Experimental justification of a pyrochemical technology for reprocessing of mixed uranium-plutonium nitride spent nuclear fuel

IF 0.3 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2025-02-10 DOI:10.1007/s10512-024-01164-x
Yu. P. Zaikov, A. E. Galashev, A. S. Kholkina, V. A. Kovrov, Yu. S. Mochalov
{"title":"Experimental justification of a pyrochemical technology for reprocessing of mixed uranium-plutonium nitride spent nuclear fuel","authors":"Yu. P. Zaikov,&nbsp;A. E. Galashev,&nbsp;A. S. Kholkina,&nbsp;V. A. Kovrov,&nbsp;Yu. S. Mochalov","doi":"10.1007/s10512-024-01164-x","DOIUrl":null,"url":null,"abstract":"<div><p>The article describes pyrochemical processing of spent nuclear fuel, including high-temperature processing, electrochemical reduction of actinide oxides to metals in a chloride-oxide melt, anode manufacture by induction remelting, and electrolytic refining of actinides in a chloride melt. The technology has been proven and tested on model nuclear fuel. The obtained data underlay the requirements for reagents and support systems. Moreover, these data were used for the design of equipment and pyrochemical section of the processing module at the pilot demonstration energy complex as part of the power unit with the BREST-OD-300 lead-cooled reactor currently being constructed at the site of the Siberian Chemical Combine JSC, Russian Federation.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"136 5-6","pages":"300 - 306"},"PeriodicalIF":0.3000,"publicationDate":"2025-02-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Atomic Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10512-024-01164-x","RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The article describes pyrochemical processing of spent nuclear fuel, including high-temperature processing, electrochemical reduction of actinide oxides to metals in a chloride-oxide melt, anode manufacture by induction remelting, and electrolytic refining of actinides in a chloride melt. The technology has been proven and tested on model nuclear fuel. The obtained data underlay the requirements for reagents and support systems. Moreover, these data were used for the design of equipment and pyrochemical section of the processing module at the pilot demonstration energy complex as part of the power unit with the BREST-OD-300 lead-cooled reactor currently being constructed at the site of the Siberian Chemical Combine JSC, Russian Federation.

查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
混合铀-氮化钚乏燃料后处理热化学技术的实验论证
文章介绍了乏核燃料的热化学处理方法,包括高温处理、在氯氧化物熔体中将锕系元素氧化物电化学还原成金属、通过感应重熔制造阳极,以及在氯化物熔体中电解精炼锕系元素。该技术已在核燃料模型上得到验证和测试。获得的数据为试剂和支持系统的要求提供了依据。此外,这些数据还被用于设计试验示范能源综合体的设备和加工模块的热化学部分,该综合体是目前正在俄罗斯联邦西伯利亚化学联合股份公司(Siberian Chemical Combine JSC)建造的带有 BREST-OD-300 铅冷却反应堆的动力装置的一部分。
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 去求助
来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
期刊最新文献
DUM-R salinometer: innovative solution for in-circuit monitoring of water salt content in the secondary circuit of reactors for nuclear vessels, floating power units, and small modular reactor plants Adjustment of ROM code models for calculating the population exposure dose according to international recommendations Estimated efficiency of gas centrifuge cascade profiling for the feeding stream of stages Predicting the composition and behavior of impurities in the primary coolant of the light-water small modular reactor based on the operating experience of propulsion reactors System of fuel cladding failure detection for the BREST-OD-300 reactor plant
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1