Tensile properties of irradiated surveillance coupons
Tensile testing of austenitic steel and superalloy samples irradiated in the HMO 13 assembly was performed in support of the Fast Flux Test Facility (FFTF) Surveillance Program. Postirradiation yield stress, ultimate tensile stress, uniform elongation, total elongation, and reduction in area of 304 stainless steel (SS), 308 SS weld, 316 SS, A286, In718, and In718 weld were determined. Results showed the strength of austenitic steels increased while the ductility decreased as a result of irradiation. Low irradiation exposure produced little property change in In718. Overall, the tensile properties of HMO 13 surveillance coupons showed a lower magnitude of irradiation-induced property change than was expected based on earlier studies. Results from these tests gave no indications of unexpectedly severe irradiation damage to FFTF components.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 10173088
- Report Number(s):
- WHC-SA--2477; ON: DE94016471
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
220600
36 MATERIALS SCIENCE
360106
AUSTENITIC STEELS
COMPONENTS AND ACCESSORIES
FFTF REACTOR
HEAT RESISTING ALLOYS
POST-IRRADIATION EXAMINATION
RADIATION EFFECTS
REACTOR COMPONENTS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TENSILE PROPERTIES
220200
220600
36 MATERIALS SCIENCE
360106
AUSTENITIC STEELS
COMPONENTS AND ACCESSORIES
FFTF REACTOR
HEAT RESISTING ALLOYS
POST-IRRADIATION EXAMINATION
RADIATION EFFECTS
REACTOR COMPONENTS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TENSILE PROPERTIES