抄録
An analytical code, CAMP, is being developed at JAERI for thermo-fluiddynamic analysis of molten core in the lower plenum of the reactor pressure vessel. This code is mainly used for the evaluation of initial and boundary conditions for ex-vessel interactions between molten core and coolant. The experiments, where molten alumina was poured into a water-filled lower head experimental vessel, were analyzed with CAMP code. It was found that thermal responses of the experimental vessel were qualitatively reproduced by using models on vessel deformation, subsequent gap formation between solidified alumina and the vessel, and water penetration into the gap. The validation of low Reynolds number two-equation turbulence model, recently incorporated into CAMP code, is also in progress with experiments for natural convection of internally heated fluids with high Rayleigh number.
