ANALYSIS OF FUEL COOLANT INTERACTION IN PWR WITH EXPERIMENT AND COMPUTER CODE
Fuel-Coolant Interaction can be divided into two stages including premixing and explosion. In the stage of premixing, the liquid corium flowing from the core fragmented into drops, and the drops may fragmented into fine fragmentations leads to steam explosion in the condition of triggering. In the severe accident, the contact of melt-fuel and coolant may result into steam explosion, which may threaten integrity of containment. The prediction of steam explosion must be based on results of experimental research and on simulations with computer code. In this work, the experimental result of low temperature fuelcoolant interaction is compared with the computing result of FCI-CMFD code MC3D, analyzing the phenomenon of FCI, the diameter of droplet and the pressure wave of explosion. Then, the MC3D is used in the analysis and prediction of fuel coolant interaction in CPR1000 NPP model.
WANG Xi LI Tian-shu HUANG Xi YANG Yan-hua
School of Nuclear Science and Engineering, Shanghai Jiao Tong University Shang Hai, China
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-6
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）