Fission Gas Composition, Rod Internal Pressure, and Rod Free Volume of High Burnup Pressurized Water Reactor Fuel Rods

摘要

The High Burnup Spent Fuel Data Project, sponsoredby the US Department of Energy (DOE) Office of NuclearEnergy (NE), is focused on experimentally evaluating theeffects of long-term storage and transportation on highburnup (HBU) (defined as >45 gigawatt days per metric tonof uranium) pressurized water reactor (PWR) spent nuclearfuel (SNF). The project has acquired 25 HBU spent fuelrods from Dominion’s North Anna Nuclear Power Plantand delivered to Oak Ridge National Laboratory (ORNL)for extensive post-irradiation examination (PIE). Theseexaminations are being conducted to obtain a baseline ofthe HBU rods’ condition prior to dry storage.Extensive nondestructive examinations (NDEs) havebeen completed, and destructive examinations (DEs) areunderway. The DEs are focused on understanding overallSNF rod strength and durability. Both composite fuel andempty cladding will be tested to derive material properties.While the data generated can be used for multiple purposes,a primary goal for obtaining the sister rod PIE data and theassociated measured mechanical properties is to supportexisting fuel storage licensing and relicensing activities by(1) addressing identified knowledge gaps and (2) enhancingthe technical basis for post-storage transportation,handling, and consolidation activities.This paper presents results obtained to date from theDEs, including fission gas composition, internal pressure,and free volume measurements for 8 sister rods.