Recent R&D activities on plasma facing components at JAERI
- 19 November 2002
- conference paper
- Published by Institute of Electrical and Electronics Engineers (IEEE)
- Vol. 1, 220-223
- https://doi.org/10.1109/fusion.1995.534207
Abstract
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.Keywords
This publication has 4 references indexed in Scilit:
- Experiments on heat transfer of smooth and swirl tubes under one-sided heating conditionsInternational Journal of Heat and Mass Transfer, 1996
- Sputtering yields of carbon based materials under high particle flux with low energyJournal of Nuclear Materials, 1995
- Erosion of CFCs and W at high temperature under high heat loadsJournal of Nuclear Materials, 1994
- High heat flux experiments of saddle type divertor moduleJournal of Nuclear Materials, 1994