactor using SCALE/TRITON T6-DEPL sequence

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-23 DOI:10.1016/j.anucene.2024.111007

Djahid Lababsa , Hakim Mazrou , Mohamed Belgaid , Tahar Zidi , Mohammed Azzoune , Azzeddine Ameur , Ahmed Guesmia , Leila Zamoun , Mohamed Boufenar

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Abstract

This work represents a key milestone in the development of a Monte Carlo Burnup Calculation System (MCBCS) specially tailored for the NUR research reactor. Developed using Python and leveraging the 3D Monte Carlo TRITON depletion sequence (T6-DEPL) within the SCALE code, MCBCS accurately simulates the reactor’s operating history. The paper provides an overview of MCBCS, focusing on its components, verification, and validation.

The verification and validation process cover both fresh and burnt core conditions. For the fresh core, comparisons of excess reactivity, control rods worth, and critical configurations against experimental data and MCNP5 calculations showed good agreement. Burnup calculations were validated against measured core excess reactivity, reactivity worths of fuel assemblies, and neutron flux distribution. The system slightly underpredicted core excess reactivity by −2.95%, and discrepancies in reactivity worths remained within the 7% uncertainty range. Neutron flux distribution showed good consistency with minor location-specific deviations.

Overall, these findings confirm MCBCS as a reliable and accurate tool for burnup calculations of the NUR research reactor.

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利用 SCALE/TRITON T6-DEPL 序列对 NUR 研究堆进行基于软件的自动燃耗计算

这项工作是专门为 NUR 研究反应堆定制的蒙特卡洛燃耗计算系统 (MCBCS) 开发过程中的一个重要里程碑。MCBCS 使用 Python 开发，并利用 SCALE 代码中的三维蒙特卡罗 TRITON 耗竭序列 (T6-DEPL)，准确地模拟了反应堆的运行历史。本文概述了 MCBCS，重点介绍了其组件、验证和确认。对于新鲜堆芯，根据实验数据和 MCNP5 计算结果对过剩反应性、控制棒价值和临界构型进行的比较显示出良好的一致性。燃耗计算与测量的堆芯过剩反应性、燃料组件的反应性值和中子通量分布进行了验证。系统略微低估了-2.95%的堆芯过剩反应度，反应度值的差异保持在 7% 的不确定性范围内。总体而言，这些研究结果证实 MCBCS 是用于 NUR 研究堆烧毁度计算的可靠而准确的工具。

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

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.