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Dissolution of Metals in Fused Fluorides

Description: In scouting tests, a number of metals used in nuclear reactor fuel elements were dissolved by 44.5-48.5-7.0 mole % ZrF4-KF-NaF fused salt at 675°C through which HF was being passed. These included type 304 stainless steel at 4 mils/hr; type 347Nb stainless steel at 7 mils/hr; thorium at 14 mils/hr; nonirradiated uranium at 17 mils/hr; zirconium at 22-35 mils/hr; titanium at 31 mils/hr; and Zircaloy-2 at 22-46 mils/hr. Only small amounts of volatile fission products formed when irradiated uraniu… more
Date: October 12, 1953
Creator: Leuze, R. E.; Cathers, G. I. & Schilling, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Damage to Organic Ion-Exchange Materials

Description: From abstract: "The stability of polystyrene and phenolic ion-exchange resins to radiation from a Co60 source and from absorbed Ce144-PR144 was investigated. Sulfonated polystyrene cation-exchange resins lost 10 to 20% of their capacity per watt-hour of radiation absorbed per gram of oven-dry resin, while the quaternary amine anion-exchange polystyrene resins lost about 40%. Phenolic cation-exchange resins lost only 1%."
Date: March 16, 1953
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor

Description: Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]
Date: January 9, 1953
Creator: Reed, James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamics of the Supercritical Water Reactor

Description: From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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