CHEMISTRY DIVISION, SECTION C-II SUMMARY REPORT FOR JULY, AUGUST AND SEPTEMBER 1946
Power Pile Problems. The resistance to thermal stresses of BeO bricks annealcd at temperature greater than 1300 deg C was far greater than unannealed BeO bricks. Calculations are given for BeO fuel tube resistance to thermal stresses. Preliminary studies were made to determine possible correction between the elastic modulus and the density of BeO shapes. Measurements of the linear dimensions of hot-pressed BeO-UO/sub 2/ pellets and cylinders before and after irradiatinn shown increase in length. The steady state activity due to 5d and 9h Xe in the coolant of the operating high temperature pile was calculated for shaped fuel rods. Diffusion of fission products from UO/sub 2/BeO fuel materials is described. Impregnation of graphite with U compounds for use as fuel rods is described. Graphite Problems. An Investigation of the properties of irradiated graphite is being carried out. Measurements of stored energy from the heat of dispersal in K were carried out. The apparatus for measuring the stored energy is given. A summary of an investigation to determine the heat of sublimation and vapor pressure for graphite is presented. Radiochemistry. Thc best values for the half lives of La/sup 140/, inum absorption curves for 12.8d Be/sup 140/ from Pu and U fission are given. Geiger-Mueller tube developmeat, sensitivity distribution in end window tubes, and construction of a magnetic lens BETA -ray spectrometer is included. Special Problems. Data are given on the magnetic moment of Pu, effect of neutron irradiation on the thermocouple power of the ChromelAumel junction, effects of gamma radiation oa insulating materials, and remote control development. (W.L.H.)
- Research Organization:
- Argonne National Lab., Lemont, Ill.
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-12-001818
- OSTI ID:
- 4327055
- Report Number(s):
- ANL-4000(Del.)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION
ALUMEL
ALUMINUM
ALUMINUM ALLOYS
BARIUM 140
BERYLLIUM 10
BERYLLIUM OXIDES
BETA DECAY
CHEMISTRY
CHROMEL
CHROMIUM ALLOYS
DENSITY
DIAGRAMS
DIFFUSION
ELASTICITY
ENERGY
EVAPORATION
FISSION
FISSION PRODUCTS
FUELS
GAMMA RADIATION
GEIGER-MUELLER COUNTERS
GRAPHITE
HALF-LIFE
HIGH TEMPERATURE
HOT WORKING
LABORATORY EQUIPMENT
LANTHANUM 140
LENSES
MAGNETISM
MANGANESE ALLOYS
MATHEMATICS
MEASURED VALUES
MOLYBDENUM 99
NEUTRONS
NICKEL ALLOYS
PELLETS
PLUTONIUM
POTASSIUM
POWER PLANTS
PRASEODYMIUM 143
PRESSURE
RADIATION EFFECTS
RADIOCHEMISTRY
REACTORS
REMOTE CONTROL
RODS
SILICIDES
SPECIFIC HEAT
SPECTROMETERS
THERM
ALUMEL
ALUMINUM
ALUMINUM ALLOYS
BARIUM 140
BERYLLIUM 10
BERYLLIUM OXIDES
BETA DECAY
CHEMISTRY
CHROMEL
CHROMIUM ALLOYS
DENSITY
DIAGRAMS
DIFFUSION
ELASTICITY
ENERGY
EVAPORATION
FISSION
FISSION PRODUCTS
FUELS
GAMMA RADIATION
GEIGER-MUELLER COUNTERS
GRAPHITE
HALF-LIFE
HIGH TEMPERATURE
HOT WORKING
LABORATORY EQUIPMENT
LANTHANUM 140
LENSES
MAGNETISM
MANGANESE ALLOYS
MATHEMATICS
MEASURED VALUES
MOLYBDENUM 99
NEUTRONS
NICKEL ALLOYS
PELLETS
PLUTONIUM
POTASSIUM
POWER PLANTS
PRASEODYMIUM 143
PRESSURE
RADIATION EFFECTS
RADIOCHEMISTRY
REACTORS
REMOTE CONTROL
RODS
SILICIDES
SPECIFIC HEAT
SPECTROMETERS
THERM