Postirradiation fracture toughness tests of ESR alloy HT-9 and modified 9Cr-1Mo alloy from UBR reactor experiments
Description
Alloy HT-9 and Modified 9Cr-1Mo are being evaluated for potential applications as first wall materials in magnetic fusion reactors. Objectives of the current research task were to test fatigue-precracked Charpy-V (PCC/sub v/) specimens from representative plates irradiated in the UBR reactor at 1490C or 3000C, and, to compare the results against postirradiation notch ductility data developed previously for the materials. Both plates represent electroslag refined (ESR) melt processing. PCC/sub v/ specimens of Alloy HT-9 and Modified 9Cr-1Mo alloy were irradiated at 3000C and 1490C, respectively, to approx.0.8 X 1020 n/cm2, E > 0.1 MeV. During this period, postirradiation tests for fracture toughness were completed and results compared to notch ductility determinations from standard Charpy-V (C/sub v/) specimens irradiated in the same reactor experiments. Fracture surface examinations by SEM are also reported
Additional details
Publishing Information
- Imprint Title
- Alloy development for irradiation performance. Semiannual progress report for period ending March 31, 1984
- Journal Page Range
- p. 86-99.
- Report number
- DOE/ER--0045/12
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16065851
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- CHARPY TEST; CHEMICAL COMPOSITION; FIRST WALL; FRACTURE PROPERTIES; HEAT TREATMENTS; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CRYSTAL STRUCTURE; DESTRUCTIVE TESTING; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; RADIATION EFFECTS; STEELS; TESTING; THERMONUCLEAR REACTOR WALLS