Resource Type

Metallurgy Research Operation: Quarterly Progress Report, January - March 1965 (open access)

Metallurgy Research Operation: Quarterly Progress Report, January - March 1965

Quarterly progress report on a project to test the radiation effects on metallurgy.
Date: April 15, 1965
Creator: Cadwell, J. J.; Bierlein, T. K.; Bement, A. L.; Dillon, R. L. & Wheeler, R. G.
System: The UNT Digital Library
Fast Flux Test Facility Studies Progress Report: April 1965 (open access)

Fast Flux Test Facility Studies Progress Report: April 1965

From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date: April 1965
Creator: Astley, E. R.
System: The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water (open access)

A Sequence for Predicting Waste Transport by Ground Water

From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date: April 15, 1965
Creator: Nelson, R. William
System: The UNT Digital Library
Geophysical Seismic Evaluation Study at Hanford (open access)

Geophysical Seismic Evaluation Study at Hanford

From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
Date: December 1964
Creator: Brown, Ruth E. & Raymond, John R.
System: The UNT Digital Library
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel (open access)

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
INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns (open access)

INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns

From introduction: "...a logical system has been developed to yield rapidly the indexing of a given powder pattern by using an electronic computer."
Date: January 1965
Creator: Goebel, J. B. & Wilson, Archie Spencer
System: The UNT Digital Library
PRTR second generation shim assembly (open access)

PRTR second generation shim assembly

From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
System: The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (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.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965

Report documenting radioactive fallout across the world, including material in the atmosphere, on land, and that has deposited into food and water supplies.
Date: October 1, 1965
Creator: Hardy, Edward P., Jr. & Rivera, Joseph
System: The UNT Digital Library
Numerical Results for EGCR Moderator-Element Stress Problems (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.
System: The UNT Digital Library
In-Pile Test of Prototype ML-1 Fuel Elements (open access)

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.
System: The UNT Digital Library
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel (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.
System: The UNT Digital Library
Applied Health Physics Annual Report for 1963 (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.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964 (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.
System: The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964 (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.
System: The UNT Digital Library
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy (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.
System: The UNT Digital Library
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor (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.
System: The UNT Digital Library
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 (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
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1 (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
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2

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
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples

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
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.4 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.4

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: 1965
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.5 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.5

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
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.6 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.6

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: 1965
Creator: Adams, R. K. & Davisson, E. G.
System: The UNT Digital Library