Published October 1998
| Version v1
Journal article
Design and material selection for ITER first wall/blanket, divertor and vacuum vessel
Creators
- 1. ITER JCT, Garching (Germany)
Description
Design and R and D have progressed on the ITER vacuum vessel, shielding and breeding blankets, and the divertor. The principal materials have been selected and the fabrication methods selected for most of the components based on design and R and D results. The resulting design changes are discussed for each system. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 258-263
- Journal Issue
- pt.A
- Journal Page Range
- p. 74-84
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 8. international conference on fusion reactor materials (ICFRM-8)
- Dates
- 26-31 Oct 1997
- Place
- Sendai (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30003549
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; DIVERTORS; FIRST WALL; ITER TOKAMAK; REACTOR VESSELS; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONTAINERS; MATERIALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 11 refs.