SEINA: A two-dimensional steam explosion integrated analysis code

被引:2
|
作者
Wu, Liangpeng [1 ]
Sun, Ruiyu [1 ]
Chen, Ronghua [1 ]
Tian, Wenxi [1 ]
Qiu, Suizheng [1 ]
Su, G. H. [1 ]
机构
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Shaanxi Key Lab Adv Nucl Energy & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
关键词
Severe accidents; FCI; Steam explosion; Numerical simulation; REACTORS; MODEL;
D O I
10.1016/j.net.2022.04.025
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
In the event of a severe accident, the reactor core may melt due to insufficient cooling. the high -temperature core melt will have a strong interaction (FCI) with the coolant, which may lead to steam explosion. Steam explosion would pose a serious threat to the safety of the reactors. Therefore, the study of steam explosion is of great significance to the assessment of severe accidents in nuclear reactors. This research focuses on the development of a two-dimensional steam explosion integrated analysis code called SEINA. Based on the semi-implicit Euler scheme, the three-phase field was considered in this code. Besides, the influence of evaporation drag of melt and the influence of solidified shell during the process of melt droplet fragmentation were also considered. The code was simulated and validated by FARO L-14 and KROTOS KS-2 experiments. The calculation results of SEINA code are in good agreement with the experimental results, and the results show that if the effects of evaporation drag and melt solidification shell are considered, the FCI process can be described more accurately. Therefore, it is proved that SEINA has the potential to be a powerful and effective tool for the analysis of steam ex-plosions in nuclear reactors.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:3909 / 3918
页数:10
相关论文
共 50 条
  • [1] Probability analysis of ex-vessel steam explosion induced pressure load based on analysis code SEINA
    Wu, Liangpeng
    Sun, Ruiyu
    Chen, Ronghua
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2022, 176
  • [2] A TWO-DIMENSIONAL EMPIRICAL-MODEL FOR ANALYZING STEAM EXPLOSION EXPERIMENTS
    CORRADINI, ML
    MITCHELL, DE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 454 - 456
  • [3] Two-dimensional code
    Ishikawa, Y
    JOURNAL OF THE JAPANESE SOCIETY FOR FOOD SCIENCE AND TECHNOLOGY-NIPPON SHOKUHIN KAGAKU KOGAKU KAISHI, 2005, 52 (03): : 144 - 144
  • [5] Analysis on Status of Two-dimensional Code Development & Prospects Prediction
    Lu, Xiaohan
    Yu, MengLan
    Huang, Bin
    PROCEEDINGS OF THE 2ND INTERNATIONAL CONFERENCE ON COMPUTER AND INFORMATION APPLICATIONS (ICCIA 2012), 2012, : 1373 - 1376
  • [6] Analysis of two-dimensional integrated Rowland circle grating
    Zhao, Chunhua
    Chen, Kangsheng
    Zhejiang Daxue Xuebao (Ziran Kexue Ban)/Journal of Zhejiang University (Natural Science Edition), 1999, 33 (05): : 465 - 470
  • [7] A TWO-DIMENSIONAL MULTIFLUID HYDRODYNAMIC CODE
    LEROUX, AY
    QUESSEVEUR, P
    LECTURE NOTES IN PHYSICS, 1985, 218 : 365 - 368
  • [8] Two-dimensional Totalistic Code 52*
    Rowland, Todd
    COMPLEX SYSTEMS, 2007, 17 (02): : 163 - 182
  • [9] Verification and refinement of the one-dimensional analysis code for the integrated steam generators in an SFR
    Kim, Seyun
    Eoh, Jae-Hyuk
    Choi, Bo Young
    Kim, Seong-O
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2008, 35 (01) : 12 - 20
  • [10] A DIMENSIONAL ANALYSIS OF EX-VESSEL STEAM EXPLOSION
    Li Wei
    Guo Qiang
    Yuan Yidan
    PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6A, 2018,