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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Decontamination Studies for HAPO High Temperature Reactor Recirculation Systems Process Report June 1958-June 1959

Description: A means for decontaminating the primary system of recirculating type reactor is necessary to insure operation and maintenance. This recirculation system can be contaminated by fuel element rupture products and induced corrosion product activities.
Date: June 10, 1959
Creator: Perrigo, Lyle D., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Fast Neutron Sensitivity of the CP Meter

Description: Abstract: "The sensitivity to fast neutrons of a CP Meter ionization chamber of the type used for health physics beta and gamma survey measurements has been investigated."
Date: June 10, 1949
Creator: Baker, E. E.; Gydesen, F. R. & Whipple, G. H., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Graphite Sample Boring from Process Channels : Final Report, Production Test 105-389-P

Description: The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.
Date: July 10, 1951
Creator: Cole, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Graphite surface studies

Description: This report discusses the the surface characteristics of virgin and irradiated artificial graphites and the changes which occur upon irradiation.
Date: October 10, 1952
Creator: Spalaris, C. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutralization of HNO₃ in Redox ICU an IAW Streams

Description: The following memorandum outlines the procedures used on the neutralization of HNO3 in redox ICU and IAW streams, and the factors influencing their choice. The procedures involve a) hexone removal by evaporation in the presence of a retardant, b) destruction of the retardant, c) nitric acid elimination by boiling with aluminum and d) concentration of the remaining solution by evaporation.
Date: December 10, 1948
Creator: Curtis, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutron Age Calculations. (Homogeneous Systems)

Description: In an earlier study on criticality conditions for homogenous mixtures, 2/cm^2 was used as the neutron age for all mixtures of water and uranium. At the higher H/U ratios (low uranium concentration), the calculated critical parameters were in good agreement were in good agreement with experimental data. At the low H/U ratios (high uranium concentrations) the calculated critical parameters were smaller than the experimental ones (more conservative from a nuclear safety point view). These results … more
Date: July 10, 1959
Creator: Ketzlach, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Operation and Maintenance of an Alpha Energy Analyzing System

Description: The measurement of a alpha-particle energy has been used by many radiochemical laboratories for the identification and analysis of alpha-active radio nuclides. The use of the total-ionization method for alpha-active radio-nuclides. The use of the total-ionization method for alpha energy in ionization chamber in which the alpha particle loses all its energy in ionization of the chamber gas. Collection of the electrons thus formed generates a voltage pulse across the chamber capacity which is pro… more
Date: July 10, 1959
Creator: Brauer, F. P. & Connally, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Preliminary Comparison of the Nannoplankton and Net Plankton of the Columbia River

Description: Plankton collected from the Columbia River by the net method and by the centrifuge method were compared. The centrifuged plankton (nannoplankton) exceeded the net plankton in weight, in abundance of organisms and in radioactivity. Similar seasonal trends were present in both types of plankton.
Date: September 10, 1953
Creator: Coopey, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Investigation of Alkaline Permanganate - Sodium Acid Sulfate for Decontamination of High Temperature Recirculating Systems.

Description: Decontamination of stainless steel and carbon steel used in high temperature recirculation systems is currently being studied to obtain an effective and economical decontamination process for use in these systems. This report presents the preliminary investigation process which has demonstrated very effective decontamination and is low in cost.
Date: June 10, 1959
Creator: Oldham, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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