Creep analysis of fuel plates for the Advanced Neutron Source

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Description

The reactor for the planned Advanced Neutron Source will use closely spaced arrays of fuel plates. The plates are thin and will have a core containing enriched uranium silicide fuel clad in aluminum. The heat load caused by the nuclear reactions within the fuel plates will be removed by flowing high-velocity heavy water through narrow channels between the plates. However, the plates will still be at elevated temperatures while in service, and the potential for excessive plate deformation because of creep must be considered. An analysis to include creep for deformation and stresses because of temperature over a given time ... continued below

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43 p.

Creation Information

Swinson, W.F. & Yahr, G.T. November 1, 1994.

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Description

The reactor for the planned Advanced Neutron Source will use closely spaced arrays of fuel plates. The plates are thin and will have a core containing enriched uranium silicide fuel clad in aluminum. The heat load caused by the nuclear reactions within the fuel plates will be removed by flowing high-velocity heavy water through narrow channels between the plates. However, the plates will still be at elevated temperatures while in service, and the potential for excessive plate deformation because of creep must be considered. An analysis to include creep for deformation and stresses because of temperature over a given time span has been performed and is reported herein.

Physical Description

43 p.

Notes

INIS; OSTI as DE95008646

Source

  • Other Information: PBD: Nov 1994

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  • Other: DE95008646
  • Report No.: ORNL/TM--12788
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/43782 | External Link
  • Office of Scientific & Technical Information Report Number: 43782
  • Archival Resource Key: ark:/67531/metadc677311

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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

  • November 1, 1994

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • Jan. 19, 2016, 12:11 p.m.

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Swinson, W.F. & Yahr, G.T. Creep analysis of fuel plates for the Advanced Neutron Source, report, November 1, 1994; Tennessee. (digital.library.unt.edu/ark:/67531/metadc677311/: accessed November 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.