DEVELOPMENT OF ADVANCED LOOP-TYPE FAST REACTOR IN JAPAN:PROGRESS OF DESIGN STUDY BASED ON PRELIMINARY ASSESSMENT RESULTS

摘要

The Japan sodium-cooled fast reactor (JSFR) is anadvanced loop-type reactor concept which is investigated in theFast Reactor Cycle Technology Development project in Japan.This paper describes some important progress on the JSFRdesign study and R&D discussed in a preliminary assessmentfor the first milestone of this project. As for the reactor systemdesign, structural integrity against both thermal stress andseismic force was investigated. Then, the specification of thereactor vessel was established. Also, investigation of designoptions to extend a design margin against seismic force hasbeen suggested. Regarding thermal hydraulics issues in thereactor vessel, design measures against cover gas entrainmentand vortex cavitations have been introduced to the reactorsystem design based on R&D results. Further investigation is inprogress for design optimization or improvement of preventiveeffect. The hot-leg piping design of primary cooling circuit wasalso established taking "Type-IV" damage into account.