Ponente
Descripción
The design for the early stage of JA DEMO divertor will be similar to the ITER divertor design, which means that mono-block type W will be used as plasma facing material with high conductivity Cu alloys being used as heatsink material. There have been several neutron irradiation tests on-going using available fission test reactors but, since transmutation effect like Re and Os productions in W or He effects on Cu alloys and joints is expected to have large impact on both materials, there is a strong demand for neutron irradiation tests with more realistic environment for material integrity evaluation. On the presentation, the needs and plans for fusion neutron irradiation of W and Cu alloys will be presented and resent and future plans for the development including evaluation techniques will be reported.
