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1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1
From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
Date:
June 1967
Creator:
Goulding, B. J.
System:
The UNT Digital Library
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Date:
June 2, 1958
Creator:
Spear, W. G.
System:
The UNT Digital Library
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
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date:
June 1959
Creator:
Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
System:
The UNT Digital Library
Cobalt-60 Bulk Grain Irradiator: Study Report
Report issued by the Brookhaven National Laboratory discussing bulk grain irradiators. As stated in the abstract, "this report presents the results of a study to conceive, evaluate, review and estimate costs for a number of suitable designs for a Cobalt-60 Bulk Grain Irradiator; select a preferred type; and establish required criteria for future detail design and construction of the selected concept" (p. ii). This report includes tables, and illustrations.
Date:
June 30, 1963
Creator:
Brookhaven National Laboratory
System:
The UNT Digital Library
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
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date:
June 1961
Creator:
Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System:
The UNT Digital Library
Electronuclear Research Division Annual Progress Report, December 31, 1963
Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Electronuclear Research Division.
System:
The UNT Digital Library
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes
Report documenting the problems, design, and operation of countercurrent liquid-foam columns.
Date:
June 1965
Creator:
Haas, P. A.
System:
The UNT Digital Library
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
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
Engineering Test Reactor Critical Facility Control System Manual
This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date:
June 23, 1961
Creator:
Meichle, F. A.
System:
The UNT Digital Library
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
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date:
June 26, 1959
Creator:
Jackson, P. M.
System:
The UNT Digital Library
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
Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, June 1966
Progress report discussing the activities in "a program of studies of nutron-deficient nuclides using the techniques of gamma-ray spectroscopy" (abstract).
Date:
June 1966
Creator:
Heath, R. L. & Cline, J. E.
System:
The UNT Digital Library
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
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques
Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.
Date:
June 1964
Creator:
Ryan, B. A.
System:
The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date:
June 1961
Creator:
Muraoka, J.
System:
The UNT Digital Library
HRP Radiation Corrosion Studies: In-Pile Loop L-4-11
Report issued by the Oak Ridge National Laboratory discussing radiation corrosion studies. As stated in the introduction, "the purpose of this experiment was to compare the performance of a large number of materials under similar irradiation and exposure conditions" (p. 1). This report includes tables, illustrations, and photographs.
Date:
June 27, 1958
Creator:
McWherter, J. R. & Baker, J. E.
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
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
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
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
Instrumentation and Controls Division Annual Progress Report, September 1, 1963
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library