Search Results

open access

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Dibutyl Carbitol Solvent Extraction of Polonium-210 from Nitric Acid Solutions of Irradiated Bismuth

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Description: From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Date: February 1965
Creator: Miller, R. W.; McCardell, Richard K. & Lagier, T. F.
Partner: UNT Libraries Government Documents Department
open access

Flux Control for Irradiation Experiments

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Jones, Edith Seymour
Partner: UNT Libraries Government Documents Department
open access

The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

Description: 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
Partner: UNT Libraries Government Documents Department
open access

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Advanced Test Reactor Servo Regulator Rod Test Program

Description: From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T., III
Partner: UNT Libraries Government Documents Department
open access

Flow Stability of Gas-Solids Suspensions: Final Report

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Description: 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.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen