Japanese contributions to IAEA INTOR Workshop, Phase Two A, Part 3

This report includes Japanese contributions presented at INTOR Workshop Phase 2A, Part 3 relevant to the studies of technical critical issues of blanket, first wall, divertor plate and shield designs, and new database concerning these areas. New database for ceramic breeder materials, high heat flux materials, high heat flux experiments and fabrication experience are included. A comparison study of blanket concepts and design studies of candidate blankets have been carried out. The blanket with lithium oxide breeder is selected as the leading blanket concept because of its high breeding performance and good tritium release behavior. Two types of first wall concepts, bare stainless steel first wall concept and protected first wall concepts, are evaluated. For disruptions, the behaviors of crack propagation are examined based on J integrals. The local guard limiter concept with easy maintainability is selected as a reference considering currently rather uncertain disruption scenarios. Tungsten is selected as the reference armor material of divertor plate because of its good thermal and sputtering resistance. The inboard shield thickness has been optimized both for stainless steel material and tungsten material. Blanket engineering test program of FER is also described in this report. Major basic engineering tests on blanket performances such as neutronics, thermal-hydraulics, tritium recovery etc. can be performed by test elements and modules. (author)