This paper describes the current status and future plans of the fusion
safety research and development regarding to the developments of the
dust removal system and safety analysis code and the thermofluid exper
iments in the Japan Atomic Energy Research Institute (JAERI) for a fus
ion experimental reactor. The containment of the radioactive material
is the key to achieve fusion safety. In the event of accidents, the so
urce terms need to be evaluated with sufficient accuracy. Therefore, i
n JAERI, the dust characterization have been investigated and the dust
removal system using electric force has been developed and tested. A
safety analysis code including both thermal and plasma transient analy
ses under the various event sequences has been developed. Moreover, th
e preliminary experiments of thermofluid transients in the vacuum vess
el such as Ingress of Coolant Event (ICE) and Loss of Vacuum Event (LO
VA) have been started and the experimental results using preliminary L
OVA/ICE apparatus during 1995-1996 are summarized in this paper.