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Salt Bath Heat Transfer Rates for Uranium Plate
Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date:
February 1, 1962
Creator:
Burditt, R. B.
System:
The UNT Digital Library
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel
The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date:
February 1965
Creator:
Richman, R. B.
System:
The UNT Digital Library
Flow Stability of Gas-Solids Suspensions: Final Report
From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.
Date:
February 1964
Creator:
Wachtell, G. P. & Waggener, J. P.
System:
The UNT Digital Library
An Industrial Gamma Irradiator for Medical Supplies
From foreword: This report presents the preliminary design of an industrial gamma irradiator for the sterilization of medical supplies.
Date:
February 19, 1960
Creator:
Frankfort, J. Harry; Haram, S. & Wallach, S.
System:
The UNT Digital Library
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F
Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date:
February 28, 1961
Creator:
McDonald, J. S.
System:
The UNT Digital Library
Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator
Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date:
February 28, 1961
Creator:
Webster, L. J.
System:
The UNT Digital Library
Design Modifications to the SRE during FY 1960
Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date:
February 15, 1961
Creator:
Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
System:
The UNT Digital Library
Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date:
February 1, 1965
Creator:
Willard, R. M. & Schmitt, A. R.
System:
The UNT Digital Library
The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date:
February 1, 1965
Creator:
Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
System:
The UNT Digital Library
Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits
Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date:
February 1, 1963
Creator:
Holland, J. W.
System:
The UNT Digital Library
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators.
Date:
February 1, 1965
Creator:
Casey, D. F.; Hammer, J. J.; Logan, D. & Williams, M. C.
System:
The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
February 3, 1961
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Mechanical Properties of Zircaloy-2
Abstract: The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrogen content, and the presence or absence of a notch.
Date:
February 1, 1961
Creator:
Mehan, R. L. & Wiesinger, F. W.
System:
The UNT Digital Library
Flux Control for Irradiation Experiments
Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date:
February 1, 1965
Creator:
McCarty, W. K.
System:
The UNT Digital Library
Comparative Fuel Cycle Evaluations, Low Decontamination Pyroprocessing, and Aqueous Reprocessing: Part 2. UC Fuel in a Thermal Reactor
From abstract: Preliminary cost estimates for fuel cycles using both aqueous and CARBOX reprocessing are presented.
Date:
February 15, 1965
Creator:
Mattern, K. L. & Colby, L. J., Jr.
System:
The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date:
February 1, 1965
Creator:
Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System:
The UNT Digital Library
Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head
Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
Date:
February 20, 1965
Creator:
Lemcoe, M. M.
System:
The UNT Digital Library
Dibutyl Carbitol Solvent Extraction of Polonium-210 from Nitric Acid Solutions of Irradiated Bismuth
Abstract: "A continuous countercurrent solvent extraction process utilizing dibutyl carbitol as the extractant has been developed for separating 210Po from large amounts of associated bismuth. Both laboratory and pilot plant data demonstrate the process is a suitable headend step in recovery of kilogram quantities of 210Po. Typically, the extraction process recovers over 98% of the 210Po, essentially free from bismuth (Bi DF>1500), in a dilute HNO3 solution suitable as a starting material for final concentration and purification steps."
Date:
February 1968
Creator:
Schulz, Wallace W. & Richardson, G. L.
System:
The UNT Digital Library
Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations
This report follows a study that was made to develop comparative fuel cycle costs for nitride and carbide fuels in a 1000 MWe sodium-cooled fast-breeder reactor.
Date:
February 1968
Creator:
Fletcher, John F. & Greenborg, Jess
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
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:
February 1965
Creator:
Trauger, D. B. & Whitman, G. D.
System:
The UNT Digital Library
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date:
February 1969
Creator:
Oak Ridge National Laboratory. Metals and Ceramics Division.
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library