Thermal responses of first wall limiters in the Tokamak Fusion Test Reactor

Journal Article · Tue Jan 01 00:00:00 EST 1980 · J. Vac. Sci. Technol.; (United States)

DOI:https://doi.org/10.1116/1.570417· OSTI ID:5312982

Budny, R

A model was used for the heat flux to estimate the thermal responses and the sublimation rates of several first wall limiters proposed for the Tokamak Fusion Test Reactor. The critical parameter is the thickness of the scrape-off layer, or outer skin of the plasma. The thinner this is, the hotter the limiter will become after repeated discharges. The minimum tolerable thickness is about 0.5 cm for copper or graphite tiles over Nitronic 33 steel backing plates. For thicknesses less than this the steel will be too hot; the sublimation rates of most of the proposed first wall coatings for the tiles are sufficiently low to not contaminate the plasma.

• Research Organization: Princeton University, Princeton, New Jersey 08544
• DOE Contract Number: EY-76-C-02-3073
• OSTI ID: 5312982
• Journal Information: J. Vac. Sci. Technol.; (United States), Vol. 17:1
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
LIMITERS
SUBLIMATION
TOKAMAK TYPE REACTORS
PLASMA CONFINEMENT
COPPER
FIRST WALL
GRAPHITE
HEAT FLUX
HEAT TRANSFER
SPUTTERING
CARBON
CONFINEMENT
ELEMENTS
ENERGY TRANSFER
EVAPORATION
METALS
NONMETALS
PHASE TRANSFORMATIONS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing