Effects of irradiation temperature, fluence, and heating rate on flow properties of cladding under simulated temperature transient heating and deformation conditions. [Temperature to 720/sup 0/C and fluence to 10/sup 23/ n/cm/sup 2/ (E > 0. 1 MeV)]
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% cold-worked Type 316 stainless steel cladding, irradiated in the Experimental Breeder Reactor-II at temperatures to 720/sup 0/C and fluences to 10/sup 23/ n/cm/sup 2/ (E > 0.1 MeV). A monotonic decrease of transient failure temperature with increasing irradiation temperature was observed at the ''standard'' heating rate of 5.6/sup 0/C/s. This effect became more pronounced for irradiation temperatures above 600/sup 0/C. Transient failure temperatures generally decreased with increasing fluence for tests performed at the standard heating rate. Irradiated and unirradiated specimens were tested at several heating rates. For equal stress, fluence, and irradiation temperature, decreasing the heating rate decreased failure temperatures by as much as 170/sup 0/C for irradiated specimens and 150/sup 0/C for unirradiated specimens. Data reported fall well within FFTF design limits for transient conditions and serve to confirm the material properties currently used in the design analyses.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6649897
- Report Number(s):
- HEDL-SA-1461; CONF-780722-4
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tensile property correlations for highly irradiated 20% C. W. type 316 stainless steel. [Irradiation at 370 to 816/sup 0/C at fast neutron fluence of 8. 4 x 10/sup 22/ n/cm/sup 2/ (E > 0. 1 MeV)]
High temperature in-reactor creep of 20% cold worked FTR cladding
Mechanical properties of transient-tested irradiated fast-reactor cladding. [811/sup 0/ to 1644/sup 0/K; 5. 8 x 10/sup 22/ n/cm/sup 2/]
Conference
·
Thu May 11 00:00:00 EDT 1978
·
OSTI ID:6551330
High temperature in-reactor creep of 20% cold worked FTR cladding
Conference
·
Wed Nov 30 23:00:00 EST 1977
·
OSTI ID:6400521
Mechanical properties of transient-tested irradiated fast-reactor cladding. [811/sup 0/ to 1644/sup 0/K; 5. 8 x 10/sup 22/ n/cm/sup 2/]
Conference
·
Wed Aug 09 00:00:00 EDT 1978
·
OSTI ID:6400498
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COLD WORKING
CORROSION RESISTANT ALLOYS
DUCTILITY
EPITHERMAL REACTORS
FABRICATION
FAILURES
FAST REACTORS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEATING RATE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS WORKING
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
PLASTICITY
PRESSURE DEPENDENCE
RADIATION EFFECTS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEMPERATURE EFFECTS
TENSILE PROPERTIES
TRANSIENTS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COLD WORKING
CORROSION RESISTANT ALLOYS
DUCTILITY
EPITHERMAL REACTORS
FABRICATION
FAILURES
FAST REACTORS
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEATING RATE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS WORKING
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NEUTRON FLUENCE
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
PLASTICITY
PRESSURE DEPENDENCE
RADIATION EFFECTS
REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEMPERATURE EFFECTS
TENSILE PROPERTIES
TRANSIENTS