Nuclear Technology · 2008 · 36 citations · 10 references
EngineeringMaterials ScienceNuclear EngineeringNuclear ChemistryNuclear Fuel CycleNuclear MaterialsFuel ChemistryHigh-level Radioactive WasteNuclear FissionNuclear Fuel ChemistryNuclear Fuel MaterialsSpent Fuel BehaviorFission Gas BehaviorFission Gas ReleaseFission Product BehaviorFission Product ReleaseFission ReactionsPressurized Water ReactorsUranium Oxide FuelVolatile Species Release
Quantitative analysis of the fission gas release characteristics during the voloxidation and oxidation and reduction of oxide fuel (OREOX) processes of spent pressurized water reactor (PWR) fuel was carried out by spent PWR fuel in a hot cell of the DUPIC Fuel Development Facility. The release characteristics of 85Kr and 14C fission gases during voloxidation process at 500°C are closely linked to the degree of conversion efficiency of UO2 to U3O8 powder, and it can be interpreted that the release from grain boundary would be dominated during this step. Volatile fission gases of 14C and 85Kr were released to near completion during the OREOX process. Both the 14C and 85Kr have similar release characteristics under the voloxidation and OREOX process conditions. A higher burnup spent fuel showed a higher release fraction than that of a low burnup fuel during the voloxidation step. It was also observed that the release fraction of semivolatile Cs was ~16% during a reduction at 1000°C of the oxidized powder, but over 90% during the voloxidation at 1250°C.
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Phase characterisation of simulated high burn-up UO2 fuel
J. Cobos, D. Papaioannou, J. Spino et al. · Journal of Alloys and Compounds · 1998 · 45 citations