IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR

Technical Report · Sun Apr 01 00:00:00 EST 1962

DOI:https://doi.org/10.2172/4818425· OSTI ID:4818425

Quigley, H C

A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. The amount of swelling increased during this interval from 0.8 to 3.6% (0.7% final cladding strain). This test indicated that the dimensional stability of the U-2 wt% Zr alloy is inferior to that of unalloyed U irradiated under similar conditions. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co., Wilmington, Del.
• DOE Contract Number: AT(07-2)-1
• NSA Number: NSA-16-024237
• OSTI ID: 4818425
• Report Number(s): DP-709
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

METALS, CERAMICS, AND OTHER MATERIALS
BURNUP
DEFORMATION
EXPANSION
EXTRUSION
FUEL CANS
HEAVY WATER COOLANT
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
NEUTRON BEAMS
POWER PLANTS
RADIATION EFFECTS
REACTORS
STABILITY
TEMPERATURE
TUBES
URANIUM ALLOYS
USES
VBWR
VOLUME
ZIRCALOY
ZIRCONIUM ALLOYS