(385a) Design and Operation of a System for the Preparation of a Molten Chloride Nuclear Fuel Salt

The design and operation of a system to prepare a uranium containing chloride fuel salt from impure components will be presented. Impure NaCl and CaCl2 are first dehydrated using a combination of vacuum heating and reaction with HCl gas. Metal impurities are removed using Ca metal. Uranium is oxidized into the salt using FeCl2 as an oxidant to form UCl3. The success of the process is determined in-situ by analyzing the salt using cyclic voltammetry and analyzing the off-gas using Quadrupole Mass Spectrometer or acid-base titration. The purity of the salt will be confirmed using TGA/DSC and ICP-MS. The design considerations of the reaction system will be discussed including the quartz and teflon reaction vessel. The prepared chloride fuel salt may be used to conduct neutron experiments in a test reactor such as the planned Versatile Test Reactor.