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Study mapping U-10Zr porosity informs metallic fuel design
Researchers at Idaho National Laboratory and the Massachusetts Institute of Technology have conducted a three-dimensional study of irradiated U-10Zr—uranium alloyed with 10 percent zirconium—across key radial regions, providing new insights into how the material swells, transfers heat, and interacts with the fuel cladding.
U-10Zr was extensively tested in historical sodium-cooled fast reactors and is now attracting attention for use in next-generation advanced reactors.
Luke R. Cornejo, Dmitriy Y. Anistratov, Kord Smith
Nuclear Science and Engineering | Volume 193 | Number 8 | August 2019 | Pages 803-827
Technical Paper | doi.org/10.1080/00295639.2019.1573601
Articles are hosted by Taylor and Francis Online.
In this paper we present nonlinear multilevel methods with multiple grids in energy for solving the k-eigenvalue problem for multigroup neutron diffusion equations. We develop multigrid-in-energy algorithms based on a nonlinear projection operator and several advanced prolongation operators. The evaluation of the eigenvalue is performed in the space with smallest dimensionality by solving the effective one-group diffusion problem. We consider two-dimensional Cartesian geometry. The multilevel methods are formulated in discrete form for the second-order finite volume discretization of the diffusion equation. The homogenization in energy is based on a spatially consistent discretization of the group diffusion equations on coarse grids in energy. We present numerical results of model reactor-physics problems with 44 energy groups. They demonstrate performance and main properties of the proposed iterative methods with multigrid in energy.