SIMULATION RESEARCH ON THERMAL-HYDRAULIC PERFORMANCE OF A NATURAL CIRCULATION INTEGRATED PRESSURIZED WATER REACTOR

被引:0
|
作者
Zhao, Yanan [1 ]
Peng, Minjun [1 ]
Xia, Genglei [1 ]
Lv, Lianxin [1 ]
机构
[1] Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin, Heilongjiang, Peoples R China
基金
美国国家科学基金会;
关键词
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
As an effective measure to improve the reactor's inherent safety feature, natural circulation is widely used in current integrated reactor design. The thermal-hydraulic performance of a flashing-driven nature circulation integrated pressurized water reactor (NC-IPWR) is studied, by taking IP100 reactor as reference. The simulation model of the reactor is established by RELAP5 code. A control system is designed based on the operation characteristics of the reactor. Both steady-state and dynamic performance of the reactor are analyzed and the rationality of the control strategy is verified in this work. The results demonstrate the operation characteristics of the IP 100 reactor, and the dynamic performance of the reactor during power variation is discussed in detail. The control strategy that keeps the steam pressure and the core outlet temperature constant shows good performance under normal operation conditions. The obtained analysis results are significant for deeper understanding and improving the operation characteristics of the IP 100 reactor.
引用
收藏
页数:8
相关论文
共 50 条
  • [1] THERMAL-HYDRAULIC CONSTRAINTS ON WATER-COOLED RESEARCH REACTOR PERFORMANCE
    GAMBILL, WR
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 1986, 249 (01): : 53 - 57
  • [2] 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
    [J]. ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [3] Review on Thermal-hydraulic Characteristic Research in Passive Cooling Water Tank of Large Advanced Pressurized Water Reactor
    Lu, Daogang
    Zhang, Yuhao
    Li, Xiangbin
    Zhou, Shiliang
    Cao, Qiong
    Sui, Danting
    Wang, Han
    [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (10): : 1930 - 1940
  • [4] Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor
    Wu, Y. W.
    Su, G. H.
    Qiu, S. Z.
    Zhuang, C. J.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (01) : 112 - 122
  • [5] An improved core thermal-hydraulic model for coastdown transient in pressurized water reactor
    Ahmad, Idrees
    Arshad, Saad
    Tahir, Sajjad
    Nadeem, Qaisar
    Samee, Abdus
    [J]. PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART A-JOURNAL OF POWER AND ENERGY, 2018, 232 (04) : 416 - 424
  • [6] Numerical simulation of thermal-hydraulic characteristics in a closed natural circulation system
    Wang, Qiang
    Gao, Puzhen
    Xu, Yuting
    Zhang, Yinxing
    Lin, Yuqi
    Wang, Zhongyi
    [J]. THIRD INTERNATIONAL CONFERENCE ON ENERGY ENGINEERING AND ENVIRONMENTAL PROTECTION, 2019, 227
  • [7] Analysis of natural circulation operational characteristics for integrated pressurized water reactor
    Xia, G. L.
    Su, G. H.
    Peng, M. J.
    [J]. ANNALS OF NUCLEAR ENERGY, 2016, 92 : 304 - 311
  • [8] Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor
    Khan, Salah Ud-Din
    Peng, Minjun
    Khan, Shahab Ud-Din
    [J]. INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2013, 37 (13) : 1709 - 1717
  • [9] PRESSURIZED WATER-REACTOR THERMAL-HYDRAULIC CORE ANALYSIS WITH THE FLICA COMPUTER CODE
    RAYMOND, P
    SPINDLER, B
    LENAIN, R
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1990, 124 (03) : 299 - 313
  • [10] A RELAP5 MODEL FOR THE THERMAL-HYDRAULIC ANALYSIS OF A TYPICAL PRESSURIZED WATER REACTOR
    Agamy, Said
    Metwally, Adul Mohsen
    Al-Ramady, Amir Mohammad
    Elaraby, Sayed Mohamed
    [J]. THERMAL SCIENCE, 2010, 14 (01): : 79 - 88