NUCLEAR FUELS AND MATERIALS DEVELOPMENT (SUPPLEMENT)
Fuels. Long thin plates of U-3.5 Mo--0.2 Al were cast. The densities and viscosities of liquid Pu and Pu- Fe eutectic mixture were measured up to 925 deg C. Phase equi librium diagrams of the Pu-Cu and Pu--Ce--Cu systems were determined. Uranium silicide was investigated for use as a high-temperature, long-burnup fuel. Preparation, fabrication, mechanical properties, and compatibility with Nb alloys is discussed for uranium carbide. Properties of PuC and PuC-- UC mixtures were studied. Irradiation Testing. Measurable diffusion occurred through the Al/sub 2/O/sub 3/ coatings of irradiated UO/sub 2/ pellets. The irradiation behavior of PuC, UC --20 wt.% PuC, Pu-1 wt.% Al, Th--Pu, U-- PuFissium, and Z r- Pu alloys was investigated. Irradiations of U-- 5 wt.% fissium alloy indicated that the alloy will be able to withstand the desired EBR- II core conditions. Th--U alloys were irradiated to determine their suitability for high-temperature fuel elements. Fabrication. BeO-- 30% UO/sub 2/ dispersions were fabricated by cold pressing and sintering to 95% theoretical density for irradiation tests. Differential thermal amlysis and thermogravimetric studies were made of the calcination of BeC/sub 2/O/sub 4/ - 3H/ sub 2/O. Cladding and Container Materials. Nb was studied for use both as cladding and as a bond and diffusion barrier material between a U alloy fuel and Al cladding for organic cooled reactors. Phase equilibria of the Nb-- Zr system were deternined. Long-term corrosion tests were performed on a low-Si, Al alloy A288 containing 1 wt.% Ni, 0.5 wt.% Fe, 0.1 wt.%, Ti, and 0.001 wt.% Si max. The development of Zr alloys for cladding and jackets for use in superheated steam continued. The corrosion behavior of Fe in water containing O/sub 2/ was investigated. Liquid-Metal Compatibility Studies. Batches of commercial K were purified by hot gettering and subsequent cold trapping to produce a relatively pure material for use in compatibility and heat transfer experiments. Nine refluxing K compatibility tests were conducted to provide screening information regarding the comparative corrosion resistance of Fe, Ni, Co, and Nb alloys. Results of boiling K loop tests are discussed. Nondestructive Testing Development. Studies of ultrasonic behavior in thin sections were directed toward the detection and evaluation of nonbond areas in clad structures. Development of a suitable technique and calibration of gamma spectrometry equipment for U-Al core blanks were essentially completed. The dual-frequency, probe-type eddy current inspection technique was employed in the inspection of Zircaloy-2 tubing. Neutron radiography techniques are discussed. (M.C.G.)
- Research Organization:
- Division of Reactor Development, AEC
- NSA Number:
- NSA-15-014646
- OSTI ID:
- 4051551
- Report Number(s):
- TID-11295(Suppl.)
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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ALUMINUM
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ALUMINUM OXIDES
BARRIERS
BERYLLIUM COMPOUNDS
BERYLLIUM OXIDES
BOILING
BONDING
CALCINATION
CALIBRATION
COBALT ALLOYS
CORROSION
DENSITY
DIFFUSION
DISPERSIONS
EDDY CURRENTS
EUTECTICS
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FABRICATION
FISSION PRODUCTS
FREQUENCY
FUEL CANS
GAMMA SPECTROMETERS
HEAT TRANSFER
HIGH TEMPERATURE
INSPECTION
IRON
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IRRADIATION
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LIQUID METALS
MATERIALS TESTING
MECHANICAL STRUCTURES
NEUTRONS
NICKEL ALLOYS
NIOBIUM
NIOBIUM ALLOYS
NONDESTRUCTIVE TESTING
ORGANIC COOLANT
OXALATES
OXYGEN
PELLETS
PHASE DIAGRAMS
PIPES
PLUTONIUM ALLOYS
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