Chemical Development Section C Progress Report for December 1960 and January 1961 (open access)

Chemical Development Section C Progress Report for December 1960 and January 1961

Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nitrate from the solvent for recycle by contact with a lime slurry.
Date: June 2, 1961
Creator: Brown, K. B.
System: The UNT Digital Library
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961 (open access)

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: June 27, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library