HEAVY WATER MODERATED POWER REACTORS. Progress Report, January 1962

Technical Report · Thu Feb 01 00:00:00 EST 1962

OSTI ID:4792100

Hood, R R; Isakoff, L comps

Pressure testing of the HWCTR containment building continued with emphasis on the elimination of the remaining air lesks. A schedule for the initial irradiation of fuel elements within HWCTR was established. Anisotropic changes in the neutron diffusion coefficient were measured in the PDP for removal of D/sub 2/O from the coolant annuli of a two-tube assembly of natural uranium oxide fuel. The second six pairs of Zircaloy-clad inner and outer thin-walled fuel tubes of natural U metal intended for irradiation testing in the HWCTR were completed. Further evidence was obtained from postirradiation examination of compacted oxide tubes that the new steps incorporated in the fabrication process were effective in preventing localized hydriding of the Zircaloy sheaths. Interim examination of two oxide tubes that had been irradiated to sbout 750 Mwd/ t in the VBWR revealed that no detrimental changes had occurred. Pressure drops were measured for forced-convection boiling of water at 1000 psia in 19-rod bundles. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, Del.
• NSA Number: NSA-16-015896
• OSTI ID: 4792100
• Report Number(s): DP-705
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

REACTOR TECHNOLOGY
AIR
BOILING
BUILDINGS
CHEMICAL REACTIONS
COMPACTING
CONFIGURATION
CONFINEMENT
CONTAINMENT
DIFFUSION
FABRICATION
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
HEAVY WATER MODERATOR
HWCTR
HYDROGEN
INSPECTION
IRRADIATION
LEAKS
MEASURED VALUES
NATURAL URANIUM FUEL
NEUTRONS
PDP
POWER PLANTS
PRESSURE
REACTORS
TESTING
TUBES
URANIUM OXIDES
VARIATIONS
VBWR
ZIRCALOY