The Reprocessing of Beryllium-Base Reactor Fuels : a Chemical Feasibility Study of a Modified Thorex Process for the Recovery of the Uranium and Thorium
Description:
Stable solutions of basic beryllium nitrate can be formed with beryllium concentrations up to 9M, and an NO3/Be mole ratio as low as 1:1. The efficiency of basic beryllium nitrate as an agent for salting out uranium into a tributylphosphate/kerosene solvent has been compared with that of other salts. It appears possible to separate uranium and thorium from beryllium and fission products using a modified Thorex process in which beryllium nitrate replaces aluminum nitrate.
Date:
August 1962
Creator:
Farrell, M. S.; Orrock. B. J. & Temple, R. B.
Partner:
UNT Libraries Government Documents Department