Analysis of fuel alternatives to achieve breeding capability in the FUJI-U3-(0) reactor

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Maíra Cesário A. Lobo , Marcelo V. Silva , Diego M.E. Gonçalves , João Manoel L. Moreira , Daniel Artur P. Palma , Francky Roger A. da Silva , Giovanni L. de Stefani
{"title":"Analysis of fuel alternatives to achieve breeding capability in the FUJI-U3-(0) reactor","authors":"Maíra Cesário A. Lobo ,&nbsp;Marcelo V. Silva ,&nbsp;Diego M.E. Gonçalves ,&nbsp;João Manoel L. Moreira ,&nbsp;Daniel Artur P. Palma ,&nbsp;Francky Roger A. da Silva ,&nbsp;Giovanni L. de Stefani","doi":"10.1016/j.pnucene.2025.105958","DOIUrl":null,"url":null,"abstract":"<div><div>In this study, the core physics of the FUJI-U3-(0) small modular molten salt reactor was simulated using the SERPENT code. The cylindrical thermal reactor core was modeled with three concentric regions, each containing distinct fuel channel radii embedded within hexagonal graphite moderator rods. Five molten salt fuel compositions were analyzed, varying the fissile and fertile materials and their respective proportions. After criticality was achieved, key reactor performance metrics, including conversion ratio and waste production, were evaluated. The results led to discussion of the feasibility of a thermal molten salt breeder reactor with different fuel types. Furthermore, APTh1000 and ANGRA-I nuclear waste was incorporated into selected fuel compositions. For APTh1000 waste, an economic assessment of recycled fuel was performed, which revealed that it is more cost-effective and environmentally advantageous compared to fresh fuel.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105958"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025003567","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

In this study, the core physics of the FUJI-U3-(0) small modular molten salt reactor was simulated using the SERPENT code. The cylindrical thermal reactor core was modeled with three concentric regions, each containing distinct fuel channel radii embedded within hexagonal graphite moderator rods. Five molten salt fuel compositions were analyzed, varying the fissile and fertile materials and their respective proportions. After criticality was achieved, key reactor performance metrics, including conversion ratio and waste production, were evaluated. The results led to discussion of the feasibility of a thermal molten salt breeder reactor with different fuel types. Furthermore, APTh1000 and ANGRA-I nuclear waste was incorporated into selected fuel compositions. For APTh1000 waste, an economic assessment of recycled fuel was performed, which revealed that it is more cost-effective and environmentally advantageous compared to fresh fuel.
FUJI-U3-(0)反应堆实现增殖能力的燃料替代分析
在本研究中,使用SERPENT代码对FUJI-U3-(0)小型模块化熔盐堆的堆芯物理进行了模拟。圆柱形热堆堆芯采用三个同心区域进行建模,每个区域包含嵌入在六边形石墨慢化剂棒内的不同燃料通道半径。分析了五种熔盐燃料的组成,改变了易裂变和可增殖物质及其各自的比例。达到临界后,对包括转化率和废物产生量在内的关键反应器性能指标进行评估。研究结果对不同燃料类型的热熔盐增殖反应堆的可行性进行了讨论。此外,将APTh1000和ANGRA-I核废料加入选定的燃料成分中。对于APTh1000废弃物,进行了循环燃料的经济评估,结果表明,与新鲜燃料相比,循环燃料更具成本效益和环境优势。
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
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信