Design and Fabrication of Fuel Rods Containing Sintered UO2 Extrusions - Assembly 11L

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Description

The extrusion forming of ceramic powders may be economically interesting in the field of nuclear fuel fabrication. When applied to the forming of rod-type uranium dioxide fuel, extrusion processes have been able to produce cylindrical bodies with length-to-diameter ratios much greater than those of the conventional die-pressed pellets. Furthermore, after being sintered, the extrusions have exhibited densities at least as high as those of sintered pellets. Thus, extrusion forming may offer reductions in handling during fabrication and, at the same time, provide a fuel with improved performance characteristics by decreasing the number of discontinuities in the fuel column. This report … continued below

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66 pages ; illustrations

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Megerth, F. H. February 1964.

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The extrusion forming of ceramic powders may be economically interesting in the field of nuclear fuel fabrication. When applied to the forming of rod-type uranium dioxide fuel, extrusion processes have been able to produce cylindrical bodies with length-to-diameter ratios much greater than those of the conventional die-pressed pellets. Furthermore, after being sintered, the extrusions have exhibited densities at least as high as those of sintered pellets. Thus, extrusion forming may offer reductions in handling during fabrication and, at the same time, provide a fuel with improved performance characteristics by decreasing the number of discontinuities in the fuel column. This report reviews the production of these extrusions, sets forth some of their characteristics, describes the materials and processes employed in cladding them, and records the pre-irradiation data pertaining to the finished fuel rods and fuel assembly. Irradiation of the fuel assembly in the VBWR was initiated on July 17, 1962.

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66 pages ; illustrations

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U.S. Atomic Energy Commission Contract AT(04-3)-189 Project Agreement 11.

Includes bibliographic references (page 1).

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  • Report No.: GEAP-4556
  • Grant Number: AT(04-3)-189 PA 11
  • SuDoc Number: Y 3.At 7:22/GEAP-4556
  • Accession or Local Control No: metadc1201424
  • Archival Resource Key: ark:/67531/metadc1201424

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  • February 1964

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  • Aug. 15, 2019, 10:26 p.m.

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  • Sept. 15, 2023, 1:16 a.m.

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Megerth, F. H. Design and Fabrication of Fuel Rods Containing Sintered UO2 Extrusions - Assembly 11L, report, February 1964; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1201424/: accessed January 13, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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