Published March 1982 | Version v1
Journal article

Compatibility of the Zr-Al alloy with a tokamak plasma environment

  • 1. Princeton Univ., NJ (USA). Plasma Physics Lab.

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