Thermal tests to investigate stability of externally pressurized Zircaloy-4 tubing over axial gaps (LWBR Development Program)

Technical Report · Thu Jul 01 00:00:00 EDT 1982

OSTI ID:5238064

Selsley, I A

Externally pressurized thermal testing of 152 specimens of Zircaloy-4 fuel rod cladding has been conducted to determine effects of several parameters on cladding stability over potential axial gaps in LWBR (nonfreestanding) fuel rods. Parameters evaluated include temperature, radial gaps, pellet tapers, axial gaps, cladding wall, thickness, cladding diameter, and contractile strain ratio.

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 5238064
• Report Number(s): WAPD-TM-1509; ON: DE82019363
• Country of Publication: United States
• Language: English

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210500* -- Power Reactors
Breeding
ALLOYS
BREEDER REACTORS
DEFORMATION
FUEL CANS
LWBR TYPE REACTORS
REACTORS
STRAINS
STRESSES
SWELLING
THERMAL REACTORS
THERMAL STRESSES
TIN ALLOYS
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ZIRCALOY
ZIRCALOY 4
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ZIRCONIUM BASE ALLOYS