Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Progress Report on Refining of MgX and Other Uranium-Bearing Materials

From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
Date: August 31, 1950
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on the Concentration of Pitchblende (open access)

Progress Report on the Concentration of Pitchblende

Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date: December 31, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Topical Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Topical Report on Refining of MgX and Other Uranium-Bearing Materials

This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
Date: December 31, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Identification of Slag Constituents from Uranium Metal Production Bombs (open access)

Identification of Slag Constituents from Uranium Metal Production Bombs

Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
Date: January 31, 1952
Creator: Vaughan, D. A.; Cocks, G. G. & Schwartz, C. M.
System: The UNT Digital Library
Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements (open access)

Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
System: The UNT Digital Library
Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations (open access)

Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations

Report discussing laboratory investigations of thorium nitrate purification. Batch equilibrium data, solubility data, viscosity data, density data, and the results seven batch countercurrent extraction tests and two selective stripping tests are included.
Date: July 31, 1952
Creator: Ewing, R. A.; Fishel, J. B.; Kiehl, S. J., Jr.; Sharpe, R. E. & Bearse, A. E.
System: The UNT Digital Library
Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations (open access)

Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations

From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
Date: July 31, 1952
Creator: Burkhart, C. A.; Foley, D. D.; Retzke, F. A.; Filbert, Robert B., Jr. & Clegg, John W.
System: The UNT Digital Library
Final Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Final Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report discusses tests of several nonaqueous extractive methods meant to leach Western ores of uranium and vanadium. Explanations of different methods are given as well as their extraction results.
Date: January 31, 1955
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Enamels for the Protection of Aluminum Cans for Uranium Slugs (open access)

Enamels for the Protection of Aluminum Cans for Uranium Slugs

The following report examines the most suitable enamels recommended for protection of aluminum slug cans.
Date: August 31, 1955
Creator: Schultz, John; Tripp, Harlan P.; King, Burnham William, 1907- & Duckworth, Winston H.
System: The UNT Digital Library
Neutron-Flux Measurements in a Flat Plat Fuel Element (open access)

Neutron-Flux Measurements in a Flat Plat Fuel Element

The following report presents neutron-flux measurements with the Mark I element, which include neutron-flux distribution and flux depression within the element.
Date: October 31, 1957
Creator: Morgan, Walter R.; Anno, James N., Jr. & Chastain, Joel W., Jr.
System: The UNT Digital Library