Published March 1984
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Postirradiation notch ductility tests of ESR alloy HT-9 and modified 9Cr-1Mo alloy from UBR reactor experiments
Description
During this period, irradiation exposures at 3000C and 1500C to approx. 8 x 1019 n/cm2, E > 0.1 MeV, were completed for the Alloy HT-9 plate and the modified Alloy 9Cr-1Mo plates, respectively. Postirradiation tests of Charpy-V (C/sub v/) specimens were completed for both alloys; other specimen types included in the reactor assemblies were fatigue precracked Charpy-V (PCC/sub v/), half-size Charpy-V, and in the case of the modified 9Cr-1Mo, 2.54 mm thick compact tension specimens
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Additional details
Publishing Information
- Imprint Title
- Alloy development for irradiation performance. Semiannual progress report for period ending September 30, 1983
- Journal Page Range
- p. 136-142.
- Report number
- DOE/ER--0045/11
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15063690
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CHARPY TEST; CHROMIUM ALLOYS; DUCTILITY; MEDIUM TEMPERATURE; MOLYBDENUM ALLOYS; STEEL-CR12MOV
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM STEELS; CORROSION RESISTANT ALLOYS; DESTRUCTIVE TESTING; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MARTENSITIC STEELS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MOLYBDENUM ADDITIONS; STAINLESS STEELS; STEELS; TENSILE PROPERTIES; TESTING; VANADIUM ADDITIONS