Reduction of the erbium content in RBMK-1000 fuel

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2024-06-10 DOI:10.1007/s10512-024-01075-x
Yu. V. Alimov, A. V. Kaplienko, P. B. Kuznetsov, I. M. Rozhdestvenskiy, A. V. Slobodchikov, V. K. Davydov, A. P. Zhirnov, S. S. Lebedev
{"title":"Reduction of the erbium content in RBMK-1000 fuel","authors":"Yu. V. Alimov,&nbsp;A. V. Kaplienko,&nbsp;P. B. Kuznetsov,&nbsp;I. M. Rozhdestvenskiy,&nbsp;A. V. Slobodchikov,&nbsp;V. K. Davydov,&nbsp;A. P. Zhirnov,&nbsp;S. S. Lebedev","doi":"10.1007/s10512-024-01075-x","DOIUrl":null,"url":null,"abstract":"<div><p>The paper presents the results of a calculation study connected with the composition of RBMK-1000 fuel having a reduced erbium content. The computational studies were carried out using SADCO software systems (developed by JSC “NIKIET”) and MCU-RBMK (developed by NRC “Kurchatov Institute”). The studies include calculations of a fuel cell with various compositions of uranium-erbium fuel and a RBMK-1000 reactor under fuel-loading conditions involving a reduced erbium content. The conversion of RBMK-1000 to a fuel having a reduced erbium content ensures the neutron-physical characteristics and volumes of accumulating commercial <sup>60</sup>Co to be maintained within operational limits under conditions of extending the reactor service life for more than 50 years.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 1-2","pages":"12 - 19"},"PeriodicalIF":0.4000,"publicationDate":"2024-06-10","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/s10512-024-01075-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 paper presents the results of a calculation study connected with the composition of RBMK-1000 fuel having a reduced erbium content. The computational studies were carried out using SADCO software systems (developed by JSC “NIKIET”) and MCU-RBMK (developed by NRC “Kurchatov Institute”). The studies include calculations of a fuel cell with various compositions of uranium-erbium fuel and a RBMK-1000 reactor under fuel-loading conditions involving a reduced erbium content. The conversion of RBMK-1000 to a fuel having a reduced erbium content ensures the neutron-physical characteristics and volumes of accumulating commercial 60Co to be maintained within operational limits under conditions of extending the reactor service life for more than 50 years.

Abstract Image

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
减少 RBMK-1000 燃料中的铒含量
本文介绍了与铒含量降低的 RBMK-1000 燃料成分有关的计算研究结果。计算研究使用 SADCO 软件系统(由 JSC "NIKIET "开发)和 MCU-RBMK(由 NRC "Kurchatov Institute "开发)进行。研究内容包括对使用不同铀铒燃料成分的燃料电池和 RBMK-1000 反应堆在降低铒含量的燃料加载条件下的计算。将 RBMK-1000 转换为铒含量降低的燃料,可确保在将反应堆使用寿命延长 50 年以上的条件下,将中子物理特性和商用 60Co 的累积量保持在运行限度内。
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
Liquidus temperature study of LiF–NaF–KF-based melts simulating the fuel salt of a molten-salt reactor for Np, Am, Cm transmutation An analysis of machine learning for the safety justification of VVER reactors Development of a neural-network methodology for the safety justification of VVER reactors in manoeuvring modes Formation of intermetallics during the metallization of model nuclear fuel based on uranium dioxide containing oxides of rare earth metals and palladium Self-protection of fast lead-cooled reactors against the partial blockage of the core flow area
×
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:481959085
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