Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates
Abstract
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.
- Authors:
-
- 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)
- Publication Date:
- Research Org.:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
- OSTI Identifier:
- 1329601
- Alternate Identifier(s):
- OSTI ID: 1396816
- Report Number(s):
- LA-UR-16-25037
Journal ID: ISSN 0022-3115
- Grant/Contract Number:
- AC52-06NA25396; AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 482; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Citation Formats
Brown, Donald William, Okuniewski, Maria A., Sisneros, Thomas A., Clausen, Bjorn, Moore, Glenn A., and Balogh, Levente. Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates. United States: N. p., 2016.
Web. doi:10.1016/j.jnucmat.2016.09.022.
Brown, Donald William, Okuniewski, Maria A., Sisneros, Thomas A., Clausen, Bjorn, Moore, Glenn A., & Balogh, Levente. Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates. United States. https://doi.org/10.1016/j.jnucmat.2016.09.022
Brown, Donald William, Okuniewski, Maria A., Sisneros, Thomas A., Clausen, Bjorn, Moore, Glenn A., and Balogh, Levente. Thu .
"Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates". United States. https://doi.org/10.1016/j.jnucmat.2016.09.022. https://www.osti.gov/servlets/purl/1329601.
@article{osti_1329601,
title = {Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates},
author = {Brown, Donald William and Okuniewski, Maria A. and Sisneros, Thomas A. and Clausen, Bjorn and Moore, Glenn A. and Balogh, Levente},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2016.09.022},
journal = {Journal of Nuclear Materials},
number = C,
volume = 482,
place = {United States},
year = {Thu Dec 01 00:00:00 EST 2016},
month = {Thu Dec 01 00:00:00 EST 2016}
}
Web of Science
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Works referencing / citing this record:
Interface formation and bonding mechanisms of hot-rolled stainless steel clad plate
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Texture Evolution in U-10Mo Nuclear Fuel Foils during Plasma Spray Coating with Zr
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