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：
Hedongli Gongcheng/Nuclear Power Engineering | 2002年 / 23卷 / 02期
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
  • [41] Comparison of Severe Accident Results by Using MAAP5 and MAAP4 codes
    Wang, Te-Chuan
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 4 PTS A AND B, 2011, : 27 - 36
  • [42] Comparison of severe accident results among SCDAP/RELAP5, MAAP, and MELCOR codes
    Wang, TC
    Wang, SJ
    Teng, JT
    NUCLEAR TECHNOLOGY, 2005, 150 (02) : 145 - 152
  • [43] Preliminary Analysis of Hydrogen Distribution during Severe Accident induced by Loss of Coolant Accident
    Wang, Di
    Cao, Xuewu
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 8, 2017,
  • [44] Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis
    Farmer, M. T.
    Bunt, R.
    Corradini, M.
    Ellison, P.
    Francis, M.
    Gabor, J.
    Gauntt, R.
    Henry, C.
    Linthicum, R.
    Luangdilok, W.
    Lutz, R.
    Paik, C.
    Plys, M.
    Rabiti, C.
    Rempe, J.
    Robb, K.
    Wachowiak, R.
    NUCLEAR SCIENCE AND ENGINEERING, 2016, 184 (03) : 293 - 304
  • [45] PROBABILISTIC ACCIDENT ANALYSIS WITH DETERMINISTIC CODES USING STOCHASTICALLY VARIABLE PARAMETERS
    ABRAMSON, PB
    HUMMEL, HH
    GELBARD, EM
    PIZZICA, PA
    SIENICKI, JJ
    NUCLEAR SCIENCE AND ENGINEERING, 1978, 66 (01) : 14 - 23
  • [46] Uncertainty analysis on early health effects modeling in accident consequence codes
    Kraan, B
    Cooke, R
    Goossens, L
    PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT (PSAM 4), VOLS 1-4, 1998, : 1077 - 1082
  • [47] SEVERE ACCIDENT TECHNOL
    VOGELSANG, WF
    NUCLEAR TECHNOLOGY, 1993, 101 (03) : 253 - 253
  • [48] SEVERE ACCIDENT BEHAVIOR
    DENNING, RS
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1986, 192 : 29 - NUCL
  • [49] Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions
    Wu, Xiaoli
    Li, Wei
    Wang, Yang
    Zhang, Yapei
    Tian, Wenxi
    Su, Guanghui
    Qiu, Suizheng
    Liu, Tong
    Deng, Yongjun
    Huang, Heng
    ANNALS OF NUCLEAR ENERGY, 2015, 80 : 1 - 13
  • [50] SEVERE ACCIDENT ANALYSIS OF A FLOATING NUCLEAR POWER PLANT AFTER STATION BALCK OUT ACCIDENT
    Li, Longze
    Chao, Fei
    He, Chuan
    Tai, Yun
    Qiu, Jinrong
    Yao, Shiwei
    Yang, Wen
    Wang, Jue
    Hou, Xiaofan
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 3, 2021,
12345