Experimental Study of a Stoppage Natural Circulation during a Nuclear Heating Reactor LOCA

被引:0
|
作者
博金海
张佑杰
姜胜耀
机构
基金
中国国家自然科学基金;
关键词
Nuclear Heating Reactor (NHR); Loss of Coolant Accident (LOCA); natural circulation; safety; stability;
D O I
暂无
中图分类号
TL41 [核反应堆:按用途分];
学科分类号
082703 ;
摘要
The 5MW nuclear heating reactor is an integral natural circulation reactor. The rupture of the coolant penetrating tube is a typical accident causing coolant loss. When the water level drops down to the upper edge of the inlet of the heat exchanger, the natural circulation stops. This influences the core cooling and the stability of the main loop. A series of tests showed that there is a stable drop of pressure, and the heated element temperature is not too high to cause burnout. But the backward flow or flow oscillation in the primary coolant circuit occurs when the flow breaks completely in the end. The whole flow process is described and the mechanism is discussed.
引用
收藏
页码:89 / 92
页数:4
相关论文
共 50 条
  • [41] Irregular pentagon loop for nuclear reactor natural circulation system test apparatus
    Hariyanto, Duwi
    Permana, Sidik
    Waris, Abdul
    Mustari, Asril Pramutadi Andi
    Kinoshita, Motoyasu
    Aji, Indarta Kuncoro
    Maulana, Alan
    Setiadipura, Topan
    Nuclear Engineering and Design, 2024, 416
  • [42] EXPERIMENTAL SIMULATION OF TRANSITIONS BETWEEN FORCED CIRCULATION AND NATURAL CIRCULATION WITH NUCLEAR REACTIVITY FEEDBACK
    Chen, Hanying
    Xia, Linzhong
    Gao, Puzhen
    Tan, Sichao
    Yuan, Hongsheng
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 1, 2021,
  • [43] EXPERIMENTAL STUDY OF TEMPERATURE AND HEATING POWER VARIATIONS ON NATURAL CIRCULATION FLOW PHENOMENA IN A CLOSED RECTANGULAR LOOP WITH SINGLE HEATING CHANNEL
    Bello, Solomon
    Gao, Puzhen
    Lin, Yuqi
    PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 3, 2020,
  • [44] Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor
    Choi, Won Jun
    Park, Jae Hyung
    Lee, Juhyeong
    Im, Jihun
    Cho, Yunsik
    Kim, Yonghee
    Kim, Sung Joong
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (03) : 1002 - 1012
  • [45] NATURAL CIRCULATION, SODIUM-COOLED REACTOR FEASIBILITY STUDY
    KLEIN, AC
    WEISMAN, J
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 335 - 336
  • [46] Experimental Simulation on Transit Process of the 5MW Nuclear Heating Reactor
    姜胜耀
    吴莘馨
    姚梅生
    博金海
    吴少融
    张佑杰
    清华大学学报(自然科学版), 1996, (11) : 49 - 54
  • [47] THEORETICAL INVESTIGATION OF DYNAMIC NATURAL CIRCULATION INSTABILITIES IN AN AST-500 DISTRICT HEATING REACTOR
    ROHDE, U
    KERNENERGIE, 1987, 30 (09): : 367 - 371
  • [48] AN EXPERIMENTAL-STUDY OF THE EFFECT OF STEAM COOLING DURING A BWR LOCA
    YAMADA, K
    NAGASAKA, H
    WATANABE, T
    GOMYO, T
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 315 - 317
  • [49] An experimental study on thermal circulation driven by horizontal differential heating
    Wang, W
    Huang, RX
    JOURNAL OF FLUID MECHANICS, 2005, 540 : 49 - 73
  • [50] Conversion from single to two-phase operation in a natural circulation nuclear reactor
    Jiang, SY
    Zhang, YJ
    Bo, JH
    Wang, F
    KERNTECHNIK, 1998, 63 (03) : 132 - 138