Experiments 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 task
s for the International Thermonuclear Experimental Reactor (ITER) to o
btain the thermofluid data for validation of safety analysis codes. Th
e ICE experiment is numerically analyzed using the transient reactor a
nalysis 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 e
xperiments have been carried out as benchmark tests for the safety ana
lysis codes. We have analyzed those experiments by using the TRAC, and
considered the difference between the analysis and experimental resul
ts. Analysis results of the temperature in the vacuum vessel show a te
ndency completely different from the experimental result. It is clarif
ied that the present TRAC has not been verified on the scattering beha
vior of water droplets. (C) 1998 Elsevier Science S.A. All rights rese
rved.