Effect of corium jet fragmentation model on ex-vessel steam explosion calculation for advanced PWR

被引:0
作者
Chen Q.-Y. [1 ]
Wang H. [1 ]
Shi X.-Y. [1 ]
机构
[1] China Nuclear Power Engineering Co., Ltd., Beijing
来源
Yuanzineng Kexue Jishu | / 5卷 / 812-818期
关键词
Corium drop; Jet fragmentation; Premixing; Steam explosion;
D O I
10.7538/yzk.2016.50.05.0812
中图分类号
学科分类号
摘要
In the ex-vessel steam explosion calculation, the corium jet fragmentation model affects the premixing parameters and phenomena such as generation rate and size of corium drops, the distribution of corium drops, corium drop solidification, void fraction and so on, and then has influence on the strength of steam explosion. Different corium jet fragmentation models (CONST model and KHF model) were used to calculate the ex-vessel steam explosion for advanced PWR based on MC3D V3.8 code in order to discuss the effect of corium jet fragmentation model on ex-vessel steam explosion calculation. It is shown that these two models give similar premixing conditions. At the time of melt bottom contact, explosion criteria of these two models are almost the same, so the strength of explosion triggering has a little difference, which indicates that these two models have a little influence on steam explosion calculation if the time of corium bottom contact is chosen as triggering time for advanced PWR. On the defined condition for advanced PWR, the maximum pressure near cavity wall is 20 MPa in approximation and the maximum impulse on cavity wall is smaller than 0.2 MPa·s. © 2016, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:812 / 818
页数:6
相关论文
共 6 条
  • [1] Meignen R., Comparative review of FCI computer models used in the OECD-SERENA program, Proceedings of ICAPP'05, (1998)
  • [2] Hong S.W., Piluso P., Leskovar M., Et al., Status of the OECD-SERENA project for the resolution of ex-vessel steam explosion risk, Journal of Energy and Power Engineering, 7, pp. 423-431, (2013)
  • [3] Leskovar M., Ursic M., Estimation of ex-vessel steam explosion pressure loads, Nuclear Engineering and Design, 239, pp. 2444-2458, (2009)
  • [4] Thakre S., Ma W.M., Simulations of ex-vessel fuel coolant interactions in a nordic BWR using MC3D code, (2013)
  • [5] Meignen R., Picchi S., Raverdy B., MC3D version 3.8: Desription of the physical models of the PREMIXING application, (2014)
  • [6] Picchi S., Raverdy B., Lamome J., MC3D version 3.8 user's guide, (2014)