Serial/Series Title

Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead (open access)

Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead

Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.
Date: June 11, 1965
Creator: Franklin, John C. & Griffin, E. B.
System: The UNT Digital Library
In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans (open access)

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.
Date: June 23, 1959
Creator: Cofield, Rogers E.
System: The UNT Digital Library
Shipboard Cobalt-60 Radiopasteurizer for Marine Products (open access)

Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
System: The UNT Digital Library
Radiation Safety and Control Training Manual (open access)

Radiation Safety and Control Training Manual

Introduction: The Laboratory follows the recommendations of the National Committee on Radiation Protection concerning permissible exposure limits for those working with radiation. A system of controls and regulations has been established which should ensure that no person at the Laboratory will receive more than the permissible exposure. This manual is intended to provide the minimum background necessary for intelligent cooperation with the regulations.
Date: June 1, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.
Date: June 30, 1961
Creator: Chittenden, W. A. & Hoveke, G. F.
System: The UNT Digital Library
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants (open access)

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.
Date: June 30, 1962
Creator: Chittenden, W. A. & Hoveke, G. F.
System: The UNT Digital Library
Evaluation and Design Heavy Water Moderated Power Reactor Plants (open access)

Evaluation and Design Heavy Water Moderated Power Reactor Plants

From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.
Date: June 30, 1960
Creator: unknown
System: The UNT Digital Library
Rotating Machinery for Gas-Cooled Reactor Application (open access)

Rotating Machinery for Gas-Cooled Reactor Application

From foreword: Representatives from various organizations met to discuss progress in the development of rotating machinery for gas-cooled reactors. The equipment covered included main blowers, shaft seals, gas turbines, gas bearing compressors, and other types of special compressors for reactor or experimental applications.
Date: June 1962
Creator: unknown
System: The UNT Digital Library
Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959 (open access)

Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959

From abstract: This paper discusses the use of high flux reactors to remove a number of deficiencies in the knowledge of the interaction of neutrons with matter.
Date: June 1960
Creator: unknown
System: The UNT Digital Library
Analytical Chemistry in Nuclear Reactor Technology: 1961 (open access)

Analytical Chemistry in Nuclear Reactor Technology: 1961

"An Automated Spectrograph has been developed for the analyses of beryllium contained on filter paper discs. With this instrument, unattended analyses can be carried out on a number of samples following simple sample preparation. Filter paper discs representing beryllium in the atmosphere as well as those used for evaluating surface contamination are accommodated. Included in the uniting are an automatic electrode changer, analytical gap servo control, spectrograph, signal detector, and computer and readout system. The performance of the instrument in the range of 0.5 to 40 mg of beryllium is discussed."
Date: June 1962
Creator: Susano, C. D.
System: The UNT Digital Library
OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations (open access)

OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations

This report describes a computer program--Oak Ridge Thermal Ellipsoid Plot program (OR TEP)--for drawing crystal structure illustrations with a mechanical plotter.
Date: June 1965
Creator: Johnson, Carroll K.
System: The UNT Digital Library
Lawrence Radiation Laboratory Chemistry Division Quarterly Report: March - May 1953 (open access)

Lawrence Radiation Laboratory Chemistry Division Quarterly Report: March - May 1953

Quarterly report of the Chemistry Division at the University of California Radiation Laboratory providing updates for each department about current findings and ongoing research.
Date: June 25, 1953
Creator: Lawrence Radiation Laboratory. Chemistry Division.
System: The UNT Digital Library
Flora of Healthy Dogs: [Part] 2. Isolation of Enteroviruses from Lower Intestines (open access)

Flora of Healthy Dogs: [Part] 2. Isolation of Enteroviruses from Lower Intestines

Fecal specimens from apparently healthy dogs were inoculated into MK, DK, HeLa, and CP cells. Twenty-six cytopathic agents were isolated in MK, 11 in HeLa, and 4 in CP, but none in DK cells. Neutralization tests indicated that all but one of the viruses were either strains of ECHO type 6 or were closely related to it. Twenty-one of 29 dogs were carrying the virus.
Date: June 1963
Creator: Clapper, W. E. & Pindak, F. F.
System: The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958 (open access)

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: June 24, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
In-Pile Test of Prototype ML-1 Fuel Elements (open access)

In-Pile Test of Prototype ML-1 Fuel Elements

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
System: The UNT Digital Library
STEP Project Quarterly Technical Report: January-June 1964 (open access)

STEP Project Quarterly Technical Report: January-June 1964

Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
Date: June 1965
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
System: The UNT Digital Library
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia (open access)

Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date: June 7, 1962
Creator: Kitts, F. G. & Clark, W. E.
System: The UNT Digital Library
Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968 (open access)

Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968

Report containing material from several Oak Ridge National Laboratory groups regarding nuclear safety.
Date: June 1969
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964 (open access)

Physics Division Annual Progress Report, January 31, 1964

Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Date: June 1964
Creator: Oak Ridge National Laboratory. Physics Division.
System: The UNT Digital Library
Procedures for Fabricating Aluminum-Base ATR Fuel Elements (open access)

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Date: June 1964
Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.
System: The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual (open access)

Oak Ridge National Laboratory Radioisotopes Procedures Manual

Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Date: June 1964
Creator: Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.
System: The UNT Digital Library
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process (open access)

Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process

Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Date: June 1965
Creator: Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.
System: The UNT Digital Library
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C (open access)

In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1965 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1965

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Trauger, D. B. & Whitman, G. D.
System: The UNT Digital Library