Published April 2001
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Fusion Reactor Materials
Description
The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the behaviour of fusion reactor materials and components during and after irradiation. Ongoing projects include: the study of the mechanical behaviour of structural materials under neutron irradiation; the investigation of the characteristics of irradiated first wall material such as beryllium; the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; and the study of dismantling and waste disposal strategy for fusion reactors. Progress and achievements in these areas in 2000 are discussed
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Additional details
Identifiers
Publishing Information
- Publisher
- Belgian Nuclear Research Center SCK-CEN, Mol
- Imprint Place
- Mol (Belgium)
- Imprint Title
- 2000 Scientific Report
- Imprint Pagination
- 176 p.
- Journal Page Range
- p. 61-67
- Report number
- INIS-BE--0003
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 32053174
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BERYLLIUM; IRRADIATION; MATERIALS TESTING; NEUTRONS; PROGRESS REPORT; RADIATION EFFECTS; RADIOACTIVE WASTE MANAGEMENT; REACTOR DISMANTLING; THERMONUCLEAR REACTORS
- Descriptors DEC
- ALKALINE EARTH METALS; BARYONS; DEMOLITION; DOCUMENT TYPES; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; HADRONS; MANAGEMENT; METALS; NUCLEONS; TESTING; WASTE MANAGEMENT
Optional Information
- Notes
- The abstract is a contribution to the 2000 Scientific Report of the Belgian Nuclear Research Centre SCK-CEN