Research on passive residual heat remove system under loss of power

被引:0
|
作者
Yuan, Tian-Hong [1 ]
Yu, Lei [1 ]
Wang, Chuan [1 ]
机构
[1] Naval University of Engineering, Wuhan 430033, China
来源
关键词
Coolants - Pressurized water reactors - Safety valves - Water levels - Flow of water - Hydraulics - Nuclear fuels - Steam - Nuclear power plants;
D O I
暂无
中图分类号
学科分类号
摘要
The reactor primary cycle and passive core cool system were simulated by use of RELAP5/MOD3.3 code, then we can conclude transient state operating characteristics of AP1000 passive residual heat removal system (PRHRS) under loss of power accident. The results show that: Condition 1, PRHRS starts on low steam generator water level coincident with low start up feed water flow, opening of pressurizer safety valves will lead coolant reverse flow in the PRHRS, and arouse coolant boiling in the core and excessive temperature differentials between inlet outlet of pressure vessel; condition 2, PRHRS starts directly on power loss signal, safety valves will not open before it starts, so PRHRS is capable of operating effectively.
引用
收藏
页码:248 / 252
相关论文
共 50 条
  • [31] Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system
    Li, Liangguo
    Yu, Jianming
    Nan, Zongbao
    Lu, Donghua
    Xing, Jun
    Lu, Xianghui
    Wu, Yingwei
    Qiu, Suizheng
    Su, Guanghui
    Tian, Wenxi
    Wu, Xiaohang
    Liu, Jiyong
    ANNALS OF NUCLEAR ENERGY, 2023, 186
  • [32] Research on the passive residual heat removal capacity of supercritical carbon dioxide
    Lu, Gonghao
    Zhang, Guangxu
    Jin, Chao
    Tang, Jiajun
    Xie, Rongshun
    Hong, Gang
    Zhang, Yaoli
    NUCLEAR ENGINEERING AND DESIGN, 2024, 429
  • [33] Study on Heat Transfer Capability of Passive Residual Heat Removal System Based on Heat Pipe
    Xian L.
    Zhou K.
    Li F.
    Yang F.
    Zhang Z.
    Zhang D.
    Wang X.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (06): : 100 - 104
  • [34] Advanced PWR passive residual heat removal system cool hot core potential difference threshold research
    Zhuo, Wen-Bin
    Huang, Yan-Ping
    Hedongli Gongcheng/Nuclear Power Engineering, 2002, 23 (SUPPL.): : 26 - 29
  • [35] Performance analysis of passive residual heat removal system under blackout accident of chinese integral advanced reactor
    Shen, Jin
    Jiang, Guang-Ming
    Tang, Gang
    Yu, Hong-Xing
    Hedongli Gongcheng/Nuclear Power Engineering, 2007, 28 (06): : 80 - 83
  • [36] Experimental Study of Density Lock in Passive Residual Heat Removal System
    Lv Xiang-bo
    Yan Chang-qi
    Gu Hai-feng
    2012 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2012,
  • [37] Numerical study on transient characteristics of passive residual heat removal system
    State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
    Hsi An Chiao Tung Ta Hsueh, 2006, 5 (605-608):
  • [38] Fuzzy PSA evaluation method for passive residual heat removal system
    Zhou, Tao
    Chen, Juan
    Luo, Feng
    Cheng, Wanxu
    NUCLEAR ENGINEERING AND DESIGN, 2012, 247 : 230 - 235
  • [39] Failure Probability Assessment of Passive Residual Heat Removal System for NPPs
    Tang H.
    Zhang Z.
    Li H.
    Zhang K.
    Deng C.
    Ran X.
    2017, Atomic Energy Press (38): : 66 - 71
  • [40] Application of direct passive residual heat removal system to the SMART reactor
    Kim, Yeon-Sik
    Bae, Sung-Won
    Cho, Seok
    Kang, Kyoung-Ho
    Park, Hyun-Sik
    ANNALS OF NUCLEAR ENERGY, 2016, 89 : 56 - 62