NDLI: Effect of disruptions on plasma-facing components

Content Provider	IEEE Xplore Digital Library
Author	Gilligan, J.G. Bourham, M.A. Tucker, E.C.
Copyright Year	1995
Description	Author affiliation: Dept. of Nucl. Eng., North Carolina State Univ., Raleigh, NC, USA (Gilligan, J.G.; Bourham, M.A.; Tucker, E.C.)
Abstract	Erosion of plasma-facing components during disruptions is a limiting factor in the design of large tokamaks like ITER. During a disruption, much of the stored thermal energy of the plasma will be dumped onto divertor plates, resulting in local heat fluxes, which may exceed 100 GW/m/sup 2/ over a period of about 0.1-1.0 msec. Melted and/or vaporized material is produced which is redistributed in the divertor region. Simulation of disruption damage is summarized from code results and from experimental exposure of materials to high heat-flux plasmas in plasma guns. In the US several codes have been used to predict both melt/vaporization and heat transfer on surfaces as well as energy and momentum transport in the vapor/plasma shield produced at the surface.
Starting Page	424
Ending Page	429
File Size	641586
Page Count	6
File Format	PDF
ISBN	0780329694
DOI	10.1109/FUSION.1995.534255
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1995-09-30
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Plasma materials processing Plasma simulation Plasma transport processes Pulse measurements Conducting materials Copper Tokamaks Guns Solids Plasma devices
Content Type	Text
Resource Type	Article

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