Research and development of fast breeder reactor, 10

This chapter reviews FBR safety R and D activities which have been conducted at PNC since 1970. Much effort in this area has been devoted, both through experimental and analytical works with full utilization of international collaborations, to studies on: thermohydraulics under abnormal transient or accident condition, degraded core, source term and sodium fire. In parallel with above R and D efforts, research on probabilistic safety assessment has been conducted. Major effort had been devoted to quantification and confirmation of safety margin on the prototype reactor Monju. And at present, such efforts are being extended so as to evaluate more precisely and reliably for accident prevention and mitigation on for post-Monju reactors by upgrading tools for safety assessment and conducting the complete PSA for Monju. (author)