IRRADIATION TESTING OF FUEL MATERIALS FOR EGCR

Journal Article · Sat Sep 01 04:00:00 EDT 1962 · Nuclear Sci. and Eng.

OSTI ID:4772189

Trauger, D B

Irradiation tests were conducted in the ORR, ETR, and LITR for evaluating fuel materials for the EGCR. Time limitations imposed by the reactor construction schedule restricted material choices and test conditions to those imMediately appropriate for the EGCR and necessitated some replication. Fifty- nine assemblies were irradiated at stainless steel cladding surface temperatures of 1300 to 1600 deg F and power densities both above and below 30,000 Btu/hr per foot of UO/sub 2/ fuel length. NaK-filled containers were employed to test prototype-size fuel capsules, and air-cooled capsules of reduced size were used for fission-gas-release studies. External pressurization of 315 psia was applied to fuel assemblies of prototype size. Preliminary results appear to affirm the adequacy of the fuel element design. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• NSA Number: NSA-17-002023
• OSTI ID: 4772189
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 14
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AIR
BUILDING MATERIALS
CANNING
ETR
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
GAS COOLANT
GASES
HIGH TEMPERATURE
INTERMETALLIC COMPOUNDS
IRRADIATION
LITR
METALS, CERAMICS, AND OTHER MATERIALS
ORR
PLANNING
POTASSIUM ALLOYS
PRESSURE
RADIATION DOSES
REACTORS
SODIUM ALLOYS
STAINLESS STEELS
SURFACES
TESTING
URANIUM DIOXIDE
VESSELS