|About this Abstract
||Materials Science & Technology 2012
||Materials Issues in Nuclear Waste Management in the 21st Century
||Burst, Ring and Biaxial Creep of Zircaloy Cladding – Applications to Dimensional Change Predictions during Dry Storage
||Boopathy Kombaiah, Chang-Sung Seok, Korukonda Linga Murty
|On-Site Speaker (Planned)
Predictions of dimensional changes of Zircaloy cladding tubes during dry storage of spent nuclear fuel are complex due to transitions in creep mechanisms as lower stresses and/or temperatures are approached. We summarize the work performed on Zircaloy cladding commonly used in LWRs as thin walled tubing by considering three different types of tests: (i) burst tests and (ii)hoop creep under closed-end internal pressurization, (iii) uniaxial ring tests for characterization of hoop creep properties. Biaxial creep and closed-end internal pressurization burst tests revealed distinct transitions in creep mechanisms from dislocation climb-glide to viscous creep mechanisms as lower stresses are approached. Importance of transitions in creep mechanisms with decreased stress levels in predicting in-service dimensional changes Zircaloy tubing under dry storage conditions is emphasized. We acknowledge the financial support by the United States National Science Foundation grants DMR-0412583 and DMR-0968825, and DOE/NEUP-IRP contract on Fuel Aging during Storage and Transportation.