Development of Adaptive Sampling Software Based on Relap5

Haoyin Chen, He Wang, Mohamedelmogtabh Omer Elfadni Suliman, Xinyue Wang, Qiang Zhao
{"title":"Development of Adaptive Sampling Software Based on Relap5","authors":"Haoyin Chen, He Wang, Mohamedelmogtabh Omer Elfadni Suliman, Xinyue Wang, Qiang Zhao","doi":"10.1115/icone29-92454","DOIUrl":null,"url":null,"abstract":"\n The RISMC analysis method is a coupled dynamic safety analysis method that combines deterministic safety analysis and probabilistic safety analysis. It comprehensively simulates the dynamic response process of nuclear power plants under accidents through Monte Carlo sampling and dynamic event tree methods. In order to fully reflect the response process of the nuclear power plant and ensure the accuracy of the calculation results, it is necessary to sample a large number of input space parameters, which will result in unbearable time costs. Adaptive sampling can predict the state of the position input space parameters through a small number of forward sampling calculation results and divide the input space by generating limit surfaces to calculate the failure probability, which can greatly save computing time. Based on researching RISMC analysis tools at home and abroad, the research and development of adaptive sampling and RELAP5 coupling calculation software is realized. The test case of the Qinshan nuclear power plant station blackout accident shows that the adaptive sampling function of calculating failure space probability through a small amount of sampling is realized, and the efficiency of RISMC analysis and calculation is improved.","PeriodicalId":302303,"journal":{"name":"Volume 15: Student Paper Competition","volume":"36 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 15: Student Paper Competition","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-92454","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

The RISMC analysis method is a coupled dynamic safety analysis method that combines deterministic safety analysis and probabilistic safety analysis. It comprehensively simulates the dynamic response process of nuclear power plants under accidents through Monte Carlo sampling and dynamic event tree methods. In order to fully reflect the response process of the nuclear power plant and ensure the accuracy of the calculation results, it is necessary to sample a large number of input space parameters, which will result in unbearable time costs. Adaptive sampling can predict the state of the position input space parameters through a small number of forward sampling calculation results and divide the input space by generating limit surfaces to calculate the failure probability, which can greatly save computing time. Based on researching RISMC analysis tools at home and abroad, the research and development of adaptive sampling and RELAP5 coupling calculation software is realized. The test case of the Qinshan nuclear power plant station blackout accident shows that the adaptive sampling function of calculating failure space probability through a small amount of sampling is realized, and the efficiency of RISMC analysis and calculation is improved.
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
基于Relap5的自适应采样软件开发
RISMC分析方法是一种确定性安全分析与概率安全分析相结合的耦合动态安全分析方法。通过蒙特卡罗采样和动态事件树方法,全面模拟了核电站在事故下的动态响应过程。为了充分反映核电站的响应过程,保证计算结果的准确性,需要对大量的输入空间参数进行采样,这将造成难以承受的时间成本。自适应采样可以通过少量前向采样计算结果预测位置输入空间参数的状态,并通过生成极限曲面对输入空间进行划分来计算失效概率,可以大大节省计算时间。在研究国内外RISMC分析工具的基础上,实现了自适应采样与RELAP5耦合计算软件的研究与开发。秦山核电站停电事故的试验实例表明,实现了通过少量采样计算故障空间概率的自适应采样函数,提高了RISMC分析计算的效率。
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
自引率
0.00%
发文量
0
期刊最新文献
Research on Generalization of Typical Data-Driven Fault Diagnosis Methods for Nuclear Power Plants Heat Transfer Characteristics of Different Horizontal Wires in Pools of Liquid and Supercritical Carbon Dioxide Specifics of Calculating Thermophysical Properties of CO2 and R134a in Critical Point Using NIST REFPROP Radiation Shielding Towards Commonly Available Objects Preliminary Core Calculation on Reactivity Compensation for SiC Matrix Fuel Compact HTTR With Erbium Burnable Poison and Plutonium Fissile Material
×
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