ANNUAL PROGRESS REPORT ON FUEL ELEMENT DEVELOPMENT FOR FY 1963
Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ intermetallic compounds demonstrated good stability and fission gas retention capabilities. Developmental aluminum powder metal products showed good corrosion resistance at high temperatures while retaining excellent high temperature strength. All of the fuel compositions tested (UO/sub 2/, U/sub 3/O/sub 8/, and UAl/sub 3/ in aluminum matrices) exhibited density decreases under irradiation. Tensile tests on sandwich-type fuel plates at elevated temperatures indicated that the fuel plate strength is strongly influenced by the core material rather than dependent primarily on the cladding material as was found true of lower (MTR) temperatures. Three capsules containing beryllium were inserted in the ETR, in order to determine strength, gas release, and growth during a high-temperature (600--800 deg C) irradiation. An MTR fuel element employing advanced metallurgical techniques to optimize the hydraulic and heat transfer characteristics was fuily irradiated in the MTR. The fuel element consisted of 32 plates containing 250 g U/sup 235/ in a U/sub 3/O/ sub 8/--Al dispersion. A prototype ETR fuel element was made without side plates. (M.C.G.)
- Research Organization:
- Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-18-008723
- OSTI ID:
- 4127977
- Report Number(s):
- IDO-16934
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-64
- Country of Publication:
- United States
- Language:
- English
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ANNUAL PROGRESS REPORT ON FUEL ELEMENT DEVELOPMENT FOR FY 1962
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Related Subjects
ALUMINUM
ALUMINUM ALLOYS
CORROSION
DENSITY
ETR
EXPANSION
FISSION PRODUCTS
FUEL ELEMENTS
FUELS
GASES
HEAT TRANSFER
HIGH TEMPERATURE
HYDRAULICS
INTERMETALLIC COMPOUNDS
IRRADIATION
LAYERS
MATERIALS TESTING
MTR
PLATES
POWDERS
QUANTITY RATIO
RADIATION EFFECTS
REACTORS
RESEARCH REACTORS
STABILITY
TENSILE PROPERTIES
URANIUM 235
URANIUM ALLOYS
URANIUM DIOXIDE
URANIUM OXIDES