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- W1656918263 abstract "The CINDA-3G computer code has been adapted to analyze the thermal responses and operating limitations of two fusion reactor first-wall concepts under normal cyclic operation. A component of an LMFBR computer has been modified and adapted to analyze the ablative behavior of first-walls after a plasma disruption. The first-wall design concepts considered are a forced-circulation water-cooled stainless steel panel with and without a monolithic graphite liner. The thermal gradients in the metal wall and liner have been determined for several burn-cycle scenarios and the extent of surface ablation that results from a plasma disruption has been determined for stainless steel and graphite first surfaces." @default.
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- W1656918263 date "1977-01-01" @default.
- W1656918263 modified "2023-09-23" @default.
- W1656918263 title "Thermal responses of tokamak reactor first walls during cyclic plasma burns" @default.
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