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Design-Development and Operation of the Experimental Boiling-Water Reactor (EBWR) Facility, 1955--1967

Description: The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(… more
Date: November 1990
Creator: Boing, L. E.; Wimunc, E. A. & Whittington, G. A.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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 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
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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Temperature distribution in the concrete shield

Description: Report describing the temperature in the Brookhaven concrete shield proposed for the X reactor. The report details the methods and equations used to find the values that determined that the effect of the gun barrel assembly in cooling the concrete is negligible.
Date: April 28, 1952
Creator: Triplett, John R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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AEC Hot Cells and Related Facilities

Description: Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Date: May 1958
Creator: Fosdick, Ellery R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operational Health Physics Training

Description: This revised publication updates a previous report (ANL-7291) initially published in 1965, entitled Radiation Safety Technician Training Course which was intended to complement on-the-job monitoring training for Health Physics Technicians. Sections include basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of alpha, beta, gamma, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units).
Date: June 1992
Creator: Moe, H. J. & Vallario, Edward J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PM-3A Nuclear Power Plant Secondary Shield Design

Description: "The design, analysis, and selection of system components for functions related to secondary shielding and associated auxiliary systems for the Antarctic PM-3A Nuclear Power Plant are described. Backfill material characteristics, shielding and activation analyses, heat transfer analysis, backfill cooling system, water exclusion and removal system, and instrumentation and control are discussed."
Date: September 1961
Creator: Siler, W C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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
Item Type: Refine your search to only Book
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Shielding of Mobile Reactors - [Part] 2

Description: From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, ar… more
Date: June 30, 1952
Creator: Blizard, E. P. & Welton, T. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation Of Windows And Shields For Neutron Point Sources

Description: An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date: May 20, 1959
Creator: Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

General Reactor-Engineering Research Quarterly Progress Report [for] Period Ending August 31, 1950

Description: Technical report describing results on work which cannot be ascribed to one reactor program. Outlines the results of miscellaneous corrosion testing, the development of new shielding materials, the testing of irradiated plastics, and general heat transfer investigation. [From Preface]
Date: November 13, 1950
Creator: Lyon, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of the Argonne Low Power Reactor (ALPR)

Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly… more
Date: May 1961
Creator: Hamer, Eberhard E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-Density Concrete for Gamma and Neutron Attenuation

Description: Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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