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Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
Discussion of laboratory tests to reduce uranium corrosion.
Date:
October 14, 1964
Creator:
Sprague, T. P.; Googin, J. M. & Phillips, L. R.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date:
October 23, 1961
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant
Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date:
October 5, 1962
Creator:
Miskell, R. V.
System:
The UNT Digital Library
Potential Applications of Nuclear Energy for Process and Space Heat in the United States
A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date:
October 1958
Creator:
Geiringer, Paul Ludwig & Goodfriend, Morton J.
System:
The UNT Digital Library
Feed Materials Production Center Summary Technical Report: July 1, 1963-September 30, 1963
From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.
Date:
October 28, 1963
Creator:
unknown
System:
The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod
Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
Date:
October 1, 1954
Creator:
Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
System:
The UNT Digital Library
A Feasibility Study for the Use of an Extended Pm¹⁴⁷ Source for Analytical Fluorescence Spectroscopy: Final Report
From summary: The design of a spectrometer with the requisite improvement in crystals facilitates X-ray tube fluorescence.
Date:
October 31, 1960
Creator:
Brech, Frederick
System:
The UNT Digital Library
An Evaluation of Fossil Superheat for Nuclear Power Plants
From introduction: This report sets forth the results of a study of the evaluation of fossil fuel superheat in nuclear power plants.
Date:
October 1960
Creator:
unknown
System:
The UNT Digital Library
A Photographic Study of Boiling Flow
From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.
Date:
October 25, 1963
Creator:
Vohr, John Henry
System:
The UNT Digital Library
Radioisotopes at Work for Agriculture
Introduction: The Office of Isotopes Development of the United States Atomic Energy Commission has requested that Stanford Research Institute prepare a report on the applications of radioisotopes in agriculture.
Date:
October 1959
Creator:
Homan, A. Gerlof & Tarrice, Richard R.
System:
The UNT Digital Library
Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator
Introduction: this report covers two series of tests run on a Freon evaporator containing a vertical copper tube having an outside diameter of 7/8 of an inch, heated externally for a length of 35 inches by steam condensing in a concentric jacket.
Date:
October 19, 1961
Creator:
Allen, Charles F.
System:
The UNT Digital Library
Organic Reactor Waste Gas Analyzer
The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date:
October 15, 1958
Creator:
Gilroy, H. M. & Edwards, R. J.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode
Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date:
October 15, 1961
Creator:
Ballif, J. L.
System:
The UNT Digital Library
Criticality-Accident Dosimetry Studies
Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date:
October 15, 1964
Creator:
Bailey, J. C.
System:
The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System
Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date:
October 30, 1961
Creator:
Johnson, H. E.
System:
The UNT Digital Library
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date:
October 9, 1964
Creator:
Freede, W. J. & Roberts, J. K.
System:
The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date:
October 15, 1964
Creator:
Barbour, P. & Davis, W. W.
System:
The UNT Digital Library
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Abstract: The nature of the high boiling radiolysis products of OMRE coolants was studied extensively.
Date:
October 15, 1964
Creator:
Keen, R. T.; Orr, W. L.; Miller, L. J.; Sullivan, R. J. & Shepard, R. C.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date:
October 15, 1964
Creator:
Lurie, H. & Noyes, R. C.
System:
The UNT Digital Library
A Method of Calculating Boundary-Layer Thickness in Axisymmetric Nozzles with Laminar Hypersonic Flow
Abstract: "The excellent agreement between measured boundary layer thickness and thickness calculated by Sivells and Payne recommends their method for calculating turbulent boundary layer growth in axisymmetric hypersonic nozzles. It was thought worthwhile to adapt their approach to the laminar boundary layer. This analysis, along with a limited amount of corroborating data, is presented herein."
Date:
October 1959
Creator:
Johnson, Arlo F.
System:
The UNT Digital Library
Final Summary Report of the Gas-Cooled Reactor Experiment-1
Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date:
October 1963
Creator:
Chesworth, R. H.
System:
The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE
Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date:
October 15, 1964
Creator:
Peckinpaugh, C. L.
System:
The UNT Digital Library