Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961

One of 10 reports in the title: Fuel Cycle Program Progress Report available on this site.
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Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The three instrumented fuel assemblies were assembled and calibrated. Equipment and procedures have been prepared for the VBWR stability tests. Forty-two assemblies were irradiated during the last VBWR run. Average exposure for all assemblies which have been irradiated are tabulated. Detailed examination of the centermelt calibration assembly is in progress. Preliminary metallography indicates that centermelting did not occur. The conductivity of UO/sub 2/ is appreciably higher than the design basis of 1.1 Btu/hr-ft/sup 2/ ( f F/ft). This result indicates that the fuel performance limit is … continued below

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Hodde, J. A. October 10, 1961.

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  • Main Title: Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961
  • Serial Title: Fuel Cycle Program Progress Report

Description

Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The three instrumented fuel assemblies were assembled and calibrated. Equipment and procedures have been prepared for the VBWR stability tests. Forty-two assemblies were irradiated during the last VBWR run. Average exposure for all assemblies which have been irradiated are tabulated. Detailed examination of the centermelt calibration assembly is in progress. Preliminary metallography indicates that centermelting did not occur. The conductivity of UO/sub 2/ is appreciably higher than the design basis of 1.1 Btu/hr-ft/sup 2/ ( f F/ft). This result indicates that the fuel performance limit is higher than the burnout heat flux limit. Heat Transfer and Fluid Dynamics. Use of a rough'' liner in the single rod test section resulted in a l0 to 43% increase in burnout heat flux at various operating conditions. The high-speed movies of the high pressure observational boiling experiments have been edited and assembled. Analytic work is being continued. A theoretical analysis of two-phase pressure drop and density distribution has been made. Experimental Physics. Isotopic analyses of unirradiated fuel pellets show good uniformity. Preliminary calculations of expected isotopic compositions during irradiation are being made. (auth)

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

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  • October 10, 1961

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  • Jan. 22, 2018, 7:23 a.m.

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  • Nov. 23, 2024, 2:18 a.m.

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Thumbnail image of item number 1 in: 'Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961'.
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Hodde, J. A. Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961, report, October 10, 1961; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1052762/: accessed May 24, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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