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

Technical Report · Sat Oct 31 04:00:00 EST 1964

DOI:https://doi.org/10.2172/4127244· OSTI ID:4127244

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.)

• Research Organization: Nuclear Materials and Equipment Corp., Apollo, Penna.
• NSA Number: NSA-18-008772
• OSTI ID: 4127244
• Report Number(s): NUMEC-P-104
• Country of Publication: United States
• Language: English

Related Subjects

ACETONE
CARBON
CENTRIFUGATION
CESIUM
CHEMICAL REACTIONS
COATING
COLOR
COMBUSTION
CORROSION
DENSITY
DISTRIBUTION
EXPANSION
FABRICATION
FISSION PRODUCTS
GAMMA RADIATION
GRAIN BOUNDARIES
GRAIN SIZE
IMPURITIES
LABORATORY EQUIPMENT
MATERIALS TESTING
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
MIXING
NUMERICALS
ORGANIC FLUORINE COMPOUNDS
ORGANIC SULFUR COMPOUNDS
OXALATES
PELLETS
PHOTOMETRY
PLUTONIUM
PLUTONIUM OXIDES
POWDERS
PRECIPITATION
PREPARATION
QUANTITATIVE ANALYSIS
QUANTITY RATIO
SEPARATION PROCESSES
SINTERING
SOLUTIONS
SOLVENT EXTRACTION
SPECTROMETERS
SPHERES
STEAM
STRONTIUM
TEMPERATURE
TTA
URANIUM
WATER
WEIGHT