Choice of the Optimum Composition of the Solution Fuel for a Homogeneous Reactor and of Termoxid Sorbent for Recovering 99Mo

Abstract

T-52 sorbent was chosen for recovering ⁹⁹Mo from low-enriched uranium fuel of a homogeneous solution reactor, because this sorbent exhibits the maximal ⁹⁹Mo distribution coefficient in sorption from solutions containing 150–360 g L^–1 uranium. The use of sulfate and nitrate solutions for producing and recovering ⁹⁹Mo from the fuel of a homogeneous solution reactor was compared. The optimum composition of the solution fuel of a commercial reactor for ⁹⁹Mo production was suggested: nitric acid uranium solution (20% ²³⁵U, 100–200 g L^–1, 1 M HNO₃).