Corrosion of Zircaloy-4 tubing in 68OF water (LWBR development program)

Technical Report · Fri Dec 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/6216287· OSTI ID:6216287

Marino, G. P.; Fischer, R. L.

Seamless Zircaloy-4 tubing is utilized as fuel rod cladding in light water reactors. Water corrosion tests at 68OF have been performed to determine the corrosion and hydriding characteristics of Zircaloy-4 tubing, fabricated by cold reduction and finished in two metallurgical conditions: a stress-relief anneal (SRA) and a recrystallization anneal (RXA). These corrosion tests revealed differences in the post-transition corrosion product weight gains of the two materials. A computer corrosion model, designated CHORT, was developed from the test data and ascribes the observed difference in material weight gain to an assumed difference in the periodicity of a postulated cyclic buckling of the oxide.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, PA (USA)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 6216287
• Report Number(s): WAPD-TM-1322
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ALLOYS
BREEDER REACTORS
CHEMICAL REACTIONS
CORROSION
FUEL CANS
HIGH TEMPERATURE
HYDROGEN COMPOUNDS
LWBR TYPE REACTORS
OXYGEN COMPOUNDS
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THERMAL REACTORS
TIN ALLOYS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS