Justification of RCCAs lifetime extension at operating Ukrainian NPPs. Summary calculations

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Valeriy Zuyok , Oleksandr Mazurok , Oleg Godun , Mykola Chaikovskyi , Anton Makarenko , Vadym Ivanov , Valodymyr Zigunov , Mykhaylo Tretyakov
{"title":"Justification of RCCAs lifetime extension at operating Ukrainian NPPs. Summary calculations","authors":"Valeriy Zuyok ,&nbsp;Oleksandr Mazurok ,&nbsp;Oleg Godun ,&nbsp;Mykola Chaikovskyi ,&nbsp;Anton Makarenko ,&nbsp;Vadym Ivanov ,&nbsp;Valodymyr Zigunov ,&nbsp;Mykhaylo Tretyakov","doi":"10.1016/j.nucengdes.2025.114008","DOIUrl":null,"url":null,"abstract":"<div><div>One of the ways to temporarily meet the needs of NPPs for rod cluster control assemblies (RCCAs) is to extend their lifetime. The justification for extending the lifetime of RCCAs should be based on the justification of mechanical reliability of control rods (CRs) and RCCAs in general, fulfillment of the criteria for physical efficiency of RCCAs, thermotechnical characteristics of RCCAs, taking into account changes in materials characteristics during the entire previous period of operation in the reactor core.</div><div>In the course of the research, the operational data (RCCAs positions and power unit capacity) for each of the 61 RCCAs of all 13 VVER-1000 power units for the last almost 10 years were analyzed and systematized. The maximum fast neutron flux and <sup>10</sup>B burnup were calculated for each RCCA, and the margin before reaching the limit values was also calculated.</div><div>The results of the performed research enabled to extend the lifetime of almost all RCCAs in VVER-1000 reactors of Ukrainian NPPs from 25,500 to 38,000 h in the automatic control group and from 75,600 to 113,500 h in the reactor scram group, except for twelve RCCAs from RNPP Unit 4 and six RCCAs from SUNPP Unit 1. An individual (separate) assessment of the lifetime was performed for these RCCAs, throughout which the operational integrity criteria for the maximum value of fast neutron flux in the lower part of CR cladding and <sup>10</sup>B burnup will be met.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114008"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325001852","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

One of the ways to temporarily meet the needs of NPPs for rod cluster control assemblies (RCCAs) is to extend their lifetime. The justification for extending the lifetime of RCCAs should be based on the justification of mechanical reliability of control rods (CRs) and RCCAs in general, fulfillment of the criteria for physical efficiency of RCCAs, thermotechnical characteristics of RCCAs, taking into account changes in materials characteristics during the entire previous period of operation in the reactor core.
In the course of the research, the operational data (RCCAs positions and power unit capacity) for each of the 61 RCCAs of all 13 VVER-1000 power units for the last almost 10 years were analyzed and systematized. The maximum fast neutron flux and 10B burnup were calculated for each RCCA, and the margin before reaching the limit values was also calculated.
The results of the performed research enabled to extend the lifetime of almost all RCCAs in VVER-1000 reactors of Ukrainian NPPs from 25,500 to 38,000 h in the automatic control group and from 75,600 to 113,500 h in the reactor scram group, except for twelve RCCAs from RNPP Unit 4 and six RCCAs from SUNPP Unit 1. An individual (separate) assessment of the lifetime was performed for these RCCAs, throughout which the operational integrity criteria for the maximum value of fast neutron flux in the lower part of CR cladding and 10B burnup will be met.
求助全文
约1分钟内获得全文 求助全文
来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
×
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