Beryllium---a better tokamak plasma-facing material

Journal Article · Tue May 01 04:00:00 EDT 1990 · Journal of Vacuum Science and Technology, A (Vacuum, Surfaces and Films); (USA)

DOI:https://doi.org/10.1116/1.576843· OSTI ID:7093317

Wilson, K L; Causey, R A; Hsu, W L; Mills, B E; Smith, M F; Whitley, J B ^[1]

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1. Sandia National Laboratories, Livermore, CA (USA) Sandia National Laboratories, Albuquerque, NM (USA)

The plasma--material interaction and high heat flux properties of beryllium are reviewed to determine its suitability as a plasma-facing component in magnetic fusion energy reactors. Consideration is given to beryllium's outgassing, erosion, and hydrogen retention characteristics. Its responses to normal and off-normal high heat fluxes are compared to graphite in both the as-received and the neutron-irradiated states. Beryllium's performance in present-day devices is assessed, and its expected behavior in future reactors is summarized. It is concluded that beryllium is potentially a better plasma-facing material than graphite and that more development and testing is warranted.

• DOE Contract Number: AC04-76DP00789
• OSTI ID: 7093317
• Journal Information: Journal of Vacuum Science and Technology, A (Vacuum, Surfaces and Films); (USA), Journal Name: Journal of Vacuum Science and Technology, A (Vacuum, Surfaces and Films); (USA) Vol. 8:3; ISSN JVTAD; ISSN 0734-2101
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALINE EARTH METALS
BERYLLIUM
CARBON
CLOSED PLASMA DEVICES
DEGASSING
ELEMENTAL MINERALS
ELEMENTS
EROSION
GRAPHITE
HEAT FLUX
MATERIALS TESTING
METALS
MINERALS
NONMETALS
PERFORMANCE
SURFACE PROPERTIES
TESTING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES