GeN-Foam and OpenMC simulation for multi-physics analysis of fast-spectrum molten salt reactor with beryllium oxide reflector

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-03-22 DOI:10.1016/j.anucene.2025.111378

Wooseong Park, Yong Hoon Jeong

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Abstract

Recent interest in fast-spectrum molten salt reactors (F-MSRs) has promoted the need for multi-physics analysis. Specifically, the cavity core configuration requires an analysis on unstructured domain, promoting the development of OpenFOAM-based multi-physics codes. Concurrently, beryllium oxide (BeO) has been suggested as a promising reflector material for F-MSRs due to its favorable neutronics performance. However, the use of BeO introduces a highly skewed power distribution towards the wall, potentially leading to significant hot spot zones and distinctive neutronics fields. Accordingly, this study conducted multi-dimensional, multi-physics analysis of a F-MSR core with BeO reflector. GeN-Foam served as the primary multi-physics analysis tool using multi-group diffusion approach with group constants provided by OpenMC. Firstly, this study validated the applicability of GeN-Foam to BeO applications and the accuracy of group constants through pure neutronics simulation. Subsequenlty, multi-physics analysis was performed on MSFR-like geometry, revealing the distinctive characteristics of BeO reflector in F-MSRs.

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GeN-Foam 和 OpenMC 仿真用于带氧化铍反射器的快谱熔盐反应堆的多物理场分析

近年来对快谱熔盐堆（F-MSRs）的兴趣促进了对多物理场分析的需求。具体来说，空腔核结构需要对非结构化域进行分析，从而促进了基于openfoam的多物理场代码的开发。同时，氧化铍（BeO）由于其良好的中子性能被认为是一种很有前途的反射材料。然而，BeO的使用引入了对墙壁的高度倾斜的功率分布，可能导致显著的热点区域和独特的中子场。因此，本研究对带有BeO反射器的F-MSR磁芯进行了多维、多物理场分析。GeN-Foam作为主要的多物理场分析工具，使用OpenMC提供的群常数的多群扩散方法。首先，本研究通过纯中子模拟验证了GeN-Foam在BeO应用中的适用性和基团常数的准确性。随后，对类msr几何结构进行了多物理场分析，揭示了f - msr中BeO反射器的独特特征。

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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.