Temperature feedback reactivity analysis for LEU-Fuelled SLOWPOKE-2 research reactor using DRAGON5 and DONJON5 codes

Nuclear Analysis Pub Date : 2024-04-29 DOI:10.1016/j.nucana.2024.100111

Otman Jaï , Otmane El Hajjaji , Abdessamad Didi

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Abstract

The purpose of this study is to provide a new deterministic model for the SLOWPOKE-2 nuclear research reactor at École Polytechnique de Montréal (EPM) with LEU (Low Enriched Uranium) core. Using the latest release of the code system DRAGON5 and DONJON5 and the cross-section data library ENDFB.VII rel.1 evaluation, the developed model is applied to simulate the neutronic behavior of the SLOWPOKE-2 research reactor. We studied the separate temperature effects of the main components of the core (i.e., fuel, coolant/moderator, beryllium reflector, and water reflector). The contribution of different physical phenomena to the RTC was assessed. The temperature reactivity feedback calculated using the deterministic approach based on the DRAGON5 and DONJON5 code system using the ENDF/B-VII.1 evaluated nuclear data library produced in the WIMD-D4 format is in good agreement. Therefore, this work proves the capability of DRAGON5 and DONJON5 codes, normally used for power reactors, to reliably simulate a low-power research reactor.

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使用 DRAGON5 和 DONJON5 代码对 LEU-Fuelled SLOWPOKE-2 研究反应堆进行温度反馈反应性分析

本研究的目的是为蒙特利尔理工学院（EPM）采用 LEU（低浓铀）堆芯的 SLOWPOKE-2 核研究反应堆提供一个新的确定性模型。利用最新发布的 DRAGON5 和 DONJON5 代码系统以及截面数据图书馆 ENDFB.VII rel.1 评估，所开发的模型被用于模拟 SLOWPOKE-2 研究反应堆的中子行为。我们研究了堆芯主要部件（即燃料、冷却剂/慢化剂、铍反射器和水反射器）的单独温度效应。我们评估了不同物理现象对 RTC 的贡献。使用基于 DRAGON5 和 DONJON5 代码系统的确定性方法，利用 WIMD-D4 格式制作的ENDF/B-VII.1 评估核数据图书馆计算出的温度反应性反馈非常一致。因此，这项工作证明了通常用于动力反应堆的 DRAGON5 和 DONJON5 代码能够可靠地模拟低功率研究反应堆。

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

Nuclear Analysis

CiteScore

1.70

自引率

0.00%

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