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Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

Description: "An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure… more
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry, Quarterly Progress Report, July-September 1953

Description: "Continued progress has been made with the high temperature decontamination processes for irradiated uranium fuel. The fused salt treatment of molten uranium has been extended to UCl3. Plutonium and rare earths were extracted into the UCl3 phase. Direct plutonium distillation from molten irradiated uranium has been scaled up to the hundred gram scale. Solid scavenging experiments using uranium oxide, uranium carbide, and uranium nitride in contact with molten uranium have indicated fission p… more
Date: April 1, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preparation of a Thorium Slurry

Description: "A study has been made of methods to prepare a fluid containing 1 gram of thorium per milliliter. The methods considered were solutions of thorium salts, suspensions of dry solids in water, and collodial suspensions. Thorium oxide, oxalate, and fluoride were tried in conjunction with one or more surface actants, but it was not possible to attain the required thorium concentration. Thorium hydrosol, produced by peptization of thorium hydroxide and subsequent electrodialysis, gave the necessary… more
Date: April 1, 1954
Creator: Silverman, L. & Trego, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SRE Mark II Fuel Handling Machine

Description: Abstract: The Sodium Reactor Experiment Mark II Fuel Handling Machine has been modified to ensure fuel and gas containment during core III operation. A new fuel control system has been designed for the fuel handling machine.
Date: April 20, 1965
Creator: Dietz, H. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

OMRE Fuel Removal and Shipping Equipment

Description: Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date: April 1, 1960
Creator: Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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