Hydrogen isotope distillation for the Tritium Systems Test Assembly

Conference · Sun Jan 01 04:00:00 EST 1978

OSTI ID:6715858

Bartlit, J R; Denton, W H; Sherman, R H

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.

• Research Organization: Los Alamos Scientific Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6715858
• Report Number(s): LA-UR-78-1325; CONF-780508-41
• Country of Publication: United States
• Language: English

Related Subjects

060200* -- Fusion Fuels-- Processing-- (-1987)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CRYOGENIC FLUIDS
CRYOGENICS
DEUTERIUM
DISTILLATION
ELEMENTS
FLUIDS
FUELS
HYDROGEN
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PROCESSING
RADIOISOTOPES
SEPARATION PROCESSES
STABLE ISOTOPES
TEST FACILITIES
THERMONUCLEAR FUELS
THERMONUCLEAR REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES