Hydrogen isotope distillation for the Tritium Systems Test Assembly

A system of four, interlinked, cryogenic fractional distillation columns has been designed as a prototype for fuel processing for fusion power reactors. The distillation system will continuously separate a feedstream of 360 g moles/day of roughly 50-50 deuterium-tritium containing approximately 1% H into four product streams: (1) a tritium-free stream of HD for waste disposal; (2) a stream of high-purity D2 for simulated neutral beam injection; (3) a stream of DT for simulated reactor refueling; and (4) a stream of high purity T2 for refueling and studies on properties of tritium and effects of tritium on materials