Swelling of 20% cold worked 316 stainless steel fuel pin cladding and ducts
The data base of 316 Stainless Steel 20% Cold Worked cladding swelling measurements from mixed-oxide fuel pins irradiated in EBR-II has been extended to a fast (E > 0.1 MeV) fluence of 17 x 10/sup 22/ n/cm/sup 2/. Previously the data base from actual fuel pins included only developmental and FFTF first core cladding of 0.230 in. diameter irradiated to a maximum fast fluence of 13 x 10/sup 22/ n/cm/sup 2/. Recent data includes FFTF fourth core material and cladding samples 0.290 in. in diameter which were taken from various advanced oxide experiments. Differences in incubation parameter between the swelling of First and Fourth core material were at first attributed to heat-to-heat differences, but later were shown to be more properly attributed to different experimental and cladding fabrication parameters. Peak swelling values have now reached 40% volume change. Swelling in cold worked 316 stainless steel ducts used in EBR-II has also been evaluated using coupons cut or punched from irradiated duct faces. Substantial differences in swelling between faces, which reflect the local reactor environment, have been observed. More recently, duct material at the same maximum fluence as that of the fuel pin cladding has been added to the data base and compared to the swelling of EBR-II cladding.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (United States)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6891851
- Report Number(s):
- HEDL-SA-3029-FP; CONF-840604-38; ON: DE87005474
- Resource Relation:
- Conference: 12. international symposium on effects of radiation on materials, Williamsburg, VA, USA, 18 Jun 1984; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
EBR-2 REACTOR
FUEL CANS
REACTOR MATERIALS
DUCTS
FUEL PINS
MIXED OXIDE FUELS
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-316
SWELLING
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEELS
STEELS
210500* - Power Reactors
Breeding
360106 - Metals & Alloys- Radiation Effects