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Development of a Welding Process for Spire-Can Fuel Elements

Description: The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
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Effective Cadmium Cutoff Energies

Description: Effective cutoff energies for point l/v absorbers inside of spherical and cylindrical cadmium filters have been calculated for thermal reactor neutrons. The neutron spectrum was assumed to consist of a Maxwellian plus a 1/E component, and the parameters varied were the thickness of filter, the Maxwellian temperature and the Maxwellian to 1/E flux ratio. Because of the sensitivity of the effective cutoff to Maxwellian flux parameters for thin filters it is recommended that filter thicknesses of … more
Date: March 11, 1960
Creator: Stoughton, R.W.; Halperin, J. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
open access

Thermal conductivity studies on various calcined ``cold`` waste: Interim report

Description: Accelerated accumulation of high level radioactive wastes has given impetus to the development of safer and more economical waste storage methods. Several processes for converting these wastes to granular or porous-solid form are being investigated. In any waste volume-reduction process containment of the final material in a sealed metal shell is desirable as a precaution against accidental release of radioactive material. While the final waste forms are generally stable, they are, if uncontain… more
Date: March 11, 1960
Creator: DeMier, W. V.
Partner: UNT Libraries Government Documents Department
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The effect of high exposure on production efficiency

Description: We have estimated the effects on production efficiency of raising the plutonium product specification. The various cases have been considered using a pH of 6.6 at all reactors. In addition to this, the following estimates and assumptions have been used: (1) failure rates will vary with the fifth power of exposure and directly with fuel throughput, (2) charge-discharge losses will be proportional to throughput, (3) throughput will vary inversely with exposure, (4) the failure rates of the K5 sel… more
Date: March 11, 1963
Creator: Neef, W. I.
Partner: UNT Libraries Government Documents Department
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NEUTRON TISSUE DOSE AT LARGE DISTANCES FROM AN ELEVATED UNSHIELDED REACTOR

Description: The neutron tissue dose at large distances from a fission source was studied by using a water-filled phantom and four different detectors: a BF/sub 3/ counter, a polyethylenelined ethylene-filled proportional counter, indium foils, and nuclear emulsions. The source of fission neutrons was the ORNL Health Physics Research Reactor which was attached to a hoist which was in turn installed on a 1530-foot tower. The reactor could be operated at any elevation from 27 to 1500 ft. The phantom studies w… more
Date: March 11, 1963
Creator: Aceto, H. Jr.; Pick, M.A. & Stephens, L.D.
Partner: UNT Libraries Government Documents Department
open access

Remote Pipetters for Use in Hot Cell Enclosure

Description: No Description Available.
Date: March 11, 1964
Creator: Fleischer, E. S.; Snyder, A. B.; Parsons, T. C. & Howe, P. W.
Partner: UNT Libraries Government Documents Department
open access

NRD target support studies weekly report No. 3

Description: This report describes the results of work done during the period from March 2 through March 8, 1965 at Hanford. Discussed topics include: pressure testing of Zr-2 tubing at high temperature, Zr-Al corrosion, and poison -- target combinations.
Date: March 11, 1965
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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