Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor

被引:11
|
作者
Huang, Tao [1 ]
Zhang, Y. P. [1 ]
Gong, Houjun [2 ]
Tian, W. X. [1 ]
Su, G. H. [1 ]
Qiu, S. Z. [1 ]
机构
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
[2] Nucl Power Inst China, CNNC Key Lab Nucl Reactor Thermal Hydraul Technol, Chengdu 610041, Peoples R China
基金
中国国家自然科学基金;
关键词
Analysis tool; Water cooling; PRHRS; SBO accident; TRANSIENT ANALYSES; DESIGN;
D O I
10.1016/j.pnucene.2016.03.019
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
An innovative design for Chinese pressurized reactor is the steam generator (SG) secondary side water cooling passive residual heat removal system (PRHRS). The new design is expected to improve reliability and safety of the Chinese pressurized reactor during the event of feed line break or station blackout (SBO) accident. The new system is comprised of a SG, a cooling water pool, a heat exchanger (HX), an emergency makeup tank (EMT) and corresponding valves and pipes. In order to evaluate the reliability of the water cooling PRHRS, an analysis tool was developed based on the drift flux mixture flow model. The preliminary validation of the analysis tool was made by comparing to the experimental data of ESPRIT facility. Calculation results under both high pressure condition and low pressure condition fitted the experimental data remarkably well. A hypothetical SBO accident was studied by taking the residual power table under SBO accident as the input condition of the analysis tool. The calculation results showed that the EMT could supply the water to the SG shell side successfully during SBO accident. The residual power could be taken away successfully by the two-phase natural circulation established in the water cooling PRHRS loop. Results indicate the analysis tool can be used to study the steady and transient operating characteristics of the water cooling PRHRS during some accidents of the Chinese pressurized reactor. The present work has very important realistic significance to the engineering design and assessment of the water cooling PRHRS for Chinese NPPs. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:164 / 174
页数:11
相关论文
共 50 条
  • [31] Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR
    Jiang, Nan
    Peng, Minjun
    Cong, Tenglong
    ANNALS OF NUCLEAR ENERGY, 2018, 117 : 223 - 233
  • [32] Optimization design of passive residual heat removal system based on improved genetic algorithm
    Xia, Genglei
    Bi, Yuepeng
    Wang, Chenyang
    ANNALS OF NUCLEAR ENERGY, 2023, 189
  • [33] A multi-scale CFD-system coupled code for transient analysis of the passive residual heat removal system of MHTGR
    Zhao, Hangbin
    Zheng, Yanhua
    Ma, Tao
    Dong, Yujie
    ANNALS OF NUCLEAR ENERGY, 2020, 141 (141)
  • [34] Experimental investigation on natural circulation characteristics of emergency passive residual heat removal system in HPR1000
    Sun, D. C.
    Xi, Z.
    Li, Y.
    Zan, Y. F.
    Xiong, W. Y.
    Li, P. Z.
    Zhuo, W. B.
    PROGRESS IN NUCLEAR ENERGY, 2018, 103 : 1 - 7
  • [35] Development of a thermal-hydraulic analysis code for primary system of an integrated small modular pressurized water reactor
    Wang, Dongqing
    Chen, Huandong
    Chen, Jiayue
    Zhan, Dekui
    Xia, Shaoxiong
    ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [36] Experimental study on start-up and steady state characteristics of passive residual heat removal system for 2 MW molten salt reactor
    Chen, Kailun
    Meng, Zhaoming
    Yan, Changqi
    Fan, Guangming
    Ding, Tao
    ENERGY, 2018, 147 : 826 - 838
  • [37] The study of passive cooling system assisted with separate heat pipe for decay heat removal in spent fuel pool
    Lai, Kun
    Wang, Wen
    Yi, Chongchong
    Kuang, Yiwu
    Ye, Cheng
    ANNALS OF NUCLEAR ENERGY, 2018, 111 : 523 - 535
  • [38] The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system
    Xi, Mengmeng
    Wu, Yingwei
    Tian, Wenxi
    Su, G. H.
    Qiu, Suizheng
    PROGRESS IN NUCLEAR ENERGY, 2015, 85 : 573 - 587
  • [39] Research on fluctuation attenuation and optimization of passive residual heat removal system based on spring vibrator
    Wang, Sipeng
    Chen, Jin
    Kang, Zehang
    Du, Peng
    Su, Zhen
    Zhuang, Kun
    PROGRESS IN NUCLEAR ENERGY, 2025, 180
  • [40] TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
    Al-Yahia, Omar S.
    Clifford, Ivor
    Nikitin, Konstantin
    Liu, Prosper
    Ferroukhi, Hakim
    NUCLEAR ENGINEERING AND DESIGN, 2023, 406