IN-CELL FABRICATION AND TESTING OF IRRADIATED FUEL ELEMENT CLADDING TENSILE SPECIMENS

Journal Article · Mon Jan 01 04:00:00 EST 1962 · Proc. Hot Lab. Equip. Conf., 10th, Washington, D.C., 1962

OSTI ID:4768009

Corrigan, J E; Nelson, R C

An in-cell tensile testing system was developed to measure the mechanical properties of irradiated Zircaloy-2 cladding obtained from purposely defected and intact fuel rods from the Vallecitos Boiling Water Reactor core. Curved sections of the irradiated cladding were machined into longitudinai tensile specimens using a remotely operated high speed contour milling machine. Tensile tests were performed in-cell using a tensile tester with special grips to hold the curved test specimens. Zircaloy cladding specimens with hydrogen levels up to 640 ppm and having total elongations as low as 2.0% were successfully fabricated and tested in-cell with the equipment. It was possible to fabricate specimens of this brittle nature because the original curvature of the cladding was maintained during all phases of specimen preparation and testing. (auth)

• Research Organization: General Electric Co., Pleasanton, Calif.
• NSA Number: NSA-17-002765
• OSTI ID: 4768009
• Journal Information: Proc. Hot Lab. Equip. Conf., 10th, Washington, D.C., 1962, Journal Name: Proc. Hot Lab. Equip. Conf., 10th, Washington, D.C., 1962
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BRITTLENESS
COATING
FABRICATION
FUEL ELEMENTS
FUELS
GENERAL AND MISCELLANEOUS
HYDROGEN
IRRADIATION
MECHANICAL PROPERTIES
PREPARATION
REACTOR CORE
REMOTE HANDLING
RODS
TENSILE PROPERTIES
TESTING
ZIRCALOY