Irradiation behavior of experimental Mark-II Experimental Breeder Reactor II driver fuel

Journal Article · Tue Jan 01 04:00:00 EST 1980 · Nucl. Technol.; (United States)

DOI:https://doi.org/10.13182/NT80-1· OSTI ID:5694467

Hofman, G L

Prototypic driver-fuel elements using metallic fuel and stainless-steel cladding, designed to achieve a high burnup, were tested in the Experimental Breeder Reactor II. The irradiation results showed that burnup of up to 10 at.% can be attained without cladding failure and that cladding deformation can be kept to acceptable values if Type 316 stainless steel is used as the cladding material.

• Research Organization: Argonne National Lab., IL
• OSTI ID: 5694467
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 47:1; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
ALLOYS
BREEDER REACTORS
BURNUP
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DEFORMATION
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PERFORMANCE TESTING
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-304L
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TESTING