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| Home > Publications database > ITER Relevant High Heat Flux Tests on Plasma Facing Surfaces |
| Journal Article | PreJuSER-45075 |
; ;
2005
Japan Institute of Metals
Sendai
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Please use a persistent id in citations: doi:10.2320/matertrans.46.412
Abstract: The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20MW/m(2) in the divertor targets and around 0.5 MW/m(2) at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.
Keyword(s): J ; fusion (ITER) high heat flux (auto) ; plasma facing materials (auto) ; plasma facing components (auto) ; coating (auto) ; thermal fatigue (auto) ; thermal shock (auto) ; non-destructive examination (auto) ; electron beam (auto) ; particle beam (auto) ; infrared heater (auto) ; in-pile tests (auto) ; plasma gun (auto) ; laser (auto)
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