Thermal-Hydraulic Safety Assessment in Advanced Boiling Water Reactors due to Fuel Failure and Loss of Offsite Power

F. G. Thulu, C. Mikeka, Hailemichael Guadie Mengsitu, C. Tenthani
{"title":"Thermal-Hydraulic Safety Assessment in Advanced Boiling Water Reactors due to Fuel Failure and Loss of Offsite Power","authors":"F. G. Thulu, C. Mikeka, Hailemichael Guadie Mengsitu, C. Tenthani","doi":"10.1109/SEGE55279.2022.9889753","DOIUrl":null,"url":null,"abstract":"This work presents the safety assessment of thermal-hydraulic parameters in Advance Boiling Water Reactor (ABWR) due to fuel failure at full power concurrently with loss of offsite power transient. Overall thermal-hydraulic of ABWR with various control passive safety systems, trip, accident progression, actuation logics were calculated with system ASYST thermal-hydraulic program. No operator’s interference was involved during simulation. This study was carried out in reference to the main safety margins of the fuel surface temperature, primary coolant flow-rates and primary pressure. Following the postulated events, the accident progression and changes in pressure, mass flow rates, fuel clad temperature and the responses of safety emergence core cooling systems were investigated. The results showed that actuation of passive safety systems in the ABWR enhanced accident mitigation. Primary coolant flow-rates and pressure in the pressure vessel changes did not compromise with the integrity of the reactor. This affirms the inherent concepts and principles of defence-in-depth within the design of ABWR. The results provide confidence in the inherent robustness of the ABWR design with respect to fuel failure at full power concurrently with a full off-site power loss in the validity of a two-tier calculation method. This could be useful in, probabilistic safety assessment, severe accident management guidelines and public acceptance for the ABWR.","PeriodicalId":338339,"journal":{"name":"2022 IEEE 10th International Conference on Smart Energy Grid Engineering (SEGE)","volume":"14 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-08-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"2022 IEEE 10th International Conference on Smart Energy Grid Engineering (SEGE)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/SEGE55279.2022.9889753","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1

Abstract

This work presents the safety assessment of thermal-hydraulic parameters in Advance Boiling Water Reactor (ABWR) due to fuel failure at full power concurrently with loss of offsite power transient. Overall thermal-hydraulic of ABWR with various control passive safety systems, trip, accident progression, actuation logics were calculated with system ASYST thermal-hydraulic program. No operator’s interference was involved during simulation. This study was carried out in reference to the main safety margins of the fuel surface temperature, primary coolant flow-rates and primary pressure. Following the postulated events, the accident progression and changes in pressure, mass flow rates, fuel clad temperature and the responses of safety emergence core cooling systems were investigated. The results showed that actuation of passive safety systems in the ABWR enhanced accident mitigation. Primary coolant flow-rates and pressure in the pressure vessel changes did not compromise with the integrity of the reactor. This affirms the inherent concepts and principles of defence-in-depth within the design of ABWR. The results provide confidence in the inherent robustness of the ABWR design with respect to fuel failure at full power concurrently with a full off-site power loss in the validity of a two-tier calculation method. This could be useful in, probabilistic safety assessment, severe accident management guidelines and public acceptance for the ABWR.
先进沸水堆燃料失效和场外断电的热水力安全评估
本文研究了超前沸水反应堆(ABWR)在全功率燃料失效和暂态失电情况下热工参数的安全性评估。采用系统ASYST热液程序对不同控制被动安全系统下的水冷堆整体热液、起下钻、事故进展、驱动逻辑进行了计算。模拟过程中不涉及操作人员的干扰。该研究参照燃料表面温度、一次冷却剂流量和一次压力的主要安全裕度进行。在假定事件发生后,研究了事故的进展和压力、质量流量、燃料包层温度的变化以及安全应急堆芯冷却系统的响应。结果表明,被动安全系统的启动增强了事故的缓解。一次冷却剂的流量和压力容器内的压力变化没有影响反应堆的完整性。这肯定了ABWR设计中固有的纵深防御概念和原则。结果表明,在两层计算方法的有效性中,ABWR设计具有固有的鲁棒性,既考虑了全功率燃料失效,又考虑了全场外功率损失。这对ABWR的概率安全评估、严重事故管理指南和公众接受度都是有用的。
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
自引率
0.00%
发文量
0
×
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