Correlation of Autoclave Testing of Zircaloy-4 to In-Reactor Corrosion Performance

    Published: Jan 1994

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    As the service environment for core materials for Pressurized Water Reactors (PWRs) becomes more severe due to increases in water temperature, changes in water chemistry, longer cycle lengths and higher burnups; the corrosion performance of Zircaloy-4 which is used for fuel cladding and structural components becomes more important. The standard three day, 400°C steam autoclave test which has been used to evaluate the uniform corrosion resistance of Zircaloy-4 is no longer sufficient. Some cladding which has given acceptable results in this test has not exhibited satisfactory in-reactor corrosion performance. A series of cladding types for which in-reactor corrosion measurements are available has been subjected to extended autoclave testing in steam at 400 and 415°C. A better correlation to the in-reactor performance is obtained if the 400 °C test is extended to at least 100 days or if the test temperature is raised to 415°C. At 415°C, a test duration of three days is best for evaluating Zircaloy-4 since extended time does not improve the correlation.


    Zircaloy-4, uniform corrosion, autoclave testing, in-reactor performance

    Author Information:

    Parkins, RA
    Senior Engineers, Siemens Power Corporation, Richland, Washington,

    Shann, S-H
    Senior Engineers, Siemens Power Corporation, Richland, Washington,

    Committee/Subcommittee: G01.08

    DOI: 10.1520/STP24886S

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