Recent R&D activities on plasma facing components at JAERI

Plasma Facing Components will be exposed to severe heat loads during the normal operation, and will severely be eroded by evaporation and particle emission during disruptions in next generation fusion devices such as International Thermonuclear Experimental Reactor (ITER). In this paper, we present recent major R&D topics on plasma facing components (PFCs) at JAERI as follows; (1) thermal cycling experiments on a 1 m long divertor mock-up, (2) disruption simulation tests on B/sub 4/C doped CFCs and tungsten, (3) tensile and bending tests of beryllium/copper alloy duplex structures.