Work

Carbon and silicon carbide as first wall materials in inertial confinement fusion reactors

Year: 1978
Type: report
Abstract: An assessment of two first wall materials, H-451 nuclear graphite and chemical vapor deposited silicon carbide, is given. A compilation of materials properties is presented. This is followed by temperature profiles and limitations and stress distribution and effects. Next, a discussion is given on the coupling of these ceramic materials to a metal, for enhancement of heat transfer from the first wall to the coolant circuits. (MOW)
Authors: G. Hopkins, R. Price, R. Bullock, J. Dalessandro, N. Elsner
Language: English
Open Access status: gold
OpenAlex ID: W3036769251
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Cited by: 2
Related to: 10