Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Date: March 1961
Creator: Sharp, R. E.
Description: Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Date: March 1964
Creator: Kitts, F. G.
Description: Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Contributing Partner: UNT Libraries Government Documents Department
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost

MINIMIZER: A Computer Code for Determining Minimum Fuel Cost

Date: July 1965
Creator: Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
Description: Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Contributing Partner: UNT Libraries Government Documents Department
Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Date: August 1964
Creator: Walker, R. A. & Russell, J. T.
Description: Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.
Contributing Partner: UNT Libraries Government Documents Department
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Date: July 1963
Creator: Jackson, C. N., Jr.
Description: Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Contributing Partner: UNT Libraries Government Documents Department
Pressure-Pulse Propagation in Two-Phase One- and Two-Component Mixtures

Pressure-Pulse Propagation in Two-Phase One- and Two-Component Mixtures

Date: March 1971
Creator: Henry, R. E.; Grolmes, M. A. & Fauske, H. K.
Description: Report issued by the Argonne National Laboratory discussing the propagation velocity of pressure pulses in two-phase mixtures. As stated in the abstract, "in this study, a comprehensive analytical development of the propagation velocity of small pressure pulses is presented for bubble, annular, stratified, droplet, and slug-flow regimes. Particular attention is given to the influence of flow regime on the momentum transfer between phases" (p. 9). This report includes tables, illustrations, and a photograph.
Contributing Partner: UNT Libraries Government Documents Department
Heat Transfer in an Annulus with Asymmetric Heating

Heat Transfer in an Annulus with Asymmetric Heating

Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. B. & Reynolds, William C., 1933-2004
Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Contributing Partner: UNT Libraries Government Documents Department
Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Engineering development of fluid-bed fluoride volatility processes

Engineering development of fluid-bed fluoride volatility processes

Date: 1964
Creator: Vogel, G. J.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Date: March 1961
Creator: Freshley, M. D.
Description: Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
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