Corrosion and hydriding of irradiated Zircaloy fuel-rod cladding (LWBR Development Program)

Technical Report · Wed Sep 01 04:00:00 EDT 1982

OSTI ID:6797265

Clayton, J C

Zircaloy corrosion performance predicted with the CHORT computer program was compared with measured data from 214 out-of-pile LWBR reference Zircaloy-4 tubing specimens, 47 LWBR irradiation test fuel rods, three MELBA fuel rods, and fuel rod cladding from three commercial pressurized water reactors. CHORT calculations compared well with the out-of-pile autoclave test data, but corrosion thicknesses and hydrogen uptake in LWBR irradiation test program fuel rod cladding were less accurately accounted for by the CHORT program due in part to measurement scatter and material variability. Measured corrosion oxide thicknesses for Maine Yankee, KWO, Turkey Point, and MELBA fuel rods were in reasonable agreement with CHORT predictions.

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 6797265
• Report Number(s): WAPD-TM-1440; ON: DE83001689
• Country of Publication: United States
• Language: English

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ALLOYS
BREEDER REACTORS
BREEDING BLANKETS
C CODES
CHEMICAL REACTIONS
COMPUTER CODES
CORROSION
DATA
ENRICHED URANIUM REACTORS
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LWBR TYPE REACTORS
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POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
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THERMAL REACTORS
TIN ALLOYS
TURKEY POINT-3 REACTOR
TURKEY POINT-4 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
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