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] A CONCEPT OF PASSIVE SAFETY PRESSURIZED-WATER REACTOR SYSTEM WITH INHERENT MATCHING NATURE OF CORE MEAT GENERATION AND HEAT REMOVAL
    MURAO, Y
    ARAYA, F
    IWAMURA, T
    OKUMURA, K
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1995, 32 (09) : 855 - 867
  • [32] EFFECT OF A DIVIDED WETWELL ON HEAT REMOVAL CAPABILITY OF THE WATER WALL TYPE PASSIVE CONTAINMENT COOLING SYSTEM
    FUJII, T
    KATAOKA, Y
    MURASE, M
    SUMIDA, I
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1995, 32 (01) : 18 - 29
  • [33] EXPERIMENTAL-STUDY ON HEAT REMOVAL CHARACTERISTICS FOR WATER WALL TYPE PASSIVE CONTAINMENT COOLING SYSTEM
    KATAOKA, Y
    FUJII, T
    MURASE, M
    TOMINAGA, K
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1994, 31 (10) : 1043 - 1052
  • [34] SAFETY ANALYSIS OF INCREASE IN HEAT REMOVAL FROM REACTOR COOLANT SYSTEM WITH INADVERTENT OPERATION OF PASSIVE RESIDUAL HEAT REMOVAL AT NO-LOAD CONDITIONS
    Shao, Ge
    Cao, Xuewu
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2015, 47 (04) : 434 - 442
  • [35] Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor
    Wang, Chenglong
    Zhang, Dalin
    Qiu, Suizheng
    Tian, Wenxi
    Wu, Yingwei
    Su, Guanghui
    NUCLEAR ENGINEERING AND DESIGN, 2013, 265 : 691 - 700
  • [36] Conceptual design and analysis of a passive residual heat removal system for a 10 MW molten salt reactor experiment
    Sun, Lu
    Sun, Licheng
    Yan, Changqi
    Fa, Dan
    Wang, Naxiu
    PROGRESS IN NUCLEAR ENERGY, 2014, 70 : 149 - 158
  • [37] Heat transfer and flow characteristics of a cooling thimble in a molten salt reactor residual heat removal system
    Yang, Zonghao
    Meng, Zhaoming
    Yan, Changqi
    Chen, Kailun
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (08) : 1617 - 1628
  • [38] The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR
    XIAO Ze-Jun1
    2Xi’an Jiaotong University
    NuclearScienceandTechniques, 2006, (05) : 301 - 307
  • [39] Transient thermal-hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor
    Wang, Chenglong
    Yang, Yupeng
    Liu, Minghao
    Zhang, Dalin
    Qiu, Suizheng
    Su, G. H.
    Tian, Wenxi
    Deng, Jian
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 45 (02) : 1599 - 1612