Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum. [Reduced Enrichment for Research and Test Reactor]

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Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400/sup 0/C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of ... continued below

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Pages: 17

Creation Information

Wiencek, T.C.; Domagala, R.F. & Thresh, H.R. September 1, 1984.

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Description

Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400/sup 0/C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of the plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (1) the reaction of the uranium silicide with aluminum to form U(AlSi)/sub 3/ and (2) the release of hydrogen and subsequent creep and pillowing of the fuel plate. 9 references, 4 figures, 6 tables.

Physical Description

Pages: 17

Notes

NTIS, PC A02/MF A01.

Source

  • International meeting on reduced enrichment for research and test reactors, Argonne, IL, USA, 14 Oct 1984

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  • Other: DE85004037
  • Report No.: CONF-8410173-4
  • Grant Number: W-31-109-ENG-38
  • DOI: 10.2172/6286269 | External Link
  • Office of Scientific & Technical Information Report Number: 6286269
  • Archival Resource Key: ark:/67531/metadc1111467

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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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Creation Date

  • September 1, 1984

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • April 19, 2018, 4:10 p.m.

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Wiencek, T.C.; Domagala, R.F. & Thresh, H.R. Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum. [Reduced Enrichment for Research and Test Reactor], report, September 1, 1984; Illinois. (digital.library.unt.edu/ark:/67531/metadc1111467/: accessed August 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.