Radiation Damage to Organic Ion-Exchange Materials (open access)

Radiation Damage to Organic Ion-Exchange Materials

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.
System: The UNT Digital Library
The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor (open access)

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

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
System: The UNT Digital Library
Dynamics of the Supercritical Water Reactor (open access)

Dynamics of the Supercritical Water Reactor

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
System: The UNT Digital Library
Dissolution of Metals in Fused Fluorides (open access)

Dissolution of Metals in Fused Fluorides

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 uranium was dissolved. Variables that appear to affect the dissolution rate are the composition of the fused fluoride, the fused fluoride temperature, the HF flow rate, the metallurgical characteristics of the material being dissolved, and the presence of other metals. The low dissolution rate of 0.001 mil/hr observed for nickel suggests that it may be suitable as a material of construction for reaction vessels.
Date: October 12, 1953
Creator: Leuze, R. E.; Cathers, G. I. & Schilling, C. E.
System: The UNT Digital Library
Revised Z Tables of the Rach Coefficients (open access)

Revised Z Tables of the Rach Coefficients

From introduction: "54 tables are given of the Z coefficients."
Date: May 28, 1953
Creator: Biedenharn, L. C.
System: The UNT Digital Library