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

Brown, Donald William; Okuniewski, Maria A.; Sisneros, Thomas A.; Clausen, Bjorn; Moore, Glenn A.; Balogh, Levente

doi:10.1016/j.jnucmat.2016.09.022

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

Journal Article · Thu Dec 01 04:00:00 EST 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2016.09.022· OSTI ID:1329601

Brown, Donald William ^[1]; Okuniewski, Maria A. ^[2]; Sisneros, Thomas A. ^[1]; Clausen, Bjorn ^[1]; Moore, Glenn A. ^[3]; Balogh, Levente ^[4]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Purdue Univ., West Lafayette, IN (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Queens Univ., Kingston, ON (Canada)

Here, 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.

View Accepted Manuscript (DOE)

Research Organization:: Los Alamos National Laboratory (LANL)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA). Office of Defense Nuclear Nonproliferation (NA-20)

Grant/Contract Number:: AC52-06NA25396

OSTI ID:: 1329601

Alternate ID(s):: OSTI ID: 22648442
OSTI ID: 1396816

Report Number(s):: LA-UR-16-25037

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 482; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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