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Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Description: Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date: May 1, 1958