Halogenation of used aluminum matrix test reactor fuel – a bench-scale demonstration with surrogate materials

Experiments with surrogate materials were performed at bench scale to demonstrate a halogenation technique applicable treatment of used aluminum matrix test reactor fuel. The involves dissolution and separation from fuel in molten-halide salt systems prior disposition the fuel’s uranium fission products. Demonstration was neodymium metal as non-radiological for metal. involved blending forms ammonium lithium chloride or bromide, which upon heating decomposed into ammonia gas respective hydrogen bromide gas. latter reacted metals form halides. At elevated temperatures, halides gasified away halides, fused their Samples distillate salts collected analyzed, yielding extents removal that ranged 94.5–98.2% chlorination runs 91.4–97.8% bromination runs. No detected fractions. Some experiments repeated excess reactants, portion processed consolidated waste form.