Conceptual Design of Tritium Extraction System

The first generation of fusion reactors will use deuterium and tritium as fuel. Since tritium is not available in nature, it must be produced in the fusion reactor blanket which surrounds the plasma zone. Tritium extraction facility has been designed and fabricated. Calibration procedure has been performed to determine tritium losses, if any during the extraction. Lithium compounds were irradiated using Am-Be neutron source. Out of pile extraction from neutron irradiated lithium compounds was carried out by flushing the samples with helium plus 0.1 % hydrogen as a carrier gas in the temperature range 450°C to 900°C. Tritium losses will have been estimated. Extracted tritium activity will be measured by commercially available liquid scintillation counter.