A Microdetermination of Uranium by Ferric Sulfate Titration (open access)

A Microdetermination of Uranium by Ferric Sulfate Titration

Abstract: "Following nitrate removal by means of a three-stage hydrochloric acid digestion, uranium was reduced with chromous sulfate reagent. In an inert atmosphere, the quadrivalent uranium was titrated at 80-95[degrees] with standard ferric sulfate solution. The end point was obtained with a potentiometric cell including a platinum in-titrant reference electrode and a platinum indicator electrode. Application was made to various low leverl uranium solutions. For samples containing 1 - 12 milligrams or uranium, less than one percent error may be expected. Iron and chromium do not interfere."
Date: February 16, 1949
Creator: Christopherson, E. W.
System: The UNT Digital Library
Preparation of Samples of 42 Weight Percent U-Al Alloy for Pile Irradiation Tests (open access)

Preparation of Samples of 42 Weight Percent U-Al Alloy for Pile Irradiation Tests

Abstract: Processes are described for preparing small samples of 42 wt. % U-Al alloy (uranium enriched with U235) for pile irradiation studies. In the course of this work it was found that the size of the massive Al-U grains remains substantially unaltered during hot rolling.
Date: February 15, 1949
Creator: Smith, C. D.
System: The UNT Digital Library
Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions (open access)

Corrosion Tests on Tantalum, Hastelloy C and Duriron in 234-5 Project Solutions

Introduction: "Room temperature and elevated temperature, static immersion and vapor suspicion, corrosion tests were conducted with Duriron, Hastelloy C, and tantalum in hydriotic acid and 234-5 project process supernatant solution (synthetic environments. The data relevant to these tests are contained herein."
Date: February 25, 1949
Creator: Work, J. B. & Koenig, W. W.
System: The UNT Digital Library