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 Decade: 1960-1969
 Year: 1963
 Collection: Technical Report Archive and Image Library
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Date: October 1963
Creator: Spear, W. G.
Description: Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
Contributing Partner: UNT Libraries Government Documents Department
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Date: April 1963
Creator: Rieck, H. G. 1922-
Description: Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962

Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962

Date: March 1963
Creator: Scott, P. A.
Description: Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Contributing Partner: UNT Libraries Government Documents Department
Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending March 31, 1963

Gas-Cooled Reactor Project Semiannual Progress Report: for Period Ending March 31, 1963

Date: July 23, 1963
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
Description: Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Contributing Partner: UNT Libraries Government Documents Department
Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962

Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962

Date: February 6, 1963
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Description: Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Contributing Partner: UNT Libraries Government Documents Department
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
Description: Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Date: 1963-01-uu
Creator: Baird, Justus N., Jr.; Sanford, W. R. & Cristy, G. A.
Description: Report containing tests performed to evaluate a reduced pressure backflow preventer. This includes preliminary tests, resulting improvements, and final rests. Appendices begin on page 23.
Contributing Partner: UNT Libraries Government Documents Department
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Date: April 4, 1963
Creator: Oak Ridge National Laboratory
Description: Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Contributing Partner: UNT Libraries Government Documents Department
The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

Date: 1963
Creator: unknown
Description: Report documenting the design of the Oak Ridge National Laboratory Gas-Cooled Clad-Fuel Reactor Power Plant. This includes design criteria and parameters, costs, and descriptions of systems.
Contributing Partner: UNT Libraries Government Documents Department
Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Gas-Cooled Reactor Project Semiannual Progress Report, September 30, 1963

Date: [1963-09-30..1964-01-29]
Creator: Oak Ridge National Laboratory
Description: Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Contributing Partner: UNT Libraries Government Documents Department
Army Reactors Program Annual Progress Report: for Period Ending October 31, 1962

Army Reactors Program Annual Progress Report: for Period Ending October 31, 1962

Date: April 10, 1963
Creator: Oak Ridge National Laboratory
Description: Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Contributing Partner: UNT Libraries Government Documents Department
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963

Date: September 20, 1963
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Description: Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.
Contributing Partner: UNT Libraries Government Documents Department
Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Economic Evaluation of a 300 Mwe Fast Supercritical Pressure Power Reactor

Date: December 9, 1963
Creator: Aase, D. T.; Fox, J. C.; Hennig, R. J.; Peterson, R. E.; Stewart, S. L. & Toyoda, K. G.
Description: Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.
Contributing Partner: UNT Libraries Government Documents Department
The Hanford Isotopes Production Plant Engineering Study

The Hanford Isotopes Production Plant Engineering Study

Date: July 1963
Creator: La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
Description: Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Contributing Partner: UNT Libraries Government Documents Department
High Temperature Short-Time, Uranium Carbide-Metal Reactions

High Temperature Short-Time, Uranium Carbide-Metal Reactions

Date: March 1963
Creator: Christensen, J. A.
Description: Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Contributing Partner: UNT Libraries Government Documents Department
UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels

UT-4: An Automatic Ultrasonic Tester for Closures of Hanford I&E Fuels

Date: May 1963
Creator: Hunter, D. O. 1928- & Zeutschel, M. F.
Description: Report that "describes the equipment, technologies of use, and reliability of an ultrasonic tester - designated UT-4 - capable of detecting very small defects in the brazed closures of reactor fuel elements" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Date: July 30, 1963
Creator: Pessl, H. J.
Description: Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Date: October 1963
Creator: Wheelwright, E. J. (Earl J.) & Roberts, F. P.
Description: Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Contributing Partner: UNT Libraries Government Documents Department
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Date: October 1, 1963
Creator: Hanford Atomic Products Operation
Description: Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Contributing Partner: UNT Libraries Government Documents Department
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Date: October 1963
Creator: Hanford Atomic Products Operation
Description: Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Contributing Partner: UNT Libraries Government Documents Department
Prototype Burst Test Unit for irradiated Pressure Tubes

Prototype Burst Test Unit for irradiated Pressure Tubes

Date: January 1963
Creator: Jackson, P. M.
Description: Report that "describes the development of a prototype test chamber in which sections of irradiated pressure tubes from the Hanford [Laboratories] reactors are burst at elevated temperatures" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor

Date: June 12, 1963
Creator: Fox, J. K.; Magnuson, D. W. & Gilley, L. W.
Description: Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).
Contributing Partner: UNT Libraries Government Documents Department
Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey

Gas-Metal Reactions with Iron- and Nickel-Base Heat Resistant Alloys: An Interpretive Literature Survey

Date: May 1963
Creator: Jones, D. A.
Description: Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
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