Mechanical properties of type 316 stainless steel materials after irradiation at 515/sup 0/C and 585/sup 0/C
Three different heats of type 316 SS base metal plate metals and three different weld metals produced by shielded metal arc, submerged arc, and gas tungsten arc processes with type 316 SS filler metal were used in the Gas-Cooled Fast Reactor (GCFR) Structural Materials Irradiation Experiment. Pre-irradiation strength and ductility properties over the range 24/sup 0/C to 650/sup 0/C were very similar for the three base metal heats and were within the expected range for this alloy. The three welds showed variations in strength and ductility before irradiation, but properties were generally within the range of previous experience for austenitic stainless steel welds. Weld metals showed higher yield strength but lower uniform and total elongations than those of base metal.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC14-76FF02170
- OSTI ID:
- 6545366
- Report Number(s):
- HEDL-TME-81-4; TRN: 81-007304
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
GCFR REACTOR
REACTOR MATERIALS
STAINLESS STEEL-316
DUCTILITY
PHYSICAL RADIATION EFFECTS
TENSILE PROPERTIES
TEMPERATURE DEPENDENCE
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR TYPE REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM COOLED REACTORS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
STEELS
210500* - Power Reactors
Breeding
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties