Effects of irradiation temperature, fluence, and heating rate on postirradiation flow properties of cladding under simulated temperature transient heating and deformation conditions
Description
Irradiation temperature, fluence, and heating rate effects on plastic flow and failure properties of fast reactor cladding were investigated by heating internally pressurized specimens until failure occurred. Specimens tested were from 20 percent cold-worked Type 316 stainless steel cladding, irradiated in the experimental breeder reactor II (EBR-II) at temperatures to 7200C and fluences to 1023 neutrons (n)/cm2(E>0.1 MeV). A decrease of transient failure temperature with increasing irradiation temperature was observed at the ''standard'' heating rate of 5.6 C0/s. This effect became more pronounced for irradiation temperatures above 6000C. Transient failure temperatures also generally decreased with increasing fluence for tests performed at the standard heating rate. 5 refs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- Journal Issue
- no.683
- Series
- Am. Soc. Test. Mater., Spec. Tech. Publ.
- ISSN
- 0066-0558
Conference
- Title
- 9. international symposium on the effects of radiation on structural materials.
- Dates
- 11 Jul 1978.
- Place
- Richland, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11551832
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFORMATION; DUCTILITY; EBR-2 REACTOR; FFTF REACTOR; FUEL CANS; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; STAINLESS STEEL-316; STRAINS
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS; TENSILE PROPERTIES; TEST REACTORS; TRANSITION ELEMENT ALLOYS