Abstract:Fast and efficient tritium removal is needed for future DT machines with carbon plasma facing components. A novel method for tritium release has been demonstrated on codeposited layers on tiles retrieved from the Tokamak Fusion Test Reactor (TFTR