严重事故工况下反应堆热工水力参数对源项释放行为影响研究

TK08; 为了进一步研究反应堆严重事故进程中热工参数对源项释放的影响,识别对其影响较大的物理过程,从而进一步改进和发展数值模型以提高计算精度降低不确定性,以第三代压水堆为对象,利用一体化严重事故分析程序ISAA对大破口失水事故导致的严重事故开展了数值分析研究,并基于Wilks公式利用 自主开发的不确定性程序代码SAUP对17个热工参数进行了拉丁超立方抽样(LHS)执行批量计算,对目标输出(FoM)即氢气与裂变产物的释放进行了不确定性与敏感性分析.结果表明:在热工参数的不确定性范围内,氧化产氢以及裂变产物的释放呈现正态分布且存在较大的不确定带,包壳氧化层的失效温度、堆芯碎片尺寸以及碎片孔隙率对...

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Published in西安交通大学学报 Vol. 58; no. 3; pp. 25 - 37
Main Authors 杨皓, 张斌, 李济深, 缪凡, 张芷然, 单建强
Format Journal Article
LanguageChinese
Published 西安交通大学动力工程多相流国家重点实验室,710049,西安 01.03.2024
西安交通大学能源与动力工程学院,710049,西安%西安交通大学能源与动力工程学院,710049,西安
Subjects
严重事故
thermal-hydraulic
uncertainty analysis
不确定性分析
源项
sensitivity analysis
severe accident
敏感性分析
热工水力
source term
Online AccessGet full text
ISSN0253-987X
DOI10.7652/xjtuxb202403003

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Abstract TK08; 为了进一步研究反应堆严重事故进程中热工参数对源项释放的影响,识别对其影响较大的物理过程,从而进一步改进和发展数值模型以提高计算精度降低不确定性,以第三代压水堆为对象,利用一体化严重事故分析程序ISAA对大破口失水事故导致的严重事故开展了数值分析研究,并基于Wilks公式利用 自主开发的不确定性程序代码SAUP对17个热工参数进行了拉丁超立方抽样(LHS)执行批量计算,对目标输出(FoM)即氢气与裂变产物的释放进行了不确定性与敏感性分析.结果表明:在热工参数的不确定性范围内,氧化产氢以及裂变产物的释放呈现正态分布且存在较大的不确定带,包壳氧化层的失效温度、堆芯碎片尺寸以及碎片孔隙率对高挥发性裂变产物的释放有较为显著的相关性.该研究有助于理解反应堆严重事故中热工参数与源项之间的复杂联系,同时对核电厂安全系统的设计以及严重事故的预防与缓解具有参考意义.
AbstractList TK08; 为了进一步研究反应堆严重事故进程中热工参数对源项释放的影响,识别对其影响较大的物理过程,从而进一步改进和发展数值模型以提高计算精度降低不确定性,以第三代压水堆为对象,利用一体化严重事故分析程序ISAA对大破口失水事故导致的严重事故开展了数值分析研究,并基于Wilks公式利用 自主开发的不确定性程序代码SAUP对17个热工参数进行了拉丁超立方抽样(LHS)执行批量计算,对目标输出(FoM)即氢气与裂变产物的释放进行了不确定性与敏感性分析.结果表明:在热工参数的不确定性范围内,氧化产氢以及裂变产物的释放呈现正态分布且存在较大的不确定带,包壳氧化层的失效温度、堆芯碎片尺寸以及碎片孔隙率对高挥发性裂变产物的释放有较为显著的相关性.该研究有助于理解反应堆严重事故中热工参数与源项之间的复杂联系,同时对核电厂安全系统的设计以及严重事故的预防与缓解具有参考意义.
Abstract_FL To further investigate the influence of thermal-hydraulic parameters on source term release during severe accidents in a nuclear reactor,and to identify the physical processes that have significant influence and subsequently enhance and develop numerical models to improve computational accuracy and reduce uncertainties,this study focuses on a third-generation pressurized water reactor(Gen-Ⅲ PWR),and numerical analysis is conducted using the integrated severe accident analysis program(ISAA)to study severe accidents caused by a large-break loss-of-coolant accident(LOCA).Based on the Wilks formula,a self-developed uncertainty code called SAUP is employed to perform Latin hypercube sampling(LHS)for 17 thermal-hydraulic parameters,and batch calculations are carried out to analyze the uncertainty and sensitivity of the target output,specifically the release of hydrogen and fission products.The results indicate that within the uncertainty range of thermal-hydraulic parameters,the release of hydrogen oxidation and fission products follows a normal distribution with significant uncertainty.Additionally,there is a notable correlation between the failure temperature of the cladding oxide layer,core fragment size,and fragment porosity with the release of highly volatile fission products.This study contributes to the understanding of the complex relationship between thermal-hydraulic parameters and source terms in severe accidents of nuclear reactors.It also provides valuable insights for the design of safety systems in nuclear power plants and the prevention and mitigation of severe accidents.
Author 李济深
缪凡
单建强
张芷然
杨皓
张斌
AuthorAffiliation 西安交通大学能源与动力工程学院,710049,西安%西安交通大学能源与动力工程学院,710049,西安;西安交通大学动力工程多相流国家重点实验室,710049,西安
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Author_FL SHAN Jianqiang
YANG Hao
MIAO Fan
ZHANG Bin
LI Jishen
ZHANG Zhiran
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DocumentTitle_FL Research on the Influence of Reactor Thermal-Hydraulic Parameters on Source Term Release Behavior in Severe Accidents
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Keywords 严重事故
thermal-hydraulic
uncertainty analysis
不确定性分析
源项
sensitivity analysis
severe accident
敏感性分析
热工水力
source term
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PublicationTitle 西安交通大学学报
PublicationTitle_FL Journal of Xi'an Jiaotong University
PublicationYear 2024
Publisher 西安交通大学动力工程多相流国家重点实验室,710049,西安
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Snippet TK08; 为了进一步研究反应堆严重事故进程中热工参数对源项释放的影响,识别对其影响较大的物理过程,从而进一步改进和发展数值模型以提高计算精度降低不确定性,以第三代压水...
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Title 严重事故工况下反应堆热工水力参数对源项释放行为影响研究
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