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Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants

Description: Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and the results of non-destructive and destructive metallographic analyses.
Date: January 23, 1962
Creator: Haraway, E. S. & Saccocio, R. M.
Partner: UNT Libraries Government Documents Department
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Engineering Test Reactor Critical Facility Control System Manual

Description: This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
Partner: UNT Libraries Government Documents Department
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