Published March 1995
| Version v1
Journal article
Design standard issues for ITER in-vessel components
Description
Design loadings and potential mechanical damage in ITER in-vessel components are enumerated. Design by analysis requirements for ITER blanket and divertor are discussed in the light of the decreasing ductility of the structural material as a function of the neutron fluence. The applicability and limitations of the ASME Boilers and Pressure Vessels Code, Section III to ITER components are discussed. The design rules from fission reactor core components are reviewed for potential application to ITER. (orig.)
Additional details
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 29
- Journal Page Range
- p. 158-163.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 3. international symposium on fusion nuclear technology (ISFNT-3).
- Dates
- 26 Jun - 1 Jul 1994.
- Place
- Los Angeles, CA (United States).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 27024730
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOILERS; BREEDING BLANKETS; COMPUTER CODES; DESIGN; DIVERTORS; DUCTILITY; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR COMPONENTS; REACTOR SAFETY; TENSILE PROPERTIES; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONTAINERS; MECHANICAL PROPERTIES; RADIATION EFFECTS; SAFETY; THERMONUCLEAR DEVICES