Experiment Data Report IFA-226 Postirradiation Examination. [PWR, BWR]. PDF Download

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Book Description
IFA-226 contained twelve, mixed plutonium-uranium oxide fuel rods arranged in two, six-rod clusters. The assembly was designed to study fuel-cladding mechanical interaction, fuel thermal response, and fission gas release as a function of fuel density, initial fuel-to-cladding gap, rod power, and burnup. Data were obtained from fuel rod centerline thermocouples, fission gas pressure transducers, and cladding elongation sensors. Results of both nondestructive and destructive examinations are presented. The PIE indicated that one fuel rod failed during service as a result of internal hydriding of the end plug. Circumferential cladding ridges resulting from fuel-cladding interaction were present on all of the rods, with the largest ridges present on the rod with the smallest initial fuel-to-cladding gap. No incipient fuel rod failures were detected.