UNT Libraries Government Documents Department - 35 Matching Results

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Analytical Chemistry Division Annual Progress Report, December 31, 1960

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.

Date: 1961

Creator: Oak Ridge National Laboratory

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: February 22, 1961

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.

Date: August 10, 1961

Creator: Aerojet-General Corporation

Item Type: Report

open access

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.

Date: September 21, 1961

Creator: Oak Ridge National Laboratory. Chemical Technology Division.

Item Type: Report

open access

A Compilation of Information on Gamma-Ray Spectra Resulting from Thermal-Neutron Capture

Report containing a series of thermal-neutron capture gamma-ray spectra collected in a tabular form.

Date: 1961

Creator: Troubetzkoy, E. & Goldstein, H.

Item Type: Report

open access

Corn Pone: A Multigroup, Multiregion Reactor Code

Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.

Date: 1961?

Creator: Kinney, W. E. & Coveyou, R. R.

Item Type: Report

open access

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.

Item Type: Report

open access

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).

Date: February 1961

Creator: Pessl, H. J.

Item Type: Report

open access

Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination

Economic and hazards calculation of pot calcination of Purex and Thorex wastes.

Date: October 16, 1961

Creator: Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.

Item Type: Report

open access

Experimental Stress Analysis of EGCR Pressure Vessel

Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.

Date: 1961

Creator: Greenstreet, B. L.; Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R. & LaVerne, M. E.

Item Type: Report

open access

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.

Date: April 18, 1961

Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.

Item Type: Report

open access

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.

Date: September 1961

Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.

Item Type: Report

open access

Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

Date: March 1961

Creator: Baars, R. E.

Item Type: Report

open access

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.

Date: October 31, 1961

Creator: Oak Ridge National Laboratory. Health Physics Division.

Item Type: Report

open access

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.

Item Type: Report

open access

Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements

Laboratory fabrication and testing of an inline densimeter.

Date: July 19, 1961

Creator: Mackey, T. S.

Item Type: Report

open access

Interim Report on Corrosion by Zirconium-Base Fluorides

Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.

Date: January 17, 1961

Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.

Item Type: Report

open access

Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel

Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).

Date: 1961

Creator: Goode, J. H. & Flanary, J. R.

Item Type: Report

open access

Large-Scale Slurry-Circulation System, 300-SM

Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.

Date: December 21, 1961

Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.

Item Type: Report

open access

Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960

Programming research in the construction of a translator to Oracle language from ALGOL.

Date: April 6, 1961

Item Type: Report

open access

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.

Item Type: Report

open access

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

Item Type: Report

open access

Numerical Results for EGCR Moderator-Element Stress Problems

From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."

Date: July 3, 1961

Creator: Hulbert, Lewis E. & Redmond, Robert F.

Item Type: Report

open access

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.

Item Type: Report

UNT Libraries Government Documents Department - 35 Matching Results

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Analytical Chemistry Division Annual Progress Report, December 31, 1960

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Chemical Technology Division Annual Progress Report, May 31, 1961

A Compilation of Information on Gamma-Ray Spectra Resulting from Thermal-Neutron Capture

Corn Pone: A Multigroup, Multiregion Reactor Code

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination

Experimental Stress Analysis of EGCR Pressure Vessel

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Final Design Report: DR-1 Gas Loop

Health Physics Division Annual Progress Report, July 31, 1961

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements

Interim Report on Corrosion by Zirconium-Base Fluorides

Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel

Large-Scale Slurry-Circulation System, 300-SM

Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Numerical Results for EGCR Moderator-Element Stress Problems

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960