Irradiation behavior of uranium oxide-aluminum dispersion fuel

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An oxide version of the DART code has been generated in order to assess the irradiation behavior of UO{sub 2}-Al dispersion fuel. The aluminum-fuel interaction models were developed based on U{sub 3}O{sub 8}-Al irradiation data. Deformation of the fuel element occurs due to fuel particle swelling driven by both solid and gaseous fission products, as well as a consequence of the interaction between the fuel particles and the aluminum matrix. The calculations show, that with the assumption that the correlations derived from U{sub 3}O{sub 8} are valid for UO{sub 2}, the LEU UO{sub 2}-Al with a 42% fuel volume loading ... continued below

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29 p.

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Hofman, G.L.; Rest, J. & Snelgrove, J.L. December 1, 1996.

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Description

An oxide version of the DART code has been generated in order to assess the irradiation behavior of UO{sub 2}-Al dispersion fuel. The aluminum-fuel interaction models were developed based on U{sub 3}O{sub 8}-Al irradiation data. Deformation of the fuel element occurs due to fuel particle swelling driven by both solid and gaseous fission products, as well as a consequence of the interaction between the fuel particles and the aluminum matrix. The calculations show, that with the assumption that the correlations derived from U{sub 3}O{sub 8} are valid for UO{sub 2}, the LEU UO{sub 2}-Al with a 42% fuel volume loading (4 gm/cc) irradiated at fuel temperatures greater than 413 K should undergo breakaway swelling at core burnups greater than about 1.12 x 10{sup 27} fissions m{sup {minus}3} ({approximately} 63% {sup 235}U burnup).

Physical Description

29 p.

Notes

INIS; OSTI as DE97001402

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  • 19. international meeting on reduced enrichment for research and test reactors (RERTR), Seoul (Korea, Republic of), 7-10 Oct 1996

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  • Other: DE97001402
  • Report No.: ANL/TD/CP--91547
  • Report No.: CONF-9610205--3
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 414400
  • Archival Resource Key: ark:/67531/metadc678508

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Office of Scientific & Technical Information Technical Reports

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Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • December 1, 1996

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  • July 25, 2015, 2:20 a.m.

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  • Dec. 16, 2015, 5:10 p.m.

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Hofman, G.L.; Rest, J. & Snelgrove, J.L. Irradiation behavior of uranium oxide-aluminum dispersion fuel, article, December 1, 1996; Illinois. (digital.library.unt.edu/ark:/67531/metadc678508/: accessed October 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.