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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962

Description: A frequency analysis was made of the VBWR stability test data. Interpretation of the steady-state noise observed in the stability tests involved consideration of several possible sources of excitation. One of these, a theory of water surface waves, is summarized. Visual and destructive examinations were made of selected fuel rods. Fretting corrosion of the Zircaloy-clad fuel rods against stainless steel spacers was observed. Evidence that UO/sub 2/ thermal conductivity increases with time was o… more
Date: July 10, 1962
Creator: Hodde, J. A.
Item Type: Refine your search to only Report
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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eleventh Quarterly Progress Report, January-March 1963

Description: Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the… more
Date: April 1963
Creator: Howard, C. L.
Item Type: Refine your search to only Report
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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Quarterly Report No. 5, July 1961-September 1961

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 c… more
Date: October 10, 1961
Creator: Hodde, J. A.
Item Type: Refine your search to only Report
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Fuel Cycle Program, a Boiling Water Reactor Research Development Program. First Summary Report for March 1959-July 1960

Description: The Fuel Cycle Development Program is a basic development program for boiling and other water technology. It covers the areas of oxide fuel fabrication. irradiation. and examination; the physics of water-moderated reactore; and boiling-water heat transfer and stability. Schedules for the fuel- cycle program were examined. and it was concluded that portions of the Task A program should be conducted during the period May to Dec. 1959 in order to keep costs of the work as low as possible and to al… more
Date: Autumn 1961
Creator: Cook, W. H.
Item Type: Refine your search to only Report
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Fuel Cycle Program Progress Report: January-September 1977

Description: Report of the Argonne National Laboratory Chemical Engineering Division on fuel-cycle studies including pyro-chemical separation of plutonium and americium oxides from contaminated materials of construction such as steel, advanced solvent extraction techniques in the development of centrifugal contactors for use in Purex processes, and a review and evaluation of the encapsulation of high-level waste in a metal matrix.
Date: 1978?
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K. F.; Gerding, T. J.; Jardine, L. J. et al.
Item Type: Refine your search to only Report
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