Actions for DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, January 1 through March 31, 1963

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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, January 1 through March 31, 1963

Published
United States : [publisher not identified], 1964.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1964.
Physical Description
microfiche : negative ; 8 x 13 cm

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Summary
Three batches of PuO/sub 2/ were prepared via the plutonium peroxide route. Except for the high tap density, it was found that the powder characteristics of PuO/sub 2/ prepared in this manner are similar to the characteristics of PuO/sub 2/ prepared by the oxalate route. Modifications were made to equipment for preparation of mixed oxides to achieve better reproducibility and minimize operator time. A study was initiated to assess the feasibility of using gamma spectrometry for rapid in-process determination of plutonium in solutions that also contain uranium. It was found that plutonium can be determined to within 1% Provided that the uranium concentration is known to better than 2 mg/ml. Plutonium separation studies using TTA extraction were continued and the determination of cesium and strontium fission products by flame photometry was investigated. The effect of carbon content on the weight loss of PuO/sub 2/ during sintering was determined. Metallographic examination of sintered UO/sub 2/--35 wt% PuO/sub 2/ pellets indicated that the low densities obtained may be due to grain growth and broadening of grain boundaries. Green spheres of PuO/sub 2/ were formed in a small mill jar and the particle size distributions of both the formable and non-formable powder fractions were determined by centrifugal sedimentation size analysis. Preparation of duplex pellets for determining the reaction between PuO/sub 2/-- UO/sub 2/ and possible cladding and diluent metals was continued. Pellets of pure PuO/sub 2/ and six compositions of coprecipitated PuO/sub 2/-- UO/sub 2/ were fabricated for corrosion testing in water and steam. Preliminary tests in steam at 750 deg F and 2200 psi for 10 hr showed no visual evidence of corrosion. The NUSURP code was modified to allow calculation of undermoderated systems. Equipment is being installed in alpha boxes. (M.C.G.)
Report Numbers
NUMEC-P-104
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(30-1)-2389
NSA number: NSA-18-008772
OSTI Identifier 4127244
Research organization: Nuclear Materials and Equipment Corp., Apollo, Penna.
View MARC record | catkey: 41357527