DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR SEPTEMBER 1958
The macroscopic fission cross sections for the PuO/sub 2/-U0/.sub 2/ mixed crystal oxide capsules were determined. The sinterability of U0/sub 2/ and U0/sub 2/-PuO/sub 2/ was compared. The extrusion of Al-U alloy billets is described. In the process of Pu recovery from irradiated Al-Pan alloys by molten bismuth and silicon addition, experiments are being made to determine whether the Pu concentration in the resulting Al-Si alloy can be made higher than the Pu concentration in the starting Al alloy. Extranded aluminum rods were successfully loaded into Zircaloy tubes. The post-irradintion of U0/sub 2/ canned in Zircaloy-3 is continuing, and additional information is reported. Corrosion tests of steel shat in inhibited, softened water were completed. An ammonium fluoride hydrogen peroxide-acetic acid solution at pH 5 is bein- g evaluated as a pretreatment ctch for Zircaloy-2. Values of k and f were calculated from the experimental PCTR data taken with 19-rod U0/sub 2/ clusters in a 9-inch D/sub 2/0 lattice. Swelling of uranium during irradiation was studied. Gas-graphite reactions were studied for the gas-cooled central station power reactor program. (For preceding period see HW-57225-A2.) (W.D.M.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-001807
- OSTI ID:
- 4325527
- Report Number(s):
- HW-57636 A2
- Country of Publication:
- United States
- Language:
- English
Similar Records
DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR NOVEMBER 1958
DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR JANUARY 1959
Related Subjects
ACIDITY
ADSORPTION
ALUMINUM ALLOYS
AMMONIUM COMPOUNDS
BISMUTH
CANNING
CHEMICAL REACTIONS
CONFIGURATION
CORROSION
CROSS SECTIONS
DEFORMATION
ENRICHMENT
EXTRUSION
FAST FISSION FACTOR
FISSION
FLUORIDES
FUEL ELEMENTS
FUELS
GAS COOLANT
GASES
GRAPHITE
HEAVY WATER MODERATOR
HYDROGEN PEROXIDES
IRRADIATION
MATERIALS TESTING
MELTING
MULTIPLICATION FACTORS
NUMERICALS
PCTR
PLUTONIUM
PLUTONIUM OXIDES
POWER PLANTS
RADIATION EFFECTS
REACTOR CORE
REACTORS
REPROCESSING
RODS
SEPARATION PROCESSES
SILICIDES
SILICON
SINTERED MATERIALS
SINTERING
SOLUTIONS
STEELS
TUBES
URANIUM
URANIUM ALLOYS
URANIUM DIOXID