UNT Libraries Government Documents Department - 26 Matching Results

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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exp… more
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Item Type: Refine your search to only Report
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Coupled Transmission Lines

Description: In a discussion about design of cyclotron resonators, the suggestion has been made that a wide range variable-frequency system might be constructed with two coupled resonant circuits. It also would present the possibility of tuning without the switching of high-current contacts, a troublesome item now commonly used for cyclotrons. One of the circuits would be the dee and its stem which might, or might not, be tuned. The second circuit could be located out of the magnet gap in a region where mo… more
Date: June 1, 1959
Creator: Worsham, R. E. & Mosko, S. W.
Item Type: Refine your search to only Report
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Effects of Reactor Environment on Candidate PRTR Gas Loop Materials.

Description: The purpose of this program is to determine the effects of neutron radiation and reactor gaseous atmospheres on the structural integrity of candidate materials for the PRTR gas-cooled loop. An exploratory investigation is being conducted to select a high temperature resistant alloy for the fabrication of tubes and supporting appliances for the PRTR gas-cooled loop. In addition to a low neutron cross section, the material must be able to withstand the operating conditions outlined in Table 1.
Date: September 1, 1959
Creator: Bement, A. L.; Wheeler, K. R. & Pessl, M. J.
Item Type: Refine your search to only Report
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Experimental Program for the PRTR Gas Loop

Description: Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical inter… more
Date: September 1, 1959
Creator: Baker, D. E.
Item Type: Refine your search to only Report
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Report on HAPO Unitized Microfilm Drawing System

Description: This report is being submitted to provide information and data on the planning and installation of a new mechanized drawing system which utilizes a new drawing index system and a 35mm microfilm image in a standard IBM card. The communication of engineering information to date has been primarily the full size contact print produced by exposing and developing light sensitive material. This method produces legible copies; but, it has the following disadvantages : (a) the original drawings are frag… more
Date: October 1, 1959
Creator: Durbin, J.
Item Type: Refine your search to only Report
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Survey of Air and Gas Cleaning Operations

Description: The attached survey information comprises a cross section of Air and Gas Cleaning Operations as used in the Chemical Processing Department at the Hanford Atomic Products Operation, Richland, Washington. Most of the information as requested by J. T. Fitsgerald, Harvard University, is included in these surveys, certain cost information was difficult to isolate in the manner requested and may, therefore, be only roughly approximate. The numerical significance of the data will indicate this in most… more
Date: September 1, 1959
Creator: Morgenthaler, A. C.
Item Type: Refine your search to only Report
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Measurement Of Average Neutron Energies For (o, n) Neutron Sources

Description: A method is presented for measuring the average energy of the neutrons from a source. The attenuation of the neutrons by polyethylene is measured by the use of a long counter in good geometry. The attenuation length is a sensitive function of the neutron energy. The average neutron energies from several (o, n) sources have been measured and agree well with values obtained by other techniques.
Date: April 1, 1959
Creator: Hess, Wilmot N. & Smith, Alan R.
Item Type: Refine your search to only Report
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Nitrous Acid Behavior in Purex Systems

Description: In HAPO solvent extraction processes there are two independent aspects of nitrous acid chemistry. One concern the decomposition of the solvent through nitration reactions and the attendant problems. These reactions are autocatalytic in the presence of nitric acid and have threshold values for both temperature and nitric acid concentration for a given solvent below which nitrous acid disappears and above which it is generated with continuous destruction of the solvent. These reactions are ident… more
Date: May 1, 1959
Creator: Burger, L. L. & Money, M. D.
Item Type: Refine your search to only Report
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Sequential Separation of Some Actinide Elements By Anion Exchange

Description: The methods for the separation of the elements from thorium to americium having wide use are those employing solvent extraction techniques (1) (2). During recent years the behavior of these elements on anion exchangers has been studied, resulting in the wide application of these resins to the separation of the actinides (3) (4) (5) (6) (7).
Date: June 1, 1959
Creator: Roberts, F. P.
Item Type: Refine your search to only Report
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Reactor Heat Transfer by Boiling Mercury- 204

