Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2024-08-21 DOI:10.1007/s10512-024-01110-x

R. V. Plekhanov, V. E. Druzhinin, I. A. Prokhorov, D. A. Lysov, A. S. Nemirov

{"title":"Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics","authors":"R. V. Plekhanov, V. E. Druzhinin, I. A. Prokhorov, D. A. Lysov, A. S. Nemirov","doi":"10.1007/s10512-024-01110-x","DOIUrl":null,"url":null,"abstract":"<div><p>The article describes a set of studies for estimating and substantiating the limit mass of graphite removed during the resource characteristic management of RBMK reactors. The limit mass is understood as the maximum mass of graphite that can be removed from the reactor core at the stages of resource characteristic management without violating the operational limits of neutron-physical characteristics during the operation of power units over a period of 45 years. The substantiation of the limit mass was made based on the detailed computational simulation of reactor operation for realistic operational scenarios of the third and fourth power units of the Leningrad NPP. Particular attention is paid to the change in the void coefficient for the predicted states of reactors. The uncertainty of the limit mass of removed graphite is analyzed. The trueness of the calculated predictive estimates of neutron-physical characteristics and the limit mass of removed graphite is confirmed by the measurement results. It is shown that, by taking into account the considered operational scenarios for the reactors of the third and fourth power units of the Leningrad NPP, nuclear safety is ensured.</p></div>","PeriodicalId":480,"journal":{"name":"Atomic Energy","volume":"135 5-6","pages":"256 - 263"},"PeriodicalIF":0.4000,"publicationDate":"2024-08-21","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/s10512-024-01110-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 a set of studies for estimating and substantiating the limit mass of graphite removed during the resource characteristic management of RBMK reactors. The limit mass is understood as the maximum mass of graphite that can be removed from the reactor core at the stages of resource characteristic management without violating the operational limits of neutron-physical characteristics during the operation of power units over a period of 45 years. The substantiation of the limit mass was made based on the detailed computational simulation of reactor operation for realistic operational scenarios of the third and fourth power units of the Leningrad NPP. Particular attention is paid to the change in the void coefficient for the predicted states of reactors. The uncertainty of the limit mass of removed graphite is analyzed. The trueness of the calculated predictive estimates of neutron-physical characteristics and the limit mass of removed graphite is confirmed by the measurement results. It is shown that, by taking into account the considered operational scenarios for the reactors of the third and fourth power units of the Leningrad NPP, nuclear safety is ensured.

Abstract Image

查看原文本刊更多论文

估算在管理 RBMK-1000 资源特征的分阶段工作中清除的最大石墨量

文章介绍了一套研究，用于估算和证实在 RBMK 反应堆资源特性管理过程中移除石墨的极限质量。极限质量是指在 45 年的动力装置运行期间，在不违反中子物理特性运行限制的情况下，在资源特性管理阶段从反应堆堆芯中移除石墨的最大质量。极限质量是在对列宁格勒核电厂第三和第四动力装置的实际运行情况进行反应堆运行详细计算模拟的基础上确定的。其中特别关注了反应堆预测状态下空隙系数的变化。分析了去除石墨的极限质量的不确定性。测量结果证实了计算得出的中子物理特性预测值和去除石墨的极限质量的真实性。结果表明，考虑到列宁格勒核电厂第三和第四发电机组反应堆的运行情况，核安全是有保障的。

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

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.