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A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
Partner: UNT Libraries Government Documents Department

U-233 Power-Breeder Reactor: Reactor Design and Feasibility Problem

Description: Report containing information regarding several designs of breeder reactors that utilizes the circulation of solid particles consisting of a fuel-moderator mixture, from the core to a separate heat exchanger vessel from which the solids flow freely to and through the core by gravity" (p. 13). Appendix begins on page 117.
Date: January 1954
Creator: Halik, R. R.; Beckberger, L. H.; Haibeck, J. M.; Mealia, J. E.; Northrop, W. A.; Rees, D. R. et al.
Partner: UNT Libraries Government Documents Department

Reactor Engineering Division Quarterly Report: December 1, 1953 Through March 30, 1954

Description: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Date: April 15, 1954
Creator: Argonne National Laboratory. Reactor Engineering Division.
Partner: UNT Libraries Government Documents Department