A design of in-plant electric power system for the HTR-10

被引:1
|
作者
Sun, WD [1 ]
Zhou, SX [1 ]
机构
[1] Tsing Hua Univ, Inst Nucl Energy Technol, Beijing 100084, Peoples R China
关键词
D O I
10.1016/S0029-5493(02)00194-2
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
The design of in-plant electric power system for the 10 MW high-temperature gas-cooled reactor-test module (HTR-10) has taken into full consideration the feature of good inherent safety existing with the HTR-10 and has adopted a scheme different from those adopted for ordinary nuclear power plants. This paper gives an introduction to the structure, design objectives of in-plant electric power system, the designing schemes of different subsystems and the main equipment. The result of system test and operation show that the design can meet the demand for power reply from the reactor under any operational conditions. At the same time, it can reduce the system cost and improve the reliability and the safety of the system. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:227 / 232
页数:6
相关论文
共 50 条
  • [41] Error analysis and experimental research of HTR-10 burnup measurement system
    Wang, Jun-Ling
    Chen, Xiao-Ming
    Ma, Tao
    Xia, Bing
    Huang, Peng
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (04): : 614 - 618
  • [42] Digital signal processing on the fuel ball counting system for HTR-10
    Li, H
    Li, F
    NUCLEAR ENGINEERING AND DESIGN, 2003, 222 (2-3) : 139 - 146
  • [43] Study on network communication of the simulation and online assistance system of HTR-10
    Zhou, J
    Dong, YJ
    PROCEEDINGS OF THE WORLD ENGINEERS' CONVENTION 2004, VOL A, NETWORK ENGINEERING AND INFORMATION SOCIETY, 2004, : 163 - 167
  • [44] HTR-10装料前的调试
    苏庆善
    王瑞偏
    陈华
    胡守印
    梁锡华
    孙栓樑
    核动力工程, 2001, (06) : 538 - 541
  • [45] Gas transportation of fuel element in HTR-10
    Liu, Ji-Guo
    Liang, Xi-Hua
    Huang, Peng
    Hedongli Gongcheng/Nuclear Power Engineering, 2001, 22 (06): : 526 - 529
  • [46] Source Term Analysis of Tritium in HTR-10
    Xu, Yi
    Li, Hong
    Xie, Feng
    Cao, Jianzhu
    Tong, Jiejuan
    FUSION SCIENCE AND TECHNOLOGY, 2017, 71 (04) : 671 - 678
  • [47] Thermodynamic analysis of thermal efficiency of HTR-10 hydrogen production system
    Yin, Huaqiang
    Jiang, Shengyao
    Zhang, Youjie
    Ju, Huaiming
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (10) : 1188 - 1193
  • [48] EXPERIMENTAL STUDY ON PERFORMANCE IMPROVEMENT OF HTR-10 HELIUM PURIFICATION SYSTEM
    Wang, Fangfang
    Wei, Liqiang
    Kang, Tianyu
    Hu, Chuangguo
    Xie, Feng
    Chen, Xiaoming
    Shi, Lei
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 1, 2021,
  • [49] HTR-10燃耗自动测量系统
    马涛
    胡守印
    梁锡华
    黄鹏
    核动力工程, 2007, (03) : 56 - 60
  • [50] Safety functions and component classification for the HTR-10
    Wu, ZW
    Xi, SR
    NUCLEAR ENGINEERING AND DESIGN, 2002, 218 (1-3) : 103 - 110