In-reactor tests of externally pressurized, short, unsupported lengths of Zircaloy tubing (AWBA Development Program)

Technical Report · Fri Oct 01 04:00:00 EDT 1982

OSTI ID:6213525

Smithnosky, M J

Results are reported for an in-reactor, short time test of externally pressurized, unsupported lengths of Zircaloy-4 tubing simulating axial gaps in a fuel element pellet stack. Stability of unsupported cladding over fuel stack axial gaps is a design concern for light water breeder reactors because of the desire to maximize neutron economy by minimizing cladding thickness and tightly spacing fuel rods. In turn, both of these design features limit allowable rod prepressurization due to LOCA concerns. The test investigated the tendency of tubing to deform into an axial gap. Four types of Zircaloy-4 tubing having various outside diameters and wall thicknesses were tested: three in the stress relief annealed condition, one recrystallization annealed.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, PA (USA)
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 6213525
• Report Number(s): WAPD-TM-1529; ON: DE83009554
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALLOYS
BREEDER REACTORS
DEFORMATION
FUEL CANS
LWBR TYPE REACTORS
MATERIALS
PERFORMANCE TESTING
REACTOR MATERIALS
REACTORS
STRESS ANALYSIS
TESTING
THERMAL REACTORS
TIN ALLOYS
TUBES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS