SYMPOSIA PAPER Published: 01 January 1994

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


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.

Author Information

Parkins, RA
Siemens Power Corporation, Richland, Washington, USA
Shann, S-H
Siemens Power Corporation, Richland, Washington, USA
Price: $25.00
Contact Sales
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Developed by Committee: G01
Pages: 239–251
DOI: 10.1520/STP24886S
ISBN-EB: 978-0-8031-5265-6
ISBN-13: 978-0-8031-1853-9