Title :
Effect of disruptions on plasma-facing components
Author :
Gilligan, John G. ; Bourham, Mohamed A. ; Tucker, Eric C.
Author_Institution :
Dept. of Nucl. Eng., North Carolina State Univ., Raleigh, NC, USA
fDate :
30 Sep-5 Oct 1995
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/m2 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
Keywords :
Tokamak devices; fusion reactor materials; fusion reactor theory; fusion reactors; melting; vaporisation; 0.1 to 1 ms; ITER; disruption damage; disruptions; heat flux; heat transfer; melt; plasma guns; plasma-facing components; surfaces; tokamaks; vapor/plasma shield; vaporization; Conducting materials; Copper; Guns; Plasma devices; Plasma materials processing; Plasma simulation; Plasma transport processes; Pulse measurements; Solids; Tokamaks;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534255
