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Conceptual design of the INTOR first wall system

Conference · · Proc. Symp. Eng. Probl. Fusion Res.; (United States)
OSTI ID:6360289

The design concept and performance characteristics of the first wall design for the phase-1 INTOR (International Tokamak Reactor) study is described. The reference design consists of a water-cooled stainless steel panel. The major uncertainty regarding the performance of the bare stainless steel wall relates to the response of a thin melt layer predicted to form on limited regions during a plasma disruption. A more complex backup design, which incorporates radiatively cooled graphite tiles on the inboard wall, is briefly described.

Research Organization:
Argonne Natl Lab, IL, USA
OSTI ID:
6360289
Report Number(s):
CONF-811040-
Journal Information:
Proc. Symp. Eng. Probl. Fusion Res.; (United States), Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States); ISSN PSERD
Country of Publication:
United States
Language:
English