Caustic Treatment of Zircon in the Preparation of Pure Zirconium Compounds (open access)

Caustic Treatment of Zircon in the Preparation of Pure Zirconium Compounds

From abstract: This investigation was conducted in order to develop a process whereby the most abundant zirconium ore, namely zircon, could economically be put into solution and purified adequately for use in hafnium separation processes employing liquid-liquid extraction. Secondary aims concerned the preparation of pure zirconyl chloride, zirconyl nitrate, zirconyl sulfate, and zirconium oxide from the zircon ore.
Date: June 23, 1953
Creator: Spink, Donald R. & Wilhelm, Harley A.
System: The UNT Digital Library
Engineering Test Reactor Critical Facility Control System Manual (open access)

Engineering Test Reactor Critical Facility Control System Manual

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
System: The UNT Digital Library
Modified Liquid Phase Reactor (open access)

Modified Liquid Phase Reactor

The following report describes a modified Kraus type reactor that had been constructed for use in bets chemical conversion operations.
Date: June 23, 1944
Creator: Zuidema, J. W. & Ballard, A. E.
System: The UNT Digital Library
Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride (open access)

Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride

The uranium recovery processes which are in operation or under construction at the present time--TBP, Redox and Purex--yield an aqueous uranyl nitrate solution as the recovered uranium product. For conversion of this recovered uranium to UF6 for feed to the gaseous diffusion plants, the uranyl nitrate in the solution is concentrated with or without prior organic stripping, calcined to UC3, reduced to UO2 with hydrogen, hydro-fluorinated to UF4 with RF, and finally fluorinated to UF6 with elemental fluorine.
Date: June 23, 1953
Creator: Clagett, F. & Harmon, M. K.
System: The UNT Digital Library
Sludge Acidification - Progress Report (open access)

Sludge Acidification - Progress Report

Report discussing the progress made on research concerning sluge-supernate acidification. This report focuses mainly on "'reverse strike' acidification and the observations of the physical characteristics of the test material," which was a synthetic incubated metal waste.
Date: June 23, 1950
Creator: Harmon, M. K.
System: The UNT Digital Library
Structural Evaluation of Underground Waste Storage Tanks (open access)

Structural Evaluation of Underground Waste Storage Tanks

To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.
Date: June 23, 1955
Creator: Smith, Edgar F.
System: The UNT Digital Library
Thermal Conductivity of Reactor Fuel Element Materials (open access)

Thermal Conductivity of Reactor Fuel Element Materials

Report presenting data on the thermal conductivity of fuel element materials with short summaries.
Date: June 23, 1954
Creator: Westphal, R. C.
System: The UNT Digital Library
The Variation in Maximum Power Density and Maximum Heat Flux of the Core and Blanket Thorium Plates in the Converter Reactor with Irradiation Time (open access)

The Variation in Maximum Power Density and Maximum Heat Flux of the Core and Blanket Thorium Plates in the Converter Reactor with Irradiation Time

This report describes how to achieve the variation in maximum power density and maximum heat flux of the core and blanket thorium plates in the converter reactor with irradiation time.
Date: June 23, 1952
Creator: Sletten, H. L.
System: The UNT Digital Library