Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates

• Published in: Journal of nuclear materials 2016-12, Vol.482 (C), p.63-74
• Main Authors: Brown, D.W., Okuniewski, M.A., Sisneros, T.A., Clausen, B., Moore, G.A., Balogh, L.
• Format: Article
• Language: English
• Subjects: Annealing; Cladding; Density; Diffraction; Dislocation; Dislocation density; Enriched fuel reactors; Foils; Hot isostatic pressing; Neutron diffraction; Neutrons; NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Nuclear fuels; Recrystallization; Residual stress; Studies; Texture; Thermal expansion; Zirconium
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2016.09.022

Al clad U-10Mo fuel plates are being considered for conversion of several research reactors from high-enriched to low-enriched U fuel. Neutron diffraction measurements of the textures, residual phase stresses, and dislocation densities in the individual phases of the mini-foils throughout several processing steps and following hot-isostatic pressing to the Al cladding, have been completed. Recovery and recrystallization of the bare U-10Mo fuel foil, as indicated by the dislocation density and texture, are observed depending on the state of the material prior to annealing and the duration and temperature of the annealing process. In general, the cladding procedure significantly reduces the dislocation density, but the final state of the clad plate, both texture and dislocation density, depends strongly on the final processing step of the fuel foil. In contrast, the residual stress state of the final plate is dominated by the thermal expansion mismatch of the constituent materials.