Sensitivity study of Fukushima unit 1 type accident with MELCOR
5-1-3-3 Numerical modelling/analysis
Research plan regarding improvement of simulation code for understanding the status of fuel debris in the reactor - international experts' symposium on the decommissioning of TEPCO's Fukushima Daiichi Nuclear Power Plant unit 1-4
Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants. (64) Validation of SAMPSON/DCA creep model against OLHF experiments
Source term analysis using MELCOR Code
Analysis for accident progression with THALES2 Code