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Recent Developments in the Technology of Sodium-Graphite Reactor Materials

Description: Experimental results on core structural materials, moderator, and fuel materials are discussed. Data are given on grain growth of Zr and thermal conductivity, thermal expansion, and temperatures of various types of graphite. (M.H.R.)
Date: October 31, 1958
Creator: Carter, R. L. & Eichelberger, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Graphite Reactor Power Plant for CPPD

Description: The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U/sup 235/) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors a… more
Date: October 31, 1958
Creator: Olson, R. L.; Gerber, R. C.; Gordon, R. B.; Ross-Clunis, H. A. & Stolz, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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