UNT Libraries Government Documents Department - 123 Matching Results

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In-Pile Test of Prototype ML-1 Fuel Elements

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.

Date: June 1964

Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.

Item Type: Report

open access

Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units

Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.

Date: 1962

Creator: Fraas, A. P.

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

Calculation of Suspension Peptization

Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).

Date: 1960

Creator: Sweeton, F. H.

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

Applied Health Physics Annual Report for 1963

Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.

Date: August 1964

Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.

Item Type: Report

open access

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.

Item Type: Report

open access

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.

Item Type: Report

open access

Health Physics Division Annual Progress Report, July 31, 1969

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

Date: October 1969

Creator: Oak Ridge National Laboratory. Health Physics Division.

Item Type: Report

open access

Instrumentation and Controls Division Annual Progress Report, September 1, 1968

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

Date: February 1969

Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.

Item Type: Report

open access

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968

From introduction: "Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program."

Date: February 1969

Creator: Oak Ridge National Laboratory

Item Type: Report

open access

Physics Division Annual Progress Report, January 31, 1964

Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.

Date: June 1964

Creator: Oak Ridge National Laboratory. Physics Division.

Item Type: Report

open access

Mechanical Properties of Some Refractory Metals and their Alloys

Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.

Date: April 1964

Creator: McCoy, H. E., Jr.; Stephenson, R. L. & Weir, J. R., Jr.

Item Type: Report

open access

Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy

Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.

Date: March 1965

Creator: Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.

Item Type: Report

open access

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.

Date: June 1964

Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.

Item Type: Report

open access

Oak Ridge National Laboratory Radioisotopes Procedures Manual

Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.

Date: June 1964

Creator: Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.

Item Type: Report

open access

Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process

Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.

Date: June 1965

Creator: Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.

Item Type: Report

open access

Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor

Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.

Date: 1964

Creator: Knight, R. W. & Leitten, C. F., Jr.

Item Type: Report

open access

A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.

Date: August 1964

Creator: Salmon, Royes

Item Type: Report

open access

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1

This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.

Date: March 1965