Research on the Influence of Reactor Thermal-Hydraulic Parameters on Source Term Release Behavior in Severe Accidents

被引：0
|
作者：
Yang H. [1 ]
Zhang B. [1 ,2 ]
Li J. [1 ]
Miao F. [1 ]
Zhang Z. [1 ]
Shan J. [1 ,2 ]
机构：
[1] School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an
[2] State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an
来源：
Hsi-An Chiao Tung Ta Hsueh/Journal of Xi'an Jiaotong University | 2024年 / 58卷 / 03期
关键词：
sensitivity analysis; severe accident; source term; thermal-hydraulic; uncertainty analysis;
D O I：
10.7652/xjtuxb202403003
中图分类号：
学科分类号：
摘要：
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. © 2024 Xi'an Jiaotong University. All rights reserved.
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页码：25 / 37
页数：12
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