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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
open access

Nuclear Merchant Ship Reactor Shield Design Summary Report

Description: Abstract: "Most of the Nuclear Merchant Ship Reactor (NMSR) shield design work performed by The Babcock & Wilcox Company (B&W) is summarized. Primary and secondary shield results are presented, consistent with contractual requirements and designated design criteria. Methods of calculation and basic parameters are shown" (p. 1).
Date: August 1, 1959
Creator: Smith, W. R. & Turner, M. A.
open access

Liquid Metal Loops Irradiated on the ORNL Graphite Reactor and the LITR

Description: From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."
Date: June 1, 1959
Creator: Parkinson, W. W. & Sisman, O.
open access

The Chattanooga Shale of Tennessee as a Source of Uranium: Final Report

Description: From major objective: The over-all aim of the study has been to obtain a thorough geologic picture of the Chattanooga shale in the area under consideration, with emphasis upon stratigraphic relationships and associated special problems from which, in turn, implications may be obtained as to the origin and age of the formation and possibly the source of the uranium. The study has not been aimed primarily at exploration for uranium and its economic aspects.
Date: July 1, 1959
Creator: Stockdale, Paris B. & Klepser, Harry J.
open access

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.
open access

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.
open access

Remote Radiological Monitoring

Description: From abstract: A gamma-radiation telemetering system was utilized by Civil Effects Test Group personnel to measure fallout levels at the Nevada Test Site from the vicinity of Ground Zero out to, and including, an area bounded by Reno, Nevada; Salt Lake City, Utah; Kingman, Arizona; and Barstow, California.
Date: May 1, 1959
Creator: Sigoloff, Sanford C. & Borella, H. M.
open access

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.
open access

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.
open access

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.
open access

Strontium Program: Quarterly Summary Report, October 1, 1959

Description: From Introduction: "Quarterly summary reports are prepared by the Health and Safety Laboratory (HASL) with the objective of presenting a current picture of the Strontium Program. This report, which up-dates HASL-65, presents data routinely reported by the Analytical Division of the Health and Safety Laboratory and its contractor laboratories - Nuclear Science and Engineering Corporation, Isotopes, Incorporated, Radiochemistry, Incorporated, and Tracelab, Incorporated. In addition, this issue in… more
Date: October 1, 1959
Creator: Hardy, Edward P., Jr. & Klein, Stanley
open access

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.
open access

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.
open access

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.
open access

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.
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