Published September 1982
| Version v1
Report
Tensile properties of ferritic (martensitic) steels after low-temperature HFIR irradiation
Description
In addition to the ferritic steels previously tested, experiment HFIR-CTR-33 also contained tensile specimens of 20%-cold-worked type 316 stainless steel for irradiation at about 550C. The tensile behavior of the type 316 stainless steel was determined at room temperature and 3000C, and the results showed the irradiated properties of the two classes of steels to be quite similar
Additional details
Publishing Information
- Imprint Title
- Alloy development for irradiation performance. Semiannual progress report for period ending March 31, 1982
- Journal Page Range
- p. 414-423.
- Report number
- DOE/ER--0045/8
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14739433
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- FERRITIC STEELS; HFIR REACTOR; MEDIUM TEMPERATURE; NEUTRON REACTIONS; STAINLESS STEEL-316; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BARYON REACTIONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HADRON REACTIONS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUCLEAR REACTIONS; NUCLEON REACTIONS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEELS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS