Fabrication development for the Advanced Neutron Source Reactor

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Description

This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor. The fuel element is similar to that successfully fabricated and used in the High Flux Isotope Reactor (HFIR) for many years, but there are two significant differences that require some development. The fuel compound is U{sub 3}Si{sub 2} rather than U{sub 3}O{sub 8}, and the fuel is graded in the axial as well as the radial direction. Both of these changes can be accomplished with a straightforward extension of the HFIR technology. The ANS also requires some improvements in inspection technology and somewhat more stringent acceptance ... continued below

Physical Description

128 p.

Creation Information

Pace, B.W. & Copeland, G.L. August 1, 1995.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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Authors

  • Pace, B.W. Babcock and Wilcox, Lynchburg, VA (United States)
  • Copeland, G.L. Oak Ridge National Lab., TN (United States)

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Description

This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor. The fuel element is similar to that successfully fabricated and used in the High Flux Isotope Reactor (HFIR) for many years, but there are two significant differences that require some development. The fuel compound is U{sub 3}Si{sub 2} rather than U{sub 3}O{sub 8}, and the fuel is graded in the axial as well as the radial direction. Both of these changes can be accomplished with a straightforward extension of the HFIR technology. The ANS also requires some improvements in inspection technology and somewhat more stringent acceptance criteria. Early indications were that the fuel fabrication and inspection technology would produce a reactor core meeting the requirements of the ANS for the low volume fraction loadings needed for the highly enriched uranium design (up to 1.7 Mg U/m{sup 3}). Near the end of the development work, higher volume fractions were fabricated that would be required for a lower- enrichment uranium core. Again, results look encouraging for loadings up to {approx}3.5 Mg U/m{sup 3}; however, much less evaluation was done for the higher loadings.

Physical Description

128 p.

Notes

INIS; OSTI as DE96006226

Source

  • Other Information: PBD: Aug 1995

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Identifier

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  • Other: DE96006226
  • Report No.: ORNL/TM--13070
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/206430 | External Link
  • Office of Scientific & Technical Information Report Number: 206430
  • Archival Resource Key: ark:/67531/metadc668528

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Creation Date

  • August 1, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

Description Last Updated

  • Jan. 19, 2016, 1:36 p.m.

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Pace, B.W. & Copeland, G.L. Fabrication development for the Advanced Neutron Source Reactor, report, August 1, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc668528/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.