Access
55 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
55
next
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
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
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
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
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
"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
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
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
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
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
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
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
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
VBWR Stability Test Report
Analysis of the stability of boiling water reactors.
Date:
June 1963
Creator:
U.S. Atomic Energy Commission
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
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
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
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
June 27, 1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Irradiation Effects in the EGCR Fuel
From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date:
June 1965
Creator:
Baumann, C. D.
System:
The UNT Digital Library
Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel
The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date:
June 1965
Creator:
Fletcher, R. D.
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
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
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy
This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date:
June 1961
Creator:
Todd, R. H.
System:
The UNT Digital Library