Irradiation performance of U-Pu-Zr metal fuels for liquid-metal-cooled reactors

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This report discusses a fuel system utilizing metallic U-Pu-Zr alloys which has been developed for advanced liquid metal-cooled reactors (LMRs). Result`s from extensive irradiation testing conducted in EBR-II show a design having the following key features can achieve both high reliability and high burnup capability: a cast nominally U-20wt %Pu-10wt %Zr slug with the diameter sized to yield a fuel smear density of {approx}75% theoretical density, low-swelling tempered martensitic stainless steel cladding, sodium bond filling the initial fuel/cladding gap, and an as-built plenum/fuel volume ratio of {approx}1.5. The robust performance capability of this design stems primarily from the negligible loading ... continued below

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17 p.

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Tsai, H.; Cohen, A.B.; Billone, M.C. & Neimark, L.A. October 1, 1994.

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Description

This report discusses a fuel system utilizing metallic U-Pu-Zr alloys which has been developed for advanced liquid metal-cooled reactors (LMRs). Result`s from extensive irradiation testing conducted in EBR-II show a design having the following key features can achieve both high reliability and high burnup capability: a cast nominally U-20wt %Pu-10wt %Zr slug with the diameter sized to yield a fuel smear density of {approx}75% theoretical density, low-swelling tempered martensitic stainless steel cladding, sodium bond filling the initial fuel/cladding gap, and an as-built plenum/fuel volume ratio of {approx}1.5. The robust performance capability of this design stems primarily from the negligible loading on the cladding from either fuel/cladding mechanical interaction or fission-gas pressure during the irradiation. The effects of these individual design parameters, e.g., fuel smear density, zirconium content in fuel, plenum volume, and cladding types, on fuel element performance were investigated in a systematic irradiation experiment in EBR-II. The results show that, at the discharge burnup of {approx}11 at. %, variations on zirconium content or plenum volume in the ranges tested have no substantial effects on performance. Fuel smear density, on the other hand, has pronounced but countervailing effects: increased density results in greater cladding strain, but lesser cladding wastage from fuel/cladding chemical interaction.

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17 p.

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INIS; OSTI as DE95013679

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  • 3. international conference on nuclear engineering, Kyoto (Japan), 23-27 Apr 1995

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  • Other: DE95013679
  • Report No.: ANL/ET/CP--82776
  • Report No.: CONF-950426--6
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 106470
  • Archival Resource Key: ark:/67531/metadc621686

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  • October 1, 1994

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  • June 16, 2015, 7:43 a.m.

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  • Dec. 14, 2015, 12:07 p.m.

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Tsai, H.; Cohen, A.B.; Billone, M.C. & Neimark, L.A. Irradiation performance of U-Pu-Zr metal fuels for liquid-metal-cooled reactors, article, October 1, 1994; Illinois. (digital.library.unt.edu/ark:/67531/metadc621686/: accessed August 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.