Estimation of ex-vessel steam explosion pressure loads

被引:41
|
作者
Leskovar, Matjaz [1 ]
Ursic, Mitja [1 ]
机构
[1] Jozef Stefan Inst, SI-1000 Ljubljana, Slovenia
关键词
VAPOR EXPLOSIONS; FAILURE; TESTS; WATER;
D O I
10.1016/j.nucengdes.2009.07.023
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
An ex-vessel steam explosion may occur when, during a severe reactor accident, the reactor vessel fails and the molten core pours into the water in the reactor cavity. A steam explosion is a fuel coolant interaction process where the heat transfer from the melt to water is so intense and rapid that the timescale for heat transfer is shorter than the timescale for pressure relief. This can lead to the formation of shock waves and production of missiles that may endanger surrounding structures. A strong enough steam explosion in a nuclear power plant could jeopardize the containment integrity and so lead to a direct release of radioactive material to the environment. In this article, different scenarios of ex-vessel steam explosions in a typical pressurized water reactor cavity are analyzed with the code MC3D, which is being developed for the simulation of fuel-coolant interactions. A parametric study was performed varying the location of the melt release (central, right and left side melt pour), the cavity water subcooling, the primary system overpressure at vessel failure and the triggering time for explosion calculations. The main purpose of the study was to establish the influence of the varied parameters on the fuel-coolant interaction behaviour, to determine the most challenging cases and to estimate the expected pressure loadings on the cavity walls. For the most explosive central, right side and left side melt pour scenarios a detailed analysis of the explosion simulation results was performed. The study shows that for some ex-vessel steam explosion scenarios higher pressure loads are predicted than obtained in the OECD programme SERENA phase 1. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:2444 / 2458
页数:15
相关论文
共 50 条
  • [21] An Evaluation of the Ex-vessel Steam Explosion Load Against TROI Experimental Results
    Park, Ik-Kyu
    Kim, Jong-Hwan
    Min, Beong-Tae
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS B, 2009, 33 (08) : 622 - 628
  • [22] COMPUTATIONAL ANALYSIS OF PRESSURE LOADING AND IMPULSE DISTRIBUTION IN THE REACTOR CAVITY DURING THE PROCESS OF EX-VESSEL STEAM EXPLOSION
    Huang Xi
    Wang Xi
    Yang Yan-hua
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 3, 2011, : 497 - 504
  • [23] Development of a surrogate model for analysis of ex-vessel steam explosion in Nordic type BWRs
    Grishchenko, Dmitry
    Basso, Simone
    Kudinov, Pavel
    NUCLEAR ENGINEERING AND DESIGN, 2016, 310 : 311 - 327
  • [24] Evaluation of containment failure probability by ex-vessel steam explosion in Japanese LWR plants
    Moriyama, Kiyofumi
    Takagi, Seiji
    Muramatsu, Ken
    Nakamura, Hideo
    Maruyama, Yu
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2006, 43 (07) : 774 - 784
  • [25] Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor
    Leskovar, Matjaz
    Ursic, Mitja
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (01) : 72 - 86
  • [26] Effect of corium jet fragmentation model on ex-vessel steam explosion calculation for advanced PWR
    Chen Q.-Y.
    Wang H.
    Shi X.-Y.
    Yuanzineng Kexue Jishu, 5 (812-818): : 812 - 818
  • [27] Numerical simulation of ex-vessel steam explosion based on 1000 MW level PWR nuclear power plant
    Zhong, Mingjun
    Lin, Meng
    Zhang, Zhengming
    Yang, Yanhua
    Hedongli Gongcheng/Nuclear Power Engineering, 2014, 35 (04): : 43 - 47
  • [28] The plant-specific uncertainty analysis for an ex-vessel steam explosion-induced pressure load using a TEXAS-SAUNA coupled system
    Ahn, Kwang-Il
    Park, Sun-Hee
    Kim, Hee-Dong
    Park, Hyun Sun
    NUCLEAR ENGINEERING AND DESIGN, 2012, 249 : 400 - 412
  • [29] Investigation on energetics of ex-vessel vapor explosion based on spontaneous nucleation fragmentation
    Liu, J
    Koshizuka, S
    Oka, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (01) : 31 - 39
  • [30] The vulcano ex-vessel programme
    Cognet, G
    Laffont, G
    Jegou, C
    Pierre, J
    Journeau, C
    Cranga, M
    Sudreau, F
    Ramacciotti, M
    PROCEEDINGS OF THE OECD WORKSHOP ON EX-VESSEL DEBRIS COOLABILITY, 2000, 6475 : 156 - 168