UNT Libraries Government Documents Department - 48 Matching Results

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An Automatic Polarograph for the Determination of Uranium in Process Waste Streams

Description: The automatic polarograph is ideally suited for the analysis of waste streams for uranium in the Metal Recovery Process, and with modification, it is applicable to other processes, pilot plants, and even to laboratory set ups. The instrument is simple, dependable, and relatively trouble free in operation. It provides an immediate record of the uranium in the waste and, through better control of the process, lower processing costs.
Date: December 10, 1953
Creator: Koyama, K.; Michelson, C. E. & Alkire, G. J.
Item Type: Refine your search to only Report
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Concentration and Final Purification of Neptunium by Anion Exchange

Description: It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless s… more
Date: February 10, 1959
Creator: Ryan, J.L.
Item Type: Refine your search to only Report
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Continuous Ion Exchange Development - A Qualitative Review

Description: Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facili… more
Date: November 10, 1959
Creator: Nicholson, G. A.
Item Type: Refine your search to only Report
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The Determination of Total Plutonium in the Presence of Aluminum

Description: Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial pl… more
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
Item Type: Refine your search to only Report
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Diffusion of Stack Gases in Very Stable Atmospheres: Case II

Description: In 1949 Barad presented two solutions to the general diffusion equation. Basic in both solutions is the assumption that in very stable atmospheres a point source may be replaced by a vertical area of uniform concentration at a short distance downwind. This vertical area is considered to exist at the distance at which the plume finally "levels-off" and assumes a flat ribbon-like appearance. In addition if the distance over which diffusion takes place is limited to one or two miles and if only… more
Date: August 10, 1953
Creator: Barad, M. L. & Shorr, B.
Item Type: Refine your search to only Report
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EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment

Description: The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date: May 10, 1960
Creator: Nichols, P. F.
Item Type: Refine your search to only Report
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ETR-MTR Experiments on Restraint of Uranium Swelling by Zirconium Cladding

Description: In conjunction with the fuel element development program at Hanford, it is desired to determine the effects of cladding and core temperatures, cladding thickness, and exposure upon the swelling behavior of unalloyed uranium. To obtain this information, it is proposed to irradiate several fuel rods, clad by coextrusion with Zr-2, in NeK filled stainless steel capsules. The central uranium temperatures are to be monitored by axial thermocouples. Irradiation tests in the MTR and ETR using capsules… more
Date: April 10, 1959
Creator: Weber, J. W.
Item Type: Refine your search to only Report
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Experimental Studies on Steam-Water Pressure Drops in an Annulus with Heat Transfer

Description: Pressure drops are reported for forced circulation flow of steam-water mixtures in a 23.5 foot long, 1.43 inch ID, 0.1 inch thick, horizontal annulus. The inner surface of the annulus was uniformly heated over a range from 97,000 to 233,000 Btu/hr-ft², exit pressures extended from 100 to 500 psig, and exit steam qualities varied from 0 to 60% by weight. Liquid water entered the annulus and boiling lengths up to 15 feet were investigated. Moreover, the Woods and the Martinelli and Nelson methods… more
Date: October 10, 1955
Creator: McNutt, C. R. & Carbon, M. W.
Item Type: Refine your search to only Report
open access

Failure of Stressed Cylinders

Description: The conservative design criteria applied to process tubing may seriously hinder the advancement of high temperature reactor development. Factors of safety of 3 to 4 applied to an arbitrarily defined yield strength are used to calculate allowable internal working pressures. The effect of biaxial stressing on the tubes has been shown (2) to cause yielding at a lower internal pressure. However, tests conducted on biaxially stressed short lengths of tubing indicated that the ultimate tensile streng… more
Date: March 10, 1955
Creator: Taylor, A. T. & Petersen, L. M.
Item Type: Refine your search to only Report
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Fission Product Heat Generation Tables

Description: In order to obtain the most economical utilization of underground storage facilities it is desirable to maintain a running inventory of heat generation and available self concentration in a given tank. Further, it is believed that such knowledge will be helpful in studying underground storage technology. The calculation of fission product heat generation and available self concentration factor in separations waste storage tanks is a complex process. The complexity is increased greatly when mate… more
Date: April 10, 1956
Creator: Swift, W. H. & O'Neill, G. L.
Item Type: Refine your search to only Report
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Fretting Corrosion Irradiation Tests

Description: The Zircaloy-a clad, swaged UOa, 19-rod cluster fuel element for the PRTR was designed to use Zircaloy-a wire spirally wrapped around the fuel rods as spacing members. Such use of unbonded, Zircaloy-a spacers introduced the possibility of fretting corrosion. This paper reports preliminary irradiation tests conducted to determine whether or not such corrosions occurs in this fuel element design.
Date: September 10, 1959
Creator: Millhollen, M. K.
Item Type: Refine your search to only Report
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Gas-Graphite Reactions. I. Thermal and Microwave Oxidation of Various Reactor-Grade Graphites*

Description: Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.
Date: February 10, 1960
Creator: Clark, T. J.
Item Type: Refine your search to only Report
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Graphite Diffusion Length Measurements at Hanford

Description: A series of diffusion length measurements were carried out on graphite stacks of various constructions in an attempt to resolve the discrepancies between the graphite diffusion lengths measured in the Hanford reactors and that value measured in the Hanford Standard Pile. It was found that the diffusion length of the graphite in the Hanford reactors is in good agreement with the value for the Hanford Standard Pile when corrections are made for the absorption and scattering of neutrons by the alu… more
Date: September 10, 1956
Creator: Richey, C. R. & Block, E.Z.
Item Type: Refine your search to only Report
open access

Liquid Magnesium as a Coolant for Thermal Reactors

Description: It was suggested to the writer by K.A. Eschbach that liquid magnesium might offer certain advantages as a reactor coolant. As a result of this suggestion, a preliminary investigation of the possibilities of this material was made. Definite advantages for a restricted class of applications were found, but a detailed evaluation would seem to require further basic experimental research on the heat transfer, corrosion and flux-mechanical properties of the substance.
Date: June 10, 1955
Creator: Triplett, J. R.
Item Type: Refine your search to only Report
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