Development of a high temperature isotopic exchange process for recovering tritium from fusion fuel impurities

Conference · Sun Mar 01 04:00:00 EST 1992 · Fusion Technology; (United States)

OSTI ID:5067355

Sood, S K; Kalyanam, K M; Woodall, K B ^[1]; Busigin, A ^[2]

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1. Ontario Hydro, Toronto, ON (Canada)
2. NITEK Corp., 939 Griffith Street, London, Ontario N6K 3S2 (CA)

A High Temperature Isotopic Exchange (HITEX) process has been developed for processing of fusion fuel streams. The design has advantages over previous systems which have been based on catalytic oxidation or decomposition of impurities, since it eliminates the need for impurity oxidation and electrolysis of DTO, and does not rely on complicated catalytic decomposition reactions. A conceptual flowsheet of complete HITEX-based fuel processing system is described. Testing of the HITEX reactor is underway with deuterated impurities. Details of the experimental HITEX test loop are reported in this paper, and the test loop is compared to a HITEX design recently proposed for ITER (International Thermonuclear Experimental Reactor).

• OSTI ID: 5067355
• Report Number(s): CONF-910920--
• Conference Information: Journal Name: Fusion Technology; (United States) Journal Volume: 21:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700460* -- Fusion Technology-- Heating & Fueling Systems
CATALYSIS
CHEMICAL REACTIONS
CLOSED PLASMA DEVICES
DESIGN
DEUTERATION
ELECTROLYSIS
EXPERIMENT PLANNING
FUELS
Fu
Fuels-- (1992)
HYDROGEN COMPOUNDS
IMPURITIES
ISOTOPIC EXCHANGE
ITER TOKAMAK
LYSIS
NUCLEAR REACTIONS
NUCLEOSYNTHESIS
OXIDATION
PLANNING
SYNTHESIS
TEMPERATURE DEPENDENCE
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTIONS
TOKAMAK DEVICES
TRITIUM COMPOUNDS
TRITIUM RECOVERY