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 fuel-coolant 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.
- Nuclear Engineering Division
Analysis of Fuel Coolant Interaction in PWR With Experiment and Computer Code
Wang, X, Li, T, Huang, X, & Yang, Y. "Analysis of Fuel Coolant Interaction in PWR With Experiment and Computer Code." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 3. Xi’an, China. May 17–21, 2010. pp. 491-496. ASME. https://doi.org/10.1115/ICONE18-29642
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