Progress in understanding the formation and deposition behaviors of corrosion and oxidation products in lead-cooled fast reactors

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zhengang Duan , Hongchen Xiang , Pengrui Qiao , Qinglong Wen , Huiping Ouyang
{"title":"Progress in understanding the formation and deposition behaviors of corrosion and oxidation products in lead-cooled fast reactors","authors":"Zhengang Duan ,&nbsp;Hongchen Xiang ,&nbsp;Pengrui Qiao ,&nbsp;Qinglong Wen ,&nbsp;Huiping Ouyang","doi":"10.1016/j.pnucene.2025.105742","DOIUrl":null,"url":null,"abstract":"<div><div>The Lead-cooled fast reactor (LFR) is regarded as a promising fourth-generation advanced power reactor. However, the development of LFR is limited by the corrosion problems of structural materials. Corrosion and oxidation products can deposit on the heat transfer surface during the migration process of the coolant, leading to heat transfer degradation and posing a serious threat to reactor operation safety. In recent years, researchers have conducted extensive research on corrosion protection, as well as the migration, deposition, and impact of corrosion and oxidation products. This paper focuses on oxygen control technology, summarizes the current corrosion protection technologies for lead-cooled fast reactors, introduces the formation mechanisms of common corrosion and oxidation products in lead-cooled fast reactors, briefly summarizes the migration and deposition mechanisms of corrosion and oxidation products, and finally puts forward suggestions for further research based on the current research progress.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"184 ","pages":"Article 105742"},"PeriodicalIF":3.3000,"publicationDate":"2025-03-14","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/S0149197025001404","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

The Lead-cooled fast reactor (LFR) is regarded as a promising fourth-generation advanced power reactor. However, the development of LFR is limited by the corrosion problems of structural materials. Corrosion and oxidation products can deposit on the heat transfer surface during the migration process of the coolant, leading to heat transfer degradation and posing a serious threat to reactor operation safety. In recent years, researchers have conducted extensive research on corrosion protection, as well as the migration, deposition, and impact of corrosion and oxidation products. This paper focuses on oxygen control technology, summarizes the current corrosion protection technologies for lead-cooled fast reactors, introduces the formation mechanisms of common corrosion and oxidation products in lead-cooled fast reactors, briefly summarizes the migration and deposition mechanisms of corrosion and oxidation products, and finally puts forward suggestions for further research based on the current research progress.
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:481959085
Book学术官方微信