Published March 1990
| Version v1
Report
Graphites as plasma facing material of a large fusion device
Description
Several graphites, as the first wall materials of Large Helical System, are evaluated in terms of erosion, thermal shock resistance and the recycling. Adequate graphites are suggested, and the required conditions such as baking, cooling and the discharge cleaning are discussed. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the first international Toki conference on plasma physics and controlled nuclear fusion
- Imprint Pagination
- 293 p.
- Journal Page Range
- p. 57-60.
- Report number
- NIFS-PROC--3
Conference
- Title
- 1. international Toki conference on plasma physics and controlled nuclear fusion.
- Dates
- 4-7 Dec 1989.
- Place
- Toki, Gifu (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22024496
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADSORPTION; FIRST WALL; GRAPHITE; HELICAL CONFIGURATION; MECHANICAL PROPERTIES; MECHANICAL TESTS; THERMAL TESTING; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS
- Descriptors DEC
- CARBON; CONFIGURATION; ELEMENTS; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NONMETALS; PHYSICAL PROPERTIES; TESTING; THERMONUCLEAR REACTOR WALLS