Dependability Enhancement of Reactor Containment in Safety Critical Nuclear Power Plants

被引:0
|
作者
Cho, Chi-Shiang [1 ]
Chung, Wei-Ho [2 ]
Gao, Deyun [3 ]
Zhang, Hongke [3 ]
Kuo, Sy-Yen [1 ]
机构
[1] Natl Taiwan Univ, Dept Elect Engn, Taipei 106, Taiwan
[2] Res Ctr Informat Technol Innovat Acad Sinica, Taipei, Taiwan
[3] Beijing Jiaotong Univ, Coll Elect & Informat Engn, Beijing 100044, Peoples R China
基金
中国国家自然科学基金;
关键词
containment; leakage rate; ILRT; V&V;
D O I
10.1109/PRDC.2011.24
中图分类号
TP3 [计算技术、计算机技术];
学科分类号
0812 ;
摘要
The use of nuclear energy to generate electric power is crucial in meeting the high energy demand of modern economy. The dependability of nuclear power plants has been a critical issue and the reactor containment is the most important safety structure acting as a barrier against the release of radioactive material to the environment. In this paper, we propose a practical framework for design, implementation, and V&V to enhance the dependability of reactor containment through an integrated leakage rate test.
引用
收藏
页码:129 / 134
页数:6
相关论文
共 50 条
  • [41] Cyberphysical Security and Dependability Analysis of Digital Control Systems in Nuclear Power Plants
    Cho, Chi-Shiang
    Chung, Wei-Ho
    Kuo, Sy-Yen
    IEEE TRANSACTIONS ON SYSTEMS MAN CYBERNETICS-SYSTEMS, 2016, 46 (03): : 356 - 369
  • [42] REVIEW OF 1972 SAFETY-RELATED OCCURRENCES IN NUCLEAR-REACTOR POWER-PLANTS
    SCOTT, RL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 : 29 - 29
  • [43] NEW GENERATION OF BOILING-WATER-REACTOR NUCLEAR-POWER-PLANTS OF INCREASED SAFETY
    MITYAEV, YI
    TOKAREV, YI
    SOKOLOV, IN
    PAKKH, EE
    ABRAMOV, VI
    ATOMIC ENERGY, 1992, 73 (01) : 558 - 563
  • [44] Enhanced reactor core design and safety evaluation for the final cycles of Belgian nuclear power plants
    Van Parys, Ruben
    Haedens, Maxime
    Schneidesch, Christophe
    Zhang, Jinzhao
    Meert, Arnaud
    NUCLEAR ENGINEERING AND DESIGN, 2024, 421
  • [45] Design of safety critical and control systems of Nuclear Power Plants using Petri nets
    Singh, Pooja
    Singh, Lalit Kumar
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2019, 51 (05) : 1289 - 1296
  • [46] Verification of safety critical and control systems of Nuclear Power Plants using Petri nets
    Singh, Pooja
    Singh, Lalit
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 584 - 592
  • [47] Qualification of Hardware Description Language Designs for Safety Critical Applications in Nuclear Power Plants
    John, Ajith K.
    Bhattacharjee, A. K.
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2020, 67 (03) : 502 - 507
  • [48] Global concern for nuclear safety spurs analysis of reactor accident containment system
    不详
    MATERIALS & DESIGN, 1999, 20 (04): : 207 - 209
  • [49] Global concern for nuclear safety spurs analysis of reactor accident containment system
    不详
    MATERIALS & DESIGN, 1999, 20 (01): : 51 - 53
  • [50] Dependability of safety-critical systems
    Buja, G
    Castellan, S
    Menis, R
    Zuccollo, A
    2004 IEEE INTERNATIONAL CONFERENCE ON INDUSTRIAL TECHNOLOGY (ICIT), VOLS. 1- 3, 2004, : 1561 - 1566