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In-Reactor Autoclave Corrosion Studies II : Autoclave Z-19

Description: In order to test the effect of chromate ion on the corrosion of Zircaloy-2 a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (… more
Date: March 22, 1957
Creator: Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Partner: UNT Libraries Government Documents Department
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Prelimiary Analysis of the Plutonium Recycle Program Reactor Shield

Description: It is the purpose of this report to present the preliminary analysis of the PRPR shield. The results reflect a considerable degree of conservatism because of uncertainties that were present in the preliminary estimates of neutron and gamma fluxes incident on the shield.
Date: December 22, 1956
Creator: Wood, D. V. & Weeks, J. L.
Partner: UNT Libraries Government Documents Department
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