Published October 1983
| Version v1
Report
Effect of the microstructure on tensile properties of type 316 stainless steel
Description
A series of tensile specimens that had been given different thermal and mechanical processing treatments was irradiated in the ORR at 250, 290, 450, and 5000C to a neutron fluence of about 6.8 x 1025 neutrons/m2 (>0.1 MeV) (approx. 5 dpa and 40 at. ppM He). The tensile properties of irradiated and unirradiated steel with 20, 30, and 50% cold work were determined at the irradiation temperatures
Additional details
Publishing Information
- Imprint Title
- Alloy development of irradiation performance. Semiannual progress report for period ending March 31, 1983
- Journal Page Range
- p. 53-59.
- Report number
- DOE/ER--0045/10
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15020704
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; HIGH TEMPERATURE; IRRADIATION; MEDIUM TEMPERATURE; MICROSTRUCTURE; NEUTRON REACTIONS; ORR REACTOR; STEEL-CR17NI12MO3; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BARYON REACTIONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; ENRICHED URANIUM REACTORS; HADRON REACTIONS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUMERICAL DATA; REACTORS; STAINLESS STEELS; STEELS; TANK TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS