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

D. W. Brown, M. A. Okuniewski, T. A. Sisneros, B. Clausen, G. A. Moore, L. Balogh

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)63-74
Number of pages12
JournalJournal of Nuclear Materials
Volume482
DOIs
Publication statusPublished - Dec 15 2016

Fingerprint

Neutron diffraction
Metal foil
residual stress
neutron diffraction
foils
Residual stresses
textures
Textures
Annealing
hot isostatic pressing
Research reactors
annealing
Hot isostatic pressing
Processing
Thermal expansion
thermal expansion
recovery
reactors
Recovery
Temperature

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

Neutron diffraction measurement of residual stresses, dislocation density and texture in Zr-bonded U-10Mo “mini” fuel foils and plates. / Brown, D. W.; Okuniewski, M. A.; Sisneros, T. A.; Clausen, B.; Moore, G. A.; Balogh, L.

In: Journal of Nuclear Materials, Vol. 482, 15.12.2016, p. 63-74.

Research output: Contribution to journalArticle

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