SIMULATION OF THE OPERATION IN PASSIVE MODE OF REACTOR CAVITY COOLING SYSTEM OF HIGH-TEMPERATURE GAS-COOLED REACTOR

被引:0
|
作者
Matev, Alex
机构
关键词
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The Reactor Cavity Cooling System (RCCS) of a High-Temperature Gas-Cooled Reactor (HTGR) may be required to operate in a "passive" mode when heat is removed from the reactor cavity by letting RCCS water inventory to boil off to atmosphere. Overheating of the reactor cavity concrete walls may lead to a failure of the reactor vessel support structures and its shift off the design position. Dislocation of the massive reactor vessel may cause multiple ruptures of pipes, connected to both the upper and lower vessel heads. Such breaks of the reactor pressure boundary will enable air ingress into the core, fuel oxidation and overheating, and possible release of fission products into the environment. The computer code TINTE [3] was used to simulate a "Depressurized Loss Of Flow Circulation (DLOFC) Without Reactor Scram" accident and determine from its results the magnitude, axial distribution, and time dependence of the heat flux on the RCCS cooling panels. The computer code RELAP [41 was used to model the operation in "passive" mode of one RCCS train, consisting of a tank and four standpipes. This paper describes the application of both RELAP and TINTE for the simulation of RCCS operation in passive mode. The main conclusion from this analysis is that the proposed way of using both codes is suitable to perform scoping studies and design evaluation of RCCS of a pebble-bed HTGR.
引用
收藏
页码:507 / 514
页数:8
相关论文
共 50 条
  • [1] Experiments on a water pool-type reactor cavity cooling system in a high-temperature gas-cooled reactor
    Cho, Hyoung Kyu
    Cho, Yun Je
    Kim, Moon Oh
    Park, Goon Cherl
    NUCLEAR TECHNOLOGY, 2007, 159 (01) : 39 - 58
  • [3] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Yang Chen
    Jiang-hong You
    Zhi-jiang Shao
    Ke-xin Wang
    Ji-xin Qian
    Journal of Zhejiang University-SCIENCE A, 2011, 12 : 567 - 574
  • [4] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Chen, Yang
    You, Jiang-hong
    Shao, Zhi-jiang
    Wang, Ke-xin
    Qian, Ji-xin
    JOURNAL OF ZHEJIANG UNIVERSITY-SCIENCE A, 2011, 12 (07): : 567 - 574
  • [5] Simultaneous approach for simulation of a high-temperature gas-cooled reactor
    Yang CHENJianghong YOUZhijiang SHAOKexin WANGJixin QIANState Key Laboratory of Industrial Control TechnologyZhejiang UniversityHangzhou China
    Journal of Zhejiang University-Science A(Applied Physics & Engineering), 2011, (07) : 567 - 574
  • [6] MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR
    SHEPHERD, LR
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1988, 27 (01): : 37 - 47
  • [7] HIGH-TEMPERATURE GAS-COOLED REACTOR MATERIALS
    不详
    NUCLEAR TECHNOLOGY, 1984, 66 (01) : 11 - 11
  • [8] FUEL CYCLE IN GAS-COOLED HIGH-TEMPERATURE REACTOR
    MERZ, E
    CHEMIKER-ZEITUNG, 1977, 101 (02): : 81 - 91
  • [9] An operation optimization of cooling system for reactor shutdown in pebble bed gas-cooled reactor
    Liu, Junfeng
    Wang, Chenglong
    Qiu, Suizheng
    Wu, Shifa
    Wang, Boyuan
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2025,
  • [10] HIGH-TEMPERATURE GAS-COOLED BREEDER REACTOR (HTBR)
    YELLOWLEES, JM
    KRAHE, A
    OPPENHEIM, C
    VANSTEENBERGHE, T
    VIEIDER, G
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 704 - 707