PLUTONIUM FUELS DEVELOPMENT, PLUTONIUM METALLURGY OPERATION QUARTERLY REPORT-JANUARY, FEBRUARY, MARCH 1958
The last two of four Zircaloy-clad capsules containing aluminum- plutonium and aluminum-- silicon--plutonium were discharged from the MTR and are undergoing examination. These capsules withstood a fractional bunnout of plutonium atoms of 55 to 60% as determined by flux monitoring wires attached to the capsule holder. Additional capsules of these fuel alloys containing a higher concentration of plutonium are being fubricated. Concentrations of aluminum--12 wt.% silicon will be irradiated to determine the upper limits of plutonium concentration before dimensional instability or swelling becomes a problem. Work is continuing on four red clusters containing Al--8 wt.% Pu and Al--12 wt.% Si--8 wt.% Pu alloy cores in Zircaloy Jackets. These clusters will be irradiated in the high temperature (250 deg C) KER loop fucility. Corrosion properties of the Zircaloy tubing in end cap welds are being evaluated in out-of-pile loops utilizing Zircaloy-clad Al reds as stand-ins. The corrosion behavior of several U--Al and U--Al-- Si alloys in high-temperature water was investigated. Uranium alloys were being used in place of Pu alloys for this preliminary investigation because hightemperature autoclaves mounted in hoods are not available. Results indicated good corrosion resistance of alloys containing Si and of as-east 6 wt.% U--Al alloy. Some roomtemperature mechanical and physical properties of Al-- Pu alloys containing 2 to 12 wt.% Pu were determined. The ultimate and yield strengths, hardness, and density data are presented for these alloys. Pyrometallurgical tech niques are being investigated as a means of reconstituting irradiated Pu fuel materials. Liquation experlinents were performed on Al-- Pu-- Si alloys with inconsistent results. The object of this experiment was to separate a Pu bearing phase from the principal alloying element. In another experiment 80% of the Pu in 400 grams of 10 wt.% Pu--Al alloy was extracted in the molten state with bismuth. Work on injection easting of molten Al--Pu alloy directly into Zircaloy tubes is continuing utilizing air pressure and mechanical injection easting methods. Cast densities on the order of 97% of theoretical were obtained, utilizing each of these methods for injection of aluminum into periment 80% of the Pu in 400 grams of 10 wt.% Pu--Al alloy was extracted in the molten state with bismuth. Work on injection easting of molten Al--Pu alloy directly into Zircaloy tubes is continuing utilizing air pressure and mechanical injection easting methods. Cast densities on the order of 97% of theoretical were obtained, utilizing each of these methods for injection of aluminum into stainless steel tubes seven to eight feet long. Hooded injection equipment is being designed for application of these techniques to Al-- Pu alloy fuel materials. Substitute techniques were worked out for fabrication of injection east Al-- Pu capsules for MTR evaluation. An improved design for the 19 red cluster fuel element was made which incorporates several new features. This design will result in a cost saving of approximately 25% over prior designs. Parts for two clusters were fabricated and will be utilized for hydraulic testing and other engineering tests. Thermalcycling tests were performed on an NPD design Mark-I element in the Elmo-7 loop. This 19 rod stainless steel clad aluminum core cluster was cycled 143 times at 550 deg F. The cluster showed no evidence of thermal distortion, elongationing or loosening of the spiral spacer wires. Work is continuing on the U--Pu test pieces requested by Nuclear Physics Research Operation for evaluation in the PCTR. All the U--Pu alloy slugs simulating burnups of 1000 and 2000 Mwd have been fabricated and shipped. Work is continuing on the 4000 Mwd alloy. (For preceding period see HW-55415.) (auth)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-14-018109
- OSTI ID:
- 4158206
- Report Number(s):
- HW-57343
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
Similar Records
PLUTONIUM FUELS DEVELOPMENT--PLUTONIUM METALLURGY OPERATION QUARTERLY REPORT (FOR) OCTOBER, NOVEMBER, DECEMBER, 1957
DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR MARCH 1959
Related Subjects
AIR
ALUMINUM ALLOYS
AUTOCLAVES
BISMUTH
CASTING
CORROSION
DEFORMATION
DENSITY
ECONOMICS
FUEL CANS
FUEL ELEMENT CLUSTERS
HARDNESS
HIGH TEMPERATURE
HYDRAULICS
INJECTION
IRRADIATION
LEACHING
LIQUID METALS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALLURGY
PLUTONIUM
PLUTONIUM ALLOYS
PRESSURE
PRESSURE VESSELS
QUANTITY RATIO
RODS
SILICIDES
STAINLESS STEELS
TENSILE PROPERTIES
THERMAL STRESSES
TUBES
URANIUM ALLOYS
WATER
WELDS
ZIRCALOY