Year: 1978
Type: article
Abstract: 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 D/sub 2/ for simulated neutral beam injection; (3) a stream of DT for simulated reactor refueling; and (4) a stream of high purity T/sub 2/ for refueling and studies on properties of tritium and effects of tritium on materials.
Authors: J.R. Bartlit, W.H. Denton, R.H. Sherman
Language: English
Subfield: Materials Chemistry
Field: Materials Science
Domain: Physical Sciences
Open Access status: green
OpenAlex ID: W18320815
