Barrier-Fuel Lead Test Assemblies: Pre-Irradiation Characterization and First-Cycle Post-Irradiation Examination

摘要

Four lead test assemblies (LTAs) with barrier fuel were fabricated and inserted for irradiation into the core of the Quad Cities Nuclear Power Station, Unit 1. Each of the four LTAs had a different barrier cladding: Cu-barrier plated onto etched Zircaloy; Cu-barrier plated onto oxidized Zircaloy; Zr-liner (crystal bar zirconium) co-reduced with Zircaloy; Zr-liner (low oxygen sponge zirconium) co-reduced with Zircaloy. This report describes the pre-irradiation characterization of the LTAs and the first cycle post-irradiation examination after 11.7 MWd/kg U bundle average exposure. Two Cu-barrier LTAs and one Zr-liner LTA were given an overall visual inspection after the initial irradiation. The two Zr-liner LTAs were then disassembled and ten selected fuel rods (five from each assembly) were given detailed inspections. In addition to a visual inspection, the nondestructive examination included length measurements, profilometry, ultrasonics and eddy current evaluation. The detailed pre-irradiation characteristics of the selected fuel rods are presented here for comparison along with the post-irradiation measurements. (ERA citation 07:053714)