Description: In HW-56161(1), the preliminary background, bases, and advantages which could be visualized in the study and establishment of reactor concepts utilizing boiling mercury- 204 were presented. The attractive chemical and metallurgical properties of mercury which make it particularly suitable for use in special non-rigid fuel systems as well as its potential for heat transfer applications were considered to be of significant interest to the Plutonium Recycle Program also, since the issuance of the … more
Date: June 1, 1959
Creator: Rohrmann, C. A.
Item Type: Refine your search to only Report
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Heat Transfer in Radiant- Heat Spray Calcination

Description: The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford … more
Date: February 1, 1959
Creator: Johnson, B.M., Jr.
Item Type: Refine your search to only Report
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The Use of Tetravalent Uranium and Hydrazine as Partitioning Agents in Solvent Extraction Process for Plutonium and Uranium

Description: In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slugs" from the reactor containing uranium, plutonium, and fission products are dissolved in nitric acid, adjusted to the required feed composition, and pumped to the solvent extraction columns. Figure 1 in a schematic diagram of such a solvent extraction process. In the A column, the uranium and the plutonium are extracted into an organic phase while the bulk of the fission products remain in the aq… more
Date: February 1, 1959
Creator: Buckingham, J.S.; Colvin, C.A. & Goodall, C.A.
Item Type: Refine your search to only Report
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Computational Aids for Estimating Performance of Liquid to Boiling Water Heat Exchangers

Description: The computation of liquid-boiling heat exchanger performance under a wide variety of operating conditions is a cumbersome, time-consuming procedure. Rapid evaluation of a design requires the use of some form of computational aid. Exchanger equations covering the case of liquid-boiling heat transfer have been derived and evaluated for a specific correlation of local boiling condition. Examination of various data as presented by Bonilla and McAdams indicates that the boiling coefficients are not … more
Date: September 1, 1959
Creator: Love, W. J.
Item Type: Refine your search to only Report
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Hanford Neptunium Oxalate-Oxide Process Experience

Description: In recent months, relatively large quantities of neptunium-237 have been recovered from Hanford irradiated uranium. The over-all recovery process consisted of 1) isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with uranium, plutonium, and fission products (2) purification by anion exchange 3) precipitation of neptunium (IV) oxalate; and 4) calcination of the oxalate to yield neptunium (IV) oxide, NpO2. This paper… more
Date: July 1, 1959
Creator: Pollock, C. W. & Schneider, R. A.
Item Type: Refine your search to only Report
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Subsurface Geology of the Hanford Separation Areas

Description: The region in which Hanford's chemical processing plant areas (separation areas) are located in the central portion of the Hanford Works area on a plateau, shaped like a giant bar, of glaciofluviatile materials. The general locations of these areas is shown in Figure 1. The region studied rises from 200 to 300 feet above the surrounding area and encompasses approximately 40 square miles or somewhat less than 8% of the Hanford reservation (Figure 2). Within the region are located the chemical se… more
Date: October 1, 1959
Creator: Brown, D. J.
Item Type: Refine your search to only Report
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
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Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
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Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93)

Description: To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system… more
Date: May 1, 1959
Creator: Shank, E. M.
Item Type: Refine your search to only Report
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Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0)

Description: In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Item Type: Refine your search to only Report
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Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0)

Description: In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
Item Type: Refine your search to only Report
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Finite Amplitude Stress Waves in Rocks

Description: Production of new surface area by fracturing of rock behind an explosive-initiated high amplitude wave is probably an important mechanism for energy absorption in the region near n explosion in rock. Explosive-initiated high amplitude pulses in cylinders of three different rocks and two concretes were studied to determine the pulse amplitude need to damage the cylinders. An average high amplitude wave velocity of half the elastic wave velocity was observed in a porous limestone. Elastic theory … more
Date: October 1, 1959
Creator: Grine, Donald Reaville
Item Type: Refine your search to only Report
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Progress Report No. 54 for the Period through April 30, 1959

Description: This is the fifty-fourth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress reported covers the period for Physics and Chemistry through April 30,1959. Progress is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) High energy accelerator physics group, (6) Bubble chamber group, (7) Liner acceleratory group, (8) Rockefeller ge… more
Date: May 1, 1959
Item Type: Refine your search to only Report
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