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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.
Partner: UNT Libraries Government Documents Department
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Polarographic Determination of Hexone

Description: The following report describes polarographic methods that determine saturated aliphatic carbonyl compounds.
Date: November 10, 1949
Creator: Alkire, George J.
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.
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.
Partner: UNT Libraries Government Documents Department
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Production of UO₃ by Calcination of Uranyl Peroxide

Description: This report discusses the calcination or heating of UO₃. When UO₃ is heated, it loses ionic impurities and can produce uranyl peroxide.
Date: December 10, 1952
Creator: Moore, R. L. & Watts, R. A., Jr.
Partner: UNT Libraries Government Documents Department
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Production Test 235-5 Plant Process Evaluation Reduction of Plutonium Tetrafluoride With Calcium and Sulfur

Description: This report discusses the production of plutonium metal through the reduction of plutonium tetra fluoride with calcium metal and sulfur. It elaborates that iodine, which was originally used instead of calcium metal, presented several practical problems, but reductions completed with calcium were unsatisfactory.
Date: February 10, 1953
Creator: Kerr, W. B.
Partner: UNT Libraries Government Documents Department
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Liquid-Liquid Dispersions and the Significance of the Disengaging Test

Description: From introduction: "The purpose of this report is to summarize some of the observations on the dispersion and rate of disengaging of liquid-liquid systems and suggest some possible lines of future work."
Date: July 10, 1952
Creator: Burger, L. L.; Dillon, R. L. & Johnson, W. F.
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.
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.
Partner: UNT Libraries Government Documents Department
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Weighting Factors for Radically Flattened Piles

Description: The following report calculates pile reactivity changes that result from different pile loadings where it is desirable to have available values of (flux)2 d(volume) for various flat zone radii. This information was found for a cylindrical pile having circular flat zones and an effective radius of 598 cm., by integrating over a cross sectional volume of one cm. thickness.
Date: January 10, 1952
Creator: Woodruff, R. W.
Partner: UNT Libraries Government Documents Department
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Chloride Removal from Metal Waste Solutions

Description: Objective: The objective of this study is to develop a simple method of either removing the C1- ion from the RAW or converting the ion into a less corrosive valence state.
Date: October 10, 1950
Creator: Clark, L. H.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Ultrasonically Bond Testing Hanford Fuel Elements

Description: Ultrasonic equipment has been developed for nondestructive testing of Hanford fuel elements. The ultrasonic method has replaced the Frost Test for bonding layer inspection in the Hanford canning line, and provides more accurate and reliable results at lower cost. The method has also been adopted to the testing of new fuel elements for which no other method is available.
Date: May 10, 1956
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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The Recovery of Fission Product Rare Earth Sulfates from Purex LWW

Description: A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
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.
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.
Partner: UNT Libraries Government Documents Department
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Mechanical and Physical Properties of Uranium: Chapter 8 of Nuclear Metallurgy Lectures

Description: A knowledge of the mechanical and physical properties of uranium is important in understanding and explaining its pile behavior. The effects of irradiation on the properties of uranium will be dealt with in another chapter. However, it is important to know and understand the pre-irradiation properties of uranium prior to investigating the effects of irradiation.
Date: May 10, 1955
Creator: Rueschen, R. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report- January, February, March 1959 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: Four capsules containing Al-1.65 w/o Pu and Al-12 w/o Si-1.65 w/o Pu were charged into the MTR. These capsules will be irradiated to a burnup of 80-100% of the plutonium atoms to determine the stability of the material at high exposures. An additional sixteen capsules containing 5 to 20 w/o Pu in Al and Al-Si have been prepared. Eight are awaiting reactor space and should be charged soon. The remaining eight are being recanned to increase the end gap between the core and the can. Also four caps… more
Date: May 10, 1960
Creator: Wick, O. J.; Thomas, I. D.; Stewart, R. W.; Stewart, R. W. & Nelson, T. C.
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.
Partner: UNT Libraries Government Documents Department
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Quality Standards and Tests for Swaged Fuel Cladding

Description: The basic process for fabricating a swaged fuel rod is simple, easy to control and inexpensive. A zircaloy tube is filled with uranium dioxide powder, the ends temporarily plugged and the loaded tube is swaged to compact the UO2 powder to the required density. The swaged rod is then cut to length and counterbored and then end cape are welded into each end. After several tests and inspections, nineteen rods which meet the quality standards are assembled into a single fuel element ready for irra… more
Date: September 10, 1959
Creator: Olson, R. E.
Partner: UNT Libraries Government Documents Department
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Thermal Spikes and Uranium Instability

Description: Thermal spikes occurring during the life of a slug in a pile cause a momentary destruction of the original configuration of atoms in the metal. This process occurs at such a rate that in a thermal neutron flux of 10(13) neutrons per square centimeter per second each atom in the metal will be subject to temperatures above the melting point of uranium every 40 minutes.
Date: December 10, 1952
Creator: Last, G. A. & McLachlan, D., Jr.
Partner: UNT Libraries Government Documents Department
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A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media

Description: Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date: August 10, 1953
Creator: Adley, F. E.; Scott, R. H. & Gill, W. E.
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.
Partner: UNT Libraries Government Documents Department
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