EXPONENTIAL EXPERIMENTS WITH ORGANIC MODERATED URANIUM LATTICES

Technical Report · Fri Oct 31 04:00:00 EST 1958

OSTI ID:4315607

Brown, W W

S>A series of exponeatial experimeets was carried out on latiices of cylindrical uranium methl rods in a moderator of diphenyl. Three different concentrations of U/sup 235/ in uranium were available for study, 0.50, 0.72, and 0.91 at.%. The fuel rods were arranged in square lattice arrays at moderator to fuel volume ratios 1.5, 2, 3, and 4. A cadmium clad 2 1/4 ft diameter aluminum tank was used to hold the lattices. External heaters maintained the contents at 185 deg F, just above the melting point of diphenyl. The lattices were driven by neutrons from the thermal column of a water boiler reactor. Foil activation techniques were employed to make the buckling and intracell flux distribution measurements. Measurements in pure and borated diphenyl were made in order to obtain the thermal neutron diffusion length and transport mean free path in diphenyl. Buckling and intracell measurements were made for some lattices in the borated diphenyl in order to determine the neutron age in these lattices. (auth)

• Research Organization: Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
• NSA Number: NSA-12-015020
• OSTI ID: 4315607
• Report Number(s): A/CONF.15/P/595
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ACTIVATION
ALUMINUM
BOILING
BORATES
BORON
BUCKLING
CADMIUM
CONFERENCE
CONFIGURATION
CYLINDERS
DIFFUSION LENGTH
ENRICHMENT
EXPONENTIAL PILES
FERMI AGE
FOILS
FUEL ELEMENTS
HEATING
HIGH TEMPERATURE
IMPURITIES
MEASURED VALUES
MELTING POINTS
METALS
MODERATORS
NEUTRON FLUX
NEUTRON SOURCES
ORGANIC MODERATOR
PHYSICS
POISONING
POLYPHENYLS
REACTOR CORE
REACTORS
RODS
SLOWDOWN
THERMAL NEUTRONS
URANIUM
URANIUM 235
VESSELS
WATER COOLANT
ZONES