Compatibility of the Zr-Al alloy with a tokamak plasma environment
Description
We have investigated the compatibility of the Zr-Al alloy bulk getter with a tokamak plasma environment, where the hydrogenic fluxes are sufficient to cause embrittlement in relatively short times. Under normal operating conditions with the getters activated, it is necessary to regenerate the absorbed hydrogenic species before the embrittlement limit is reached. We present a method for determining the loading under tokamak conditions where the Zr-Al surface characteristics can change. During glow discharge cleaning and pulse discharge cleaning, it is not convenient to regenerate. We find, however, that during the cleaning operations the getter self-inerts, thus limitng the loading. We present data and a model which accounts for this behavior in terms of impurity adsorption on the room temperature getter surface during the cleaning operations. (orig.)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Mater.
- Journal Volume
- 103
- Journal Issue
- 1-3
- Series
- J. Nucl. Mater.
- Journal Page Range
- 539-544
- ISSN
- 0022-3115
Conference
- Title
- 2. topical meeting on fusion reactor materials.
- Dates
- 9 - 12 Aug 1981.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 13693734
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; BINARY ALLOY SYSTEMS; COMPATIBILITY; PLASMA; THERMONUCLEAR REACTOR MATERIAL; THERMONUCLEAR REACTORS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOY SYSTEMS; ALLOYS; TRANSITION ELEMENT ALLOYS