Annual Progress Report on Fuel Element Development for Fiscal Year 1961

One of 6 reports in the series: Fiscal Year 1961 available on this site.

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Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being ... continued below

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Pages: 112

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Gibson, G. W. & Shupe, O. K. March 1, 1962.

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  • Main Title: Annual Progress Report on Fuel Element Development for Fiscal Year 1961
  • Series Title: Fiscal Year 1961

Description

Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being investigated. Test results for the MTR conditions indicate that all of the compositions investigated to date will successfully withstand even the longest irradiation at these conditions if properly fabricated. Some high strength aluminum alloy claddings, not yet fully tested, show some peculiar surface effects which may be related to corrosion. Metallographic studies of irradiated cermets reveal a reaction'' (diffusion) zone produced around UO/sub 2/ particles in contact with aluminum. These zones are being studied by means of x-ray diffraction, electron microscopy, and electron microprobe analysis. From engineering studies has come promise of improved heat removal and lower pumping requlrements for reactors through artificial roughening of fuel plates. Computer optimizatlon studies and hydraulic tests indicated 80% improvement in heat transfer or 60% less flow for the same heat load are obtainable for MTR conditions. Heat transfer test results from 0.110 x 2.624 ' electrically-heated channels using heat fluxes up to 2.88 x 10/sup 6/ Btu/hr-ft/ sup 2/, sgree better with correlations based on bulk temperatures than with the more widely used modified Colburn equation. In this range, a modifled Colburn equation with a 20% safety factor, as is presently used, seems adequate. However, an equation based on the bulk coolant temperature could be used employing a smaller safety factor because of its greater accuracy. ( auth)

Physical Description

Pages: 112

Source

  • Other Information: Orig. Receipt Date: 31-DEC-62

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  • Report No.: IDO-16727
  • Grant Number: AT(10-1)-205
  • DOI: 10.2172/4782699 | External Link
  • Office of Scientific & Technical Information Report Number: 4782699
  • Archival Resource Key: ark:/67531/metadc1053712

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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

  • March 1, 1962

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

Description Last Updated

  • Jan. 31, 2018, 2:14 p.m.

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Gibson, G. W. & Shupe, O. K. Annual Progress Report on Fuel Element Development for Fiscal Year 1961, report, March 1, 1962; Idaho Falls, Idaho. (https://digital.library.unt.edu/ark:/67531/metadc1053712/: accessed March 22, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.