A simplified approach to evaluating severe accident source term for PWR

被引:4
作者
Huang, Gaofeng [1 ]
Tong, Lili [1 ]
Cao, Xuewu [1 ]
机构
[1] Shanghai Jiao Tong Univ, Sch Mech Engn, Shanghai 200240, Peoples R China
基金
中国国家自然科学基金;
关键词
Severe accident; Source term evaluation; Simplified approach;
D O I
10.1016/j.anucene.2014.03.037
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
For early design of NPPs, no specific severe accident source term evaluation was considered. Some general source terms have been used for some NPPs. In order to implement a best estimate, a special source term evaluation should be implemented for an NPP. Traditional source term evaluation approaches (mechanism approach and parametric approach) have some difficulties associated with their implementation. The traditional approaches are not consistent with cost-benefit assessment. A simplified approach for evaluating severe accident source term for PWR is studied. For the simplified approach, a simplified containment event tree is established. According to representative cases selection, weighted coefficient evaluation, computation of representative source term cases and weighted computation, five containment release categories are established, including containment bypass, containment isolation failure, containment early failure, containment late failure and intact containment. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:352 / 360
页数:9
相关论文
共 50 条
[21]   Example of PWR Severe Accident Sensitivity and Uncertainty Analyses Using MELCOR Code [J].
Malicki, M. ;
Lind, T. .
NUCLEAR TECHNOLOGY, 2025,
[22]   Application of Bayesian nonparametric models to the uncertainty and sensitivity analysis of source term in a BWR severe accident [J].
Zheng, Xiaoyu ;
Itoh, Hiroto ;
Kawaguchi, Kenji ;
Tamaki, Hitoshi ;
Maruyama, Yu .
RELIABILITY ENGINEERING & SYSTEM SAFETY, 2015, 138 :253-262
[23]   Research on severe accident diagnosis method based on PCA and DT for a small modular PWR [J].
Bi, Xiaolong ;
Sun, Peiwei ;
Wei, Xinyu .
NUCLEAR ENGINEERING AND DESIGN, 2025, 442
[24]   MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident [J].
Li, Longze ;
Zhang, Yapei ;
Tian, Wenxi ;
Su, Guanghui ;
Qiu, Suizheng .
PROGRESS IN NUCLEAR ENERGY, 2014, 77 :141-151
[25]   The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR [J].
Niu, S. P. ;
Zhang, Y. P. ;
Tian, W. X. ;
Qiu, S. Z. ;
Su, G. H. .
ANNALS OF NUCLEAR ENERGY, 2017, 99 :9-18
[26]   Uncertainty analysis and its application of radioactive source term of HPR1000 under severe accident [J].
Shi X. ;
Sun J. ;
Chen Q. ;
Wang H. .
International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3 :134-138
[27]   Study on the influence of source term release on accident consequences in severe accidents for small pressurized water reactor [J].
Mao, Zhangliang ;
Chen, Yuqing ;
Wang, Wei ;
Cai, Qi .
PROGRESS IN NUCLEAR ENERGY, 2022, 154
[28]   Severe accident management measures for a generic German PWR. Part I: Station blackout [J].
Wilhelm, P. ;
Jobst, M. ;
Kozmenkov, Y. ;
Schaefer, F. ;
Kliem, S. .
ANNALS OF NUCLEAR ENERGY, 2018, 122 :217-228
[29]   Water reflooding effectiveness assessment for 1 000 MWe PWR under severe accident condition [J].
Hu, Xiao ;
Huang, Ting ;
Pei, Jie ;
Chen, Lian .
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2015, 49 (11) :2069-2075
[30]   Comparative analysis on the influence of the MAAP4 phenomenological model parameters for the severe accident source term for different plant designs and accident scenarios [J].
Kang, Seong Woo ;
Yim, Man-Sung .
ANNALS OF NUCLEAR ENERGY, 2018, 117 :98-108