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FY2015 Status Report: CIRFT Testing of High-Burnup Used Nuclear Fuel Rods from Pressurized Water Reactor and BWR Environments

High-burnup spent nuclear fuel cladding has a significant amount of microcracks and hydrides which will reduce the stress intensity required for crack growth.  Characteristics of cladding, fuel pellets, and interface between cladding and fuel pellets are likely to change after high burnup; these material modifications may impact the structural integrity and vibration response of SNF rods in transport.  The research object is to develop a system for testing the response of high-burnup fuel rods under simulated loading conditions.  The report provides recent test results derived from the Cyclic Integrated Reversible Bending Fatigue Tester (CIRBFT) used to determine the vibration integrity of a spent fuel rod (from BWR and PWR) under normal transport conditions.  R1, 11/12/2015