Hydrogen retention of V-alloy under plasma irradiation of JFT-2M
- 1. Hokkaido Univ., Dept. of Nuclear Engineering, Faculty of Engineering, Sapporo (Japan)
- 2. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Description
Deuterium retention of V-4Cr-4Ti alloy exposed to JFT-2M tokamak environment for 9 months was examined by thermal desorption spectroscopy (TDS). The amount of deuterium retained in V-alloy was approximately 1 wppm, which was one order of magnitude larger than that of 304 SS. After the exposure, deposition of impurities was observed at the surface. The thickness of impurity layer was approximately 200 nm, and the titanium oxide was formed in this layer. Surface oxidation of V -alloy was conducted in order to reduce the hydrogen absorption. After the oxidation at temperature of 373 K, thick Ti-O layer was formed at the surface. In this case, hydrogen absorption amount was one order of magnitude reduced compared with the case of no oxidation. (author)
Additional details
Publishing Information
- Journal Title
- Shinku
- Journal Volume
- 43
- Journal Issue
- 3
- Journal Page Range
- p. 325-328
- ISSN
- 0559-8516
Conference
- Title
- 40. vacuum symposium
- Dates
- 10-12 Nov 1999
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31032510
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADSORPTION; FIRST WALL; HYDROGEN; JFT-2M TOKAMAK; RETENTION; SORPTIVE PROPERTIES; TEMPERATURE DEPENDENCE; THERMONUCLEAR REACTOR MATERIALS; VANADIUM ALLOYS
- Descriptors DEC
- ALLOYS; CLOSED PLASMA DEVICES; ELEMENTS; MATERIALS; NONMETALS; SORPTION; SURFACE PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 8 refs., 4 figs., 1 tab.