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

IF 1.9 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

{"title":"GeN-Foam and OpenMC simulation for multi-physics analysis of fast-spectrum molten salt reactor with beryllium oxide reflector","authors":"Wooseong Park, Yong Hoon Jeong","doi":"10.1016/j.anucene.2025.111378","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111378"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925001951","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

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.

查看原文本刊更多论文

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

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.