Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident

Zijie Wu, Peng Chen, Xinhao Zhao, Chao Guo, D. Zhan, Shaoxiong Xia
{"title":"Sensitivity and Uncertainty Analysis of Molten Corium-Concrete Interaction (MCCI) for ALWR During Severe Accident","authors":"Zijie Wu, Peng Chen, Xinhao Zhao, Chao Guo, D. Zhan, Shaoxiong Xia","doi":"10.1115/icone29-89217","DOIUrl":null,"url":null,"abstract":"\n Molten corium-concrete interaction is an important phenomenon in the late phase of severe accident, threatening the integrity of containment and might causing potential large release of radioactivity. A sensitivity and uncertainty analysis of MCCI under severe accident of a 1000 MW advanced light water reactor (ALWR) was performed with ASTEC (MEDICIS) [1], a lumped parametric integral severe accident code developed by IRSN. Several representative phenomena were screened out referenced by EURSAFE severe accident Phenomena Identification and Ranking Table (PIRT) [2], including debris bed formation, layer configuration, heat sources, and convective heat transfer correlation. Related input parameters, sensitivity coefficients, and modeling options in ASTEC code were selected, such as convective correlations, layer stratifications, initial layer compositions, and the potential ranges of these parameters were identified. A simple sampling method was used to analyze the independent effect of each parameter/model. Key parameters were chosen to evaluate the impact of sensitivity parameters to the MCCI process. A large break loss of coolant accident scenario, where in-vessel melt retention is invalid is simulated as an initial event. The results emphasize the importance of layer configuration and fission product partition. However, it should be emphasized that analysis results may be quite uncertain due to the limitation of the physical models and the adequacy or validity of the selected range of input variables.","PeriodicalId":284948,"journal":{"name":"Volume 11: Mitigation Strategies for Beyond Design Basis Events","volume":"17 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Volume 11: Mitigation Strategies for Beyond Design Basis Events","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-89217","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

Molten corium-concrete interaction is an important phenomenon in the late phase of severe accident, threatening the integrity of containment and might causing potential large release of radioactivity. A sensitivity and uncertainty analysis of MCCI under severe accident of a 1000 MW advanced light water reactor (ALWR) was performed with ASTEC (MEDICIS) [1], a lumped parametric integral severe accident code developed by IRSN. Several representative phenomena were screened out referenced by EURSAFE severe accident Phenomena Identification and Ranking Table (PIRT) [2], including debris bed formation, layer configuration, heat sources, and convective heat transfer correlation. Related input parameters, sensitivity coefficients, and modeling options in ASTEC code were selected, such as convective correlations, layer stratifications, initial layer compositions, and the potential ranges of these parameters were identified. A simple sampling method was used to analyze the independent effect of each parameter/model. Key parameters were chosen to evaluate the impact of sensitivity parameters to the MCCI process. A large break loss of coolant accident scenario, where in-vessel melt retention is invalid is simulated as an initial event. The results emphasize the importance of layer configuration and fission product partition. However, it should be emphasized that analysis results may be quite uncertain due to the limitation of the physical models and the adequacy or validity of the selected range of input variables.
轻水堆严重事故中熔芯-混凝土相互作用(MCCI)的敏感性和不确定性分析
熔核-混凝土相互作用是严重事故后期的一个重要现象,它威胁到安全壳的完整性,并可能导致潜在的大量放射性物质泄漏。采用IRSN开发的集总参数积分严重事故代码ASTEC (MEDICIS)[1]对1000mw先进轻水堆(ALWR)严重事故下MCCI的敏感性和不确定性进行了分析。根据EURSAFE严重事故现象识别与排名表(PIRT)[2],筛选出碎屑床形成、层构型、热源、对流换热相关性等几个具有代表性的现象。选择ASTEC代码中的相关输入参数、敏感系数和建模选项,如对流相关性、层分层、初始层组成,并确定这些参数的可能取值范围。采用简单的抽样方法分析各参数/模型的独立效应。选取关键参数,评价灵敏度参数对MCCI过程的影响。模拟了一种冷却剂大断损事故情景,其中容器内熔体保持无效。结果强调了层构型和裂变产物划分的重要性。然而,需要强调的是,由于物理模型的限制以及输入变量选择范围的充分性或有效性,分析结果可能具有很大的不确定性。
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:604180095
Book学术官方微信