Analysis codes of severe accident

被引:0
|
作者
Lang, Ming-Gang [1 ]
Gao, Zu-Ying [1 ]
机构
[1] Inst. of Nucl. Energy Technol., Tsinghua Univ., Beijing 100084, China
来源
关键词
Accident prevention - Containment vessels - Core disruptive accidents - Melting;
D O I
暂无
中图分类号
学科分类号
摘要
Based on the progression, the phenomena in a severe accident are classified into three phases: core degradation, vessel melt-through and the failure of the containment, and the fission products were released there after. The codes used for severe accident analysis fell into two categories: integrated codes and mechanistic code. Integrated codes aimed at calculating complete accident sequences. Mechanistic codes pay more attention to details and often considered a particular part or phase of an accident sequence. Integrated codes STCP, MELCOR, ASTEC and mechanistic codes RELAP5/SCDAP, VICTORIA, CONTAIN are described.
引用
收藏
页码:46 / 50
相关论文
共 50 条
  • [21] Severe Accident Analysis in Nuclear Power Plants
    Espinosa-Paredes, Gilberto
    Batet, Lluis
    Nunez-Carrera, Alejandro
    Sugimoto, Jun
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [22] CURRENT STATUS OF BWR SEVERE ACCIDENT ANALYSIS
    KOBAYASHI, K
    ISHIGAMI, T
    ASAKA, H
    AKIMOTO, M
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1985, 27 (12): : 1093 - 1101
  • [23] A SYSTEMATIC APPROACH FOR SEVERE ACCIDENT UNCERTAINTY ANALYSIS
    Hoseyni, Seyed Mohsen
    Pourgol-Mohammad, Mohammad
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016,
  • [24] PREDICTION OF HYDROGEN DISTRIBUTION UNDER SEVERE ACCIDENT CONDITIONS WITH CFD AND LUMPED PARAMETER CODES
    Szabo, Tobias
    Benz, Stefan
    Kretzschmar, Frank
    Royl, Peter
    Jordan, Thomas
    PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 3, 2012, : 401 - 410
  • [25] ANALYSIS OF A HYPOTHETICAL LMFBR ACCIDENT USING CODES FUTURE AND FRUMP
    GROSBERG, AJ
    HEAD, JL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 424 - 426
  • [26] ADJOINT-BASED SENSITIVITY ANALYSIS FOR REACTOR ACCIDENT CODES
    PARKS, CV
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 283 - 285
  • [27] Expert judgment for uncertainty analysis of european accident consequence codes
    Cooke, Roger M.
    van der Weide, Hans
    Proceedings of the World Congress on Expert Systems, 1991,
  • [28] REVIEW OF TRANSIENT ANALYSIS AND ACCIDENT SIMULATION CODES FOR NUCLEAR REACTOR
    Qiu, Xinze
    Liu, Tao
    Tong, Jiejuan
    Zhang, Liguo
    Wu, Yuzeng
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
  • [29] Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials
    Merrill, Brad J.
    Bragg-Sitton, Shannon M.
    Humrickhouse, Paul W.
    NUCLEAR ENGINEERING AND DESIGN, 2017, 315 : 170 - 178
  • [30] Severe accident analysis to verify the effectiveness of severe accident management guidelines for large pressurized heavy water reactor
    Gokhale, O. S.
    Mukhopadhyay, D.
    Lele, H. G.
    Singh, R. K.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 278 : 360 - 366