SGTR analysis on CPR1000 with a passive safety system

被引:3
|
作者
Yang, Zijiang [1 ,2 ]
Shan, Jianqiang [2 ]
Gou, Junli [2 ]
Ishii, Mamoru [1 ]
机构
[1] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian, Shaanxi, Peoples R China
[2] Purdue Univ, Sch Nucl Engn, W Lafayette, IN 47907 USA
关键词
Passive safety system; CPR1000; Modification; Actuation conditions; Accident assumptions; Sensitivity analysis; DESIGN; REACTOR; CONTAINMENT;
D O I
10.1016/j.nucengdes.2018.03.009
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
As the development of the nuclear industry, passive technology turns out to be a remarkable characteristic in the design of advanced nuclear power plants. Since the 20th century, much effort has been given to the passive technology, and a number of evolutionary passive systems have been developed. The CPR1000 plant, which is one kind of mature pressurized water plants in China, is proposed to be improved with some passive systems to enhance safety. The proposed passive systems include: (1) the RMT (reactor makeup tank); (2) the ACC (accumulator); (3) the IRWST (in-containment refueling water storage tank); (4) the PEFS (passive emergency feed water system), which is installed on the secondary side of SGs; (5) the PDS (passive depressurization system). In modifying the passive safety system, it is found that the actuation conditions of the passive safety system and the accident assumptions bring great effects on the accidental mitigation. It is necessary to study the influence induced by them. In this paper, the transient phenomenon of SGTR is analyzed to show the process in the modification of the actuation conditions and the assumptions. Finally, the most proper assumptions and actuation conditions are determined. Through the sensitivity analysis, it is found that the RMTs' and PEFSs' behaviors bring a great impact on the accident transient. The strong mutual effect between each passive safety component in the SGTR is the reason of choosing this accident to analyze in this paper.
引用
收藏
页码:319 / 328
页数:10
相关论文
共 50 条
  • [1] Analysis of SBLOCA on CPR1000 with a passive system
    Yang, Zi-Jiang
    Gou, Jun-Li
    Shan, Jian-Qiang
    Wu, Pan
    [J]. NUCLEAR SCIENCE AND TECHNIQUES, 2017, 28 (01)
  • [2] Analysis of SBLOCA on CPR1000 with a passive system
    Zi-Jiang Yang
    Jun-Li Gou
    Jian-Qiang Shan
    Pan Wu
    [J]. Nuclear Science and Techniques, 2017, 28 (01) : 92 - 101
  • [3] Analysis of SBLOCA on CPR1000 with a passive system
    Zi-Jiang Yang
    Jun-Li Gou
    Jian-Qiang Shan
    Pan Wu
    [J]. Nuclear Science and Techniques, 2017, 28
  • [4] Preliminary assessment of a combined passive safety system for typical 3-loop PWR CPR1000
    Yang, Zijiang
    Shan, Jianqiang
    Gou, Junli
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2017, 313 : 148 - 161
  • [5] Design and transient analyses of emergency passive residual heat removal system of CPR1000
    Zhang, Y. P.
    Qiu, S. Z.
    Su, G. H.
    Tian, W. X.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2012, 242 : 247 - 256
  • [6] A Brief Analysis of AP1000 and CPR1000 Excore Nuclear Instrument System
    AP1000与CPR1000堆外核测系统对比分析
    [J]. 2018, Shanghai Jiaotong University (52):
  • [7] Low temperature overpressurization analysis for CPR1000
    Liang, Yu
    Wang, Mingjun
    Li, Zhen
    Liao, Haoyu
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G.H.
    [J]. International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3 : 145 - 153
  • [8] 国和一号与CPR1000的SGTR事故响应比较
    韩凯
    [J]. 核安全, 2020, 19 (03) : 19 - 25
  • [9] CPR1000核电厂SGTR事故长期阶段的分析研究
    鲍杰
    崔军
    付浩
    王一鸣
    郑继业
    [J]. 核安全, 2018, 17 (04) : 10 - 16
  • [10] LBLOCA Analysis of CPR1000 NPP with advanced accumulator
    Hu, Hongwei
    Shan, Jianqiang
    Gou, Junli
    Zhang, Bo
    Wang, Haitao
    Yang, Zijiang
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4, 2014,