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CD-II - The Fuel Cycle of Fusion Power Plants and
Experimental Fusion Reactors
I.R. Cristescu, M. Glugla, A. Antipenkov, S. Beloglazov, C. Caldwell-Nichols,
I. Cristescu, C. Day, D. Demange, A. Mack
Forschungszentrum Karlsruhe, Tritium Laboratory, PO Box 3640, 76021 Karlsruhe, Germany
Abstract: The tritium fusion fuel cycle has to be based upon well proven technology to assure the safe handling of tritium along with credible accountancy, low tritium inventory, low generation of wastes and a high reliability of all components throughout the lifetime of the reactor. A coherent understanding of all the equipment and process details covering conceptual studies to technical scale experiments together with mathematical modeling is therefore indispensable. Corresponding research is therefore on-going in various laboratories around the world. The cryo-pumping systems for Torus exhaust and neutral beam injectors have been tested to confirm fast regeneration scenarios and to reduce the accumulation of semi-permanent inventories of tritiated impurities. A comprehensive program to test the integrated three step (permeation, chemical impurity processing and isotopic exchange) process for Torus Exhaust Processing was carried out in the last decade. An integrated concept for the Isotope Separation (ISS) and Water Detritiation systems (WDS) has been developed and is under investigation on relevant scale. A fast delivery, self-assay storage bed has been developed and is under testing.
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Synopsis (pdf)