Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2014, Vol. 25 ›› Issue (3): 030601 doi: 10.13538/j.1001-8042/nst.25.030601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Numerical analysis of pressure load in a PWR cavity in an ex-vessel steam explosion

ZHONG Ming-Jun, LI Zhi-Gang, LIN Meng, HUANG Xi, ZHOU Yuan, YANG Yan-Hua   

  1. 1School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
  • Contact: ZHOU Yuan E-mail:zhouyuan1911@126.com
  • Supported by:

    Supported by National Science and Technology Major Project of China (No. 2011ZX06004-008)

PDF ShareIt Export Citation
ZHONG Ming-Jun, LI Zhi-Gang, LIN Meng, HUANG Xi, ZHOU Yuan, YANG Yan-Hua. Numerical analysis of pressure load in a PWR cavity in an ex-vessel steam explosion.Nuclear Science and Techniques, 2014, 25(3): 030601     doi: 10.13538/j.1001-8042/nst.25.030601

Abstract:

Ex-vessel steam explosion may happen as a result of melting core falling into the reactor cavity after failure of the reactor vessel and interaction with the coolant in the cavity pool. It can cause the formation of shock waves and production of missiles that may endanger surrounding structures. Ex-vessel steam explosion energetics is affected strongly by three dimensional (3D) structure geometry and initial conditions. Ex-vessel steam explosions in a typical pressurized water reactor cavity are analyzed with the code MC3D, which is developed for simulating fuel-coolant interactions. The reactor cavity with a venting tunnel is modeled based on 3D cylindrical coordinate. A study was performed with parameters of the location of molten drop release, break size, melting temperature, cavity water subcooling, triggering time and explosion position, so as to establish parameters’ influence on the fuel-coolant interaction behavior, to determine the most challenging cases and to estimate the expected pressure loadings on the cavity walls. The most dangerous case shows the pressure loading is above the capacity of a typical reactor cavity wall.

Key words: Steam explosion, Fuel coolant interaction, Numerical analysis, Severe accident