Swelling behavior of 20% CW 316 stainless steel cladding irradiated with and without adjacent fuel

Conference · Fri Jan 01 00:00:00 EST 1982 · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)

OSTI ID:5828718

Makenas, B J ^[1]; Bates, J F; Jost, J W

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1. Hanford Engineering Development Lab., Richland, WA

Swelling behavior has been evaluated for irradiated 20% CW 316 stainless steel used as cladding material for mixed-oxide fuel pins in EBR-II. This behavior has been compared statistically with the behavior of a large number of specimens which were irradiated without adjacent fuel in the same reactor. In spite of the chemical environment and stresses experienced by fueled cladding, the fueled and nonfueled cladding appear to behave in a similar manner although some divergence was noted for one of the cases studied.

• OSTI ID: 5828718
• Report Number(s): CONF-820628-
• Journal Information: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Vol. 782; Conference: 11. international symposium on effects of radiation on materials, American Society for Testing and Materials, Scottsdale, AZ, USA, 28 Jun 1982
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
FUEL CANS
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-316
EBR-2 REACTOR
FUEL PINS
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
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
STAINLESS STEELS
STEELS
360106* - Metals & Alloys- Radiation Effects