RUPTURE KINETICS OF ZIRCALOY-CLAD FUEL ELEMENTS IN HIGH TEMPERATURE WATER AND STEAM. Interim Report No. 6. Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanisms

Technical Report · Wed Dec 30 04:00:00 EST 1959

OSTI ID:4814722

Troutner, V H

Reduction of the carbon content to very low values (about 30 ppm) eliminated non-uniform hydride attack of bare uranium at 200 deg C. The addition of 1 to 2% zirconium reduced the uniform corrosion rate of uranium by a factor of 5 to 7, and eliminated the non-uniform hydride attack. An optimum concentration appeared to be between 1.0 and 1.6%. Rupture curves were obtained with pinhole- defected rod elements made from uranium with low carbon content, and uranium with zirconium added. In contrast to the behavior of the bare corrosion samples, the reduction in carbon content did not eliminate the non-uniform hydride attack at 200 deg C. The addition of zirconium reduced the rupture rates markedly. Mechanisms are presented for various types of fuel element ruptures. The effects of heat treatment and water flow are discussed in view of these mechanisms. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-16-009197
• OSTI ID: 4814722
• Report Number(s): HW-63137
• Country of Publication: United States
• Language: English

Related Subjects

CARBON
CORROSION
FAILURES
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
HEAT TREATMENTS
HIGH TEMPERATURE
HYDRIDES
MECHANICS
METALS, CERAMICS, AND OTHER MATERIALS
QUANTITY RATIO
REACTION KINETICS
STEAM
URANIUM
URANIUM ALLOYS
WATER
ZIRCALOY
ZIRCONIUM ALLOYS