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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: AEC research and development report
 Collection: Technical Report Archive and Image Library
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
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

Date: June 1964
Creator: Ryan, B. A.
Description: Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.
Contributing Partner: UNT Libraries Government Documents Department
A New Model Concept for Large Nuclear Reactors

A New Model Concept for Large Nuclear Reactors

Date: June 1964
Creator: Harvey, R. A.
Description: Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Contributing Partner: UNT Libraries Government Documents Department
Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Date: February 1964
Creator: Richardson, G. L.
Description: Report that "presents the results of pilot plant studies on the application of the D2EHPA (di-2-ethylhexyl phosphoric acid) solvent system to the needs of the Hanford Waste Management Program" (p. 1).
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
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Date: January 1964
Creator: Hanford Atomic Products Operation. N-Reactor Project Section.
Description: Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Contributing Partner: UNT Libraries Government Documents Department
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Date: August 1962
Creator: Hanthorn, H. E.
Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Contributing Partner: UNT Libraries Government Documents Department
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