AbstractExperiments on the ingress of coolant event (ICE) in the vacuum vessel of a fusion reactor have been carried out in the Japan Atomic Energy Research Institute (JAERI) as one of the research and development tasks for the International Thermonuclear Experimental Reactor (ITER) to obtain the thermofluid data for validation of safety analysis codes. The ICE experiment is numerically analyzed using the transient reactor analysis code (TRAC) which is one of the codes preparing for the safety analysis of the ITER. The TRAC has been modified so as to analyze the ICE phenomena in the vacuum vessel of a fusion reactor. Several ICE experiments have been carried out as benchmark tests for the safety analysis codes. We have analyzed those experiments by using the TRAC, and considered the difference between the analysis and experimental results. Analysis results of the temperature in the vacuum vessel show a tendency completely different from the experimental result. It is clarified that the present TRAC has not been verified on the scattering behavior of water droplets.
In-vessel transient analysis code INTRA for ITER accident analyses