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.
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
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.
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
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
The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
Contributing Partner: UNT Libraries Government Documents Department
Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Date: March 9, 1962
Creator: Gibson, G. W. & Shupe, O. K.
Description: Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).
Contributing Partner: UNT Libraries Government Documents Department
Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process

Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process

Date: 1963
Creator: Buckham, J. A.; P'Pool, R. S. & Pitkin, R. G.
Description: Report that summarizes the design work of the radioactive chop-leach demonstration at the Idaho Chemical Processing Plant presented in two parts.
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
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
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
FIRST PREV 1 2 NEXT LAST