Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures: Preliminary results
- 1. Oak Ridge National Laboratory, TN (United States)
Description
Candidate materials for first wall/blanket structures in ITER have been irradiated to damage levels of about 3 dpa at temperatures of either 60 or 250 degrees C. Preliminary results have been obtained for several of these materials irradiated at 60 degrees C. The results show that irradiation at this temperature reduces the fracture toughness of austenitic stainless steels, but the toughness remains quite high. The unloading compliance technique developed for the subsize disk compact specimens works quite well, particularly for materials with lower toughness. Specimens of materials with very high toughness deform excessively, and this results in experimental difficulties
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Title
- Fusion reactor materials semiannual progress report for the period ending March 31, 1993
- Imprint Pagination
- 524 p.
- Journal Page Range
- p. 277-285.
- Report number
- DOE/ER--0313/14
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25054119
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- AUSTENITIC STEELS; FRACTURE PROPERTIES; IRRADIATION; NEUTRONS; PROGRESS REPORT; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; DOCUMENT TYPES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NUCLEONS; STEELS