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Experimental Demonstration of the HITEX Process for Fusion Fuel Clean-Up

Joan M. Miller, Lakshman Rodrigo, Joseph A. Senohrabek

Fusion Science and Technology / Volume 28 / Number 3P1 / October 1995 / Pages 700-704

Tritium Processing / Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 / dx.doi.org/10.13182/FST95-A30486

The HITEX (High Temperature Isotopic Exchange) process has been proposed as a simple, reliable process to detritiate impurities in the International Thermonuclear Experimental Reactor (ITER) exhaust flow. Experimental testing of the HITEX process has demonstrated decontamination factors of up to ∼106 for a tritiated-methane impurity stream. Initial results investigating the effect of the hydrogen swamping ratio, gas recirculation rate, gas composition and initial tritium level on the system performance are reported.