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Accuracy of Relaxation Length Measurements

Description: We consider here the accuracy of relaxation lengths measured during the water-uranium lattice experiments. Since such an analysis for all measurements would take a great deal of time, we have applied it to just one lattice. This one (2:1 water-to-metal ratio) was chosen completely at random.
Date: April 28, 1953
Creator: Kouts, H.
open access

Aerosol Collection by Wetted Fiberglass Media

Description: A wet collection system for aerosols has been developed using fibrous media. Tests show the performance to be in accord with recently developed theory of collection by fibrous media. The effects of varying aerosol particle size, particle density, and gas velocity have indicated that inertial impaction is the primary collection mechanism. Three-year operating experience on several full scale plant installations shows reliable performance.
Date: April 28, 1954
Creator: Leary, Joseph A.; Clark, Robert A.; Hammond, R. Philip & Leopold, Charles S.
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report For Period Ending June 10, 1955

Description: The development of the reactor layout is continuing. New features that have been incorporated because of stress, fluid flow, or fabricability considerations include an elliptical fuel expansion tank, a rounded dome to enclose the top of the reactor, a newly designed sodium pump impeller, and other related items. Recently completed heat exchanger tests yielded consistent data from which a series of heat exchangers is being designed. The most promising of these will be chosen for the ART.
Date: July 28, 1955
Creator: Jordan, W. H.; Cromer, S. J.; Strough, R. I.; Miller, A. J. & Savolainen, A. W.
open access

Centrifugal Casting for Plutonium and Plutonium-Uranium Plates

Description: The objective of this investigation was to determine the feasibility of centrifugal casting to produce fuel element plates suitable for use in a power reactor. Preliminary investigations involving the centrifugal casting of metal plates suitable for use in a power reactor proved to be successful. Lead plates cast at medium speeds contained very few voids and exhibited a surface which conformed very closely to that of the mold.
Date: November 28, 1956
Creator: Quinlan, F. B. & Tverberg, J. C.
open access

Compilation of Various Undocumented Classified Memoranda on Sherwood Program

Description: This compilation includes the following subjects: (1) Spectroscopic studies, (2) Neutral carbon in the vacuum carbon arc, (3) Anode effects, doppler blast effects, and stark broadening, (4) Neutrals in the high-current carbon arc; (5) Photon breakup of N2 in the high-current carbon arc, (6) Ion density in the high current carbon arc, and (7) Recombination cross-section for fast hydrogen ions and slow electrons. Minor revisions have been made in the subject memoranda in incorporating them in the… more
Date: June 28, 1957
Creator: McNally, J. Rand (James Rand), 1917-
open access

Continuous Electrochemical Determination of Oxygen in Gases

Description: To forestall the oxidation of graphite in HAPO reactors, a process specification provides that the oxygen concentration in pile gas should be kept to a minimum. Close control in maintaining this limit is difficult when only periodic samples are taken because laboratory results are always obtained long after any required corrections should have been made. A continuous-type analyzer that provides immediate knowledge of the oxygen concentration eliminates these time delays.
Date: March 28, 1956
Creator: Koyama, K.
open access

Creep Strength of Uranium Alloys at 1500 and 1800 F

Description: Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates… more
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
open access

Critical Ionization of Potentials of Uranium Hexafluoride

Description: Introduction: "The extensive use of uranium hexafluoride in the Nier-type mass spectrometers, where the ionization is produced by slow electrons, made a knowledge of the ionization potentials of the various ions desirable. This information was not available and work was accordingly begun to secure such data. The first measurement was made with a VGIA ion gauge and has been described in TEO report CD-310. With this apparatus it was not possible to identify the ionization products and it was pres… more
Date: November 28, 1955
Creator: Cameron, Angus Ewan, 1906- & White, J. R.
open access

Cyclotron Resonance Heating of a Deuterium Plasma

Description: Abstract: "The energy gained by a deuterium plasma, from a three megacycle per second radiofrequency field, was studied experimentally. A static magnetic field, in the form of a "mirror", was used. The coil of an rf resonant circuit, placed at the center of the machine produced a time-varying magnetic field parallel to the static field. This, in turn, induced an electrical field, in an azmuthal direction, which acted on the ions. When this was in synchronism with the cyclotron frequency, the io… more
Date: October 28, 1957
Creator: Chambers, Edmund S.; Lamb, William A. S. & Kippenhan, Dean O.
open access

The Decontamination of Reactor Cooling Water with Aluminum

Description: The discharge of cooling water from the Hanford reactors introduce radioactive contaminants to the Columbia River. These materials may subsequently bring about exposure to human populations either through the direct use of the water for sanitary purposes or transfers of the radioisotopes into the food chains. It is therefore desirable to keep to a minimum the amounts of radioisotopes released to the river.
Date: January 28, 1959
Creator: Silker, W. B.
open access

Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures

Description: Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mis… more
Date: June 28, 1956
Creator: Ewing, Robert A. & Bearse, Arthur E.
open access

Digestion and Filtration of Leached Zone in Pilot Plant

Description: Introduction: The present report summarizes pilot plant operations on the sulfuric acid digestion of -200 mesh leached zone and filtration of the digested slurry for the period May 5, 1952 through August 7, 1953.
Date: February 28, 1955
Creator: Dugger, Gordon L.; Adams, J. B. & Bart, Roger
open access

The Entropy and Low Temperature Heat Capacity of Neptunium Dioxide

Description: The following report is focused on finding the measurements of low temperature heat capacities of neptunium dioxide. The entropy and the interpretation of the anomaly in the heat capacity curve will be dicussed."
Date: July 28, 1950
Creator: Westrum, Edgar F., Jr.; Hatcher, J. B. & Osborne, Darrell W.
open access

Examination of Masonite in Biological Shield : Interim Report

Description: Introduction: "Evidence of masonite deterioration in test hole plugs was interpreted to mean that a previous estimate of the minimum lifetime of the masonite in a Hanford biological shield might be somewhat optimistic. The importance of understanding the effects of radiations on masonite for both present and future pile shields dictated that masonite be sampled from an operating pile shield and studied. The results and techniques are discussed in the following sections of this report."
Date: June 28, 1950
Creator: Dickeman, R. L.
open access

Field Corrosion Tests in Redox and Purex Underground Waste Storage Tanks

Description: A corrosion testing program has been initiated in Purex and Redox storage tanks to obtain corrosion data on SAE 1020 carbon steel, two alloy-high strength steels, and an alloy steel in neutralized process wastes.
Date: June 28, 1955
Creator: Groves, N. D.; Fraser, M. C. & Walker, W. L.
open access

Fission Product Activities in Irradiated Natural Uranium, Enriched Uranium, and Thorium

Description: Calculated data and graphs describing the effects of batch thermal-neutron irradiations on the buildup of fission products in natural uranium, enriched uranium, and thorium are presented together with empirical equations and plots correlating total fission product activities and/or decontamination factors. Fluxes of 1012-1015 are considered.
Date: March 28, 1956
Creator: Arnold, E. D.
open access

Freezing Point Diagram and Liquid-Liquid Solubilities of the System Uranium Hexafluoride-Hydrogen Fluoride

Description: Abstract: "The complete freezing point diagram for the system uranium hexafluoride-hydrogen fluoride has been determined. In addition, liquid-liquid solubilities of these compounds have been measured up to the consolute temperature of 101 C. A miscibility gap starts at 61.2 C. over the compositions range 10 to 80 mole per cent uranium hexafluoride. The lowest melting point of this binary system under its own pressure, i.e. the eutectic, is -85 C."
Date: December 28, 1952
Creator: Rutledge, Gene P.; Jarry, Roger L. & Davis, W., Jr.
open access

Gaseous Detonation : Bibliography

Description: This report is a bibliography divided into two sections: one that documents books and journal articles, the other containing classified and unclassified documents, that are based around gaseous detonation. These sources cover the period between 1941 to October of 1957.
Date: October 28, 1957
Creator: Maynard, G. R. & Frost, Fred
open access

High Pressure Low Resistance Joint

Description: The following report describes the usage of tin-foil to obtain a mechanical joint of low electrical resistance while providing a seal to hold water at a pressure of 300 psi.
Date: March 28, 1955
Creator: Peters, Ralph
open access

IBM Multigroup Numerical Procedures

Description: Introduction: "This paper presents in formula form IBM computational procedure for averaging cross-section data and for calculating reflected spherical reactors by the linear by the linear multigroup numerical method developed by the Physics Section of the ANP Central Design Group. The adjoint reactor numerical procedural is included."
Date: November 28, 1950
Creator: Holmes, David K. & Schulze, O. A.
open access

Interim Report: Investigation of Ultrasonic Decontamination

Description: The purpose of this investigation is to make a preliminary study and evaluation of the application of ultrasonic equipment and associated handling equipment to the problem of decontaminating reactor tube dummy pieces. Reactor Section is currently planning the construction of batch process nitric acid facilities for dummy decontamination. It was felt that use of ultrasonics together with a solution less corrosive than nitric acid might provide adequate decontamination at lower project cost than … more
Date: January 28, 1955
Creator: Reed, E. L.
open access

Investigation of Solvent Degradation Products in Recycled Uranium Recovery Plant Solvent

Description: As part of an investigation of solvent stability, a direct analysis of recycled Uranium Recovery Plant solvent* has been made to determine the type, source, and properties of the impurities which have been generated in the solvent and are present in the solvent after it has been in use for some time. This work has been directed towards the separation and identification of the impurities by compound class, and the conclusions are set forth in this report. Another purpose of this report is to pre… more
Date: April 28, 1955
Creator: Moore, R. H.
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