The project is aimed to understand intercompound formation and radiation responses of diffusion couples made of deleted uranium (DU) and various metals (Fe, Zr, Ni, and Cr). First, a polished single crystal DU is mechanical bonded with metals and form diffusion couples through thermal annealing in vacuum over a prolonged period, i.e. a few days, depending on kinetics of metal diffusion and regions of interest in phase diagrams. Second, part of the diffusion couples are irradiated by light ions to 1 dpa (displacements per atom). Third, microstructure and microchemistry of samples, with or without irradiation, are compared, by using scanning electron microscopy (SEM), focused-ion beam (FIB), and transmission electron microscopy (TEM). The project expect to have the following significant impact: (1) it will provide validation on phase diagram and phase field theories concerning uranium: (2) it will reveal radiation induced structural changes of different phases; (3) it will accelerate our understanding of fuel-cladding interactions; (4) it will help to separate effects from grain boundaries for understanding materials’ intrinsic properties, since single crystals are used for fabrications of diffusion couples. Sample fabrications and ion irradiations will be performed at the Texas A&M University. The focus ion beam (FIB) and lift off technique will be used to prepare specimens and atomic scale characterization will be performed by the Idaho National Laboratory team. The project involves three investigators and one graduate student.
The U.S. Advanced Fuel Cycle Initiative (AFCI) seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products, thereby dramatically decreasing the volume, the long-term radiotoxicity, and the heat load of material that must be stored in a geologic repository. To support the needs for validation and verification of current fuel-cladding interactions and to further conclude a fuel model basic fuel matrix data are needed to allow for the prediction of fuel properties under reactor conditions. Therefore experimental input data on diffusion coefficients and activation energies in the base fuel-cladding system is critical.