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Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
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Polyethylene as a Radiation Shielding Standard in Simulated Cosmic-Ray Environments

Description: Radiation risk management for human space missions dependson accurate modeling of high-energy heavy ion transport in matter. Theprocess of nuclear fragmentation can play a key role in reducing both thephysical dose and the biological effectiveness of the radiationencountered in deep space. Hydrogenous materials and light elements areexpected to be more effective shields against the deleterious effects ofGalactic Cosmic Rays (GCR) than aluminum, which is used in currentspacecraft hulls. NASA has chosen polyethylene, CH2, as the referencematerial for accelerator-based radiation testing of multi-functioncomposites that are currently being developed. A detailed discussion ofthe shielding properties of polyethylene under a variety of relevantexperimental conditions is presented, along with Monte Carlo simulationsof the experiments and other Monte Carlo calculations in which the entireGCR flux is simulated. The Monte Carlo results are compared to theaccelerator data and we assess the usefulness of 1 GeV/amu 56Fe as aproxy for GCR heavy ions. We conclude that additional accelerator-basedmeasurements with higher beam energies would be useful.
Date: August 19, 2006
Creator: Guetersloh, Stephen B.; Zeitlin, Cary; Heilbronn, Lawrence H.; Miller, Jack; Komiyama, Tatsudo; Fukumura, A. et al.
Partner: UNT Libraries Government Documents Department
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Reactor Shielding Design Manual

Description: The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date: March 1956
Creator: Rockwell, Theodore, III
Partner: UNT Libraries Government Documents Department
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Calculation of Shielding for Mark II Accelerator

Description: The proper roof thickness to correspond with a given side wall thickness has been estimated fro experience with the 184 feet cyclotron, which has indicated that a roof of about 1 1/2 feet should accompany a wall of 5 feet, and a roof of 4 feet should accompany a wall of 15 feet. For the roof area involved, this should bring about the condition that down-scattered neutrons in the working areas are but a small fraction of the neutrons coming through the side walls.
Date: June 30, 1951
Creator: Moyer, B. J.
Partner: UNT Libraries Government Documents Department
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Field Handling Study of Heavy Aggregate Concrete

Description: Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""
Date: December 7, 1951
Creator: Emmons, C. D.
Partner: UNT Libraries Government Documents Department
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Military Field Expedient Shielding Experiment

Description: Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.
Date: October 18, 1960
Creator: Wheeler, D. M. & Bostick, L. H.
Partner: UNT Libraries Government Documents Department
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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 exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Partner: UNT Libraries Government Documents Department
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Radiation Shielding for Test Cell "C"

Description: "This report contains information on the following topics related to the radiation shielding at test cell "C". (1) Calculation of wall and roof thicknesses. (2) Calculation of radiation heating of front wall by gamma and neutron absorption. (3) Calculation of neutron activation in front face of test cell. (4) Calculation of γ-dose rates both direct and behind shadow shields at various distances. (5) Dose produced by a reactor catastrophe."
Date: June 1959
Creator: Fenstermacher, Charles Alvin & Henshall, James
Partner: UNT Libraries Government Documents Department
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High-Boron Steels for Reactor Shielding

Description: This report follows work performed to determine the effects of large boron additions on the fabricability and room-temperature tensile properties of various steels for reactor shielding.
Date: September 27, 1955
Creator: Saller, Henry A.; Stacy, John T. & Klebanow, Herbert L.
Partner: UNT Libraries Government Documents Department
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Magnesium Oxychloride Cements and Concretes for Pile Shielding

Description: From introduction: "The present report covers the results of an extended investigation of magnesium oxychloride cements and concretes. In this study the effects of the composition of the cement or concrete on its physical and mechanical properties were determined. In addition, the stability of the mixes was observed."
Date: August 1949
Creator: Snyder, M. J. & Pavlish, A. E.
Partner: UNT Libraries Government Documents Department
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Boral : A New Thermal Neutron Shield, Supplement I

Description: The following report provides information on the making of large sheets of boral, an engineering material for the absorption of thermal neutrons, as well as physical properties and recommendations on casting and rolling ingots into sheets.
Date: 1952
Creator: Kitzes, A. S. & Hullings, W. Q.
Partner: UNT Libraries Government Documents Department
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Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department
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The Nuclear Test Gauge

Description: From abstract: "The 'Nuclear Test Gauge', a slightly subcritical assembly for quality control of reactor components, was designed, constructed, and placed in operation. calibration experiments demonstrated that the sensitivity of the unit is adequate, and that the speed of testing is increased y a factor of ten over that of a critical test pile."
Date: June 1956
Creator: Parkinson, Thomas F.; Goosey, Malcolm H.; Heston, William M. & Hollberg, Herbert J.
Partner: UNT Libraries Government Documents Department
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Measurements of an Iron and Borated Water Shield in the Lid Tank : Experiment 10

Description: The following report measures a shield mockup in three regions: the first made almost entire of iron; the second, transition, region is made of various thicknesses of B4C; and the third region was borated water. The iron samples used in the experiments were made in the form of rectangular plates and place in the lid tank; however, the plates were not completely flat and created a water gap that was measured in this report.
Date: December 14, 1950
Creator: Blizard, E. P. & Clifford, C. E.
Partner: UNT Libraries Government Documents Department
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Engineering Properties of High-Density Concretes

Description: From summary: "Methods were developed for measuring various engineering properties of high-density concretes. Data are presented on selected thermal properties of a limonite-iron concrete and the mechanical properties of the limonite-iron concrete, a magnesium oxychloride concrete, and a Portland cement concrete containing steel punchings and shot (no limonite)."
Date: May 1951
Creator: Snyder, M. Jack; Burkart, C. A. & Clegg, John W.
Partner: UNT Libraries Government Documents Department
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Energy Per Fission and Power of the Bulk Shielding Reactor

Description: Due to some lack of knowledge of the energy per fission, there has been some uncertainty over the absolute power of the Bulk Shielding Reactor. This report analyzes measurements to state the absolute power of the BSR within a few percent.
Date: May 12, 1953
Creator: Meen, J. L.; Johnson, E. B. & Hungerford, H. E.
Partner: UNT Libraries Government Documents Department
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Shielding Requirements for the Army Package Power Reactor

Description: Abstract. The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of iron and water. this shield has been adopted to permit fast erection and to provide low transported weight. economically, including transportation cost, the iron water shield is better than a lead water shield and is competitive with a concrete shield for a remote site. Because of the location at Fort Belvoir,Va., the shielding requirements for the APR-1 are considerably more stringent than those for a reactor at a remote base. Since the secondary shielding which surrounds the entire primary system must provide protection for personnel at any location outside the vapor container, concrete is provided for this need.
Date: May 1, 1956
Creator: Meem, J. L. (James Lawrence). & Fairbanks, F. B.
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Design of the MMSR Primary Shield

Description: The purpose of this report is to describe the shielding calculations and techniques used in sizing the MMSR primary shield, the results obtained, and the resulting shield thicknesses. The present report covers many of the items scheduled for presentation in the final MMSR shield design report to be issued in November of 1958. The primary shield in the MMSR consists of the reflector, thermal shields, pressure vessel wall, a 33" water annulus and a layer of lead shielding at the exterior of the primary shield tank vary from 3" to 1" in thickness.
Date: April 1958
Creator: Smith, W. R. & Turner, M. A.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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