Transfers of tritium in regeneration/recovery systems hold (ITER) for the experimental demonstration of self-sufficiency fuel in Nuclear Fusion

A tritium self-sufficiency assessment is performed for pulsed tritium breeding and recovery systems in ITER under a DCLL configuration scaling-down parameters to ITER of Spanish DCLL DEMO auxiliaries configuration showing how self-sufficiency scenarios can be strongly justified for DCLL designs. It is not the case in other options in development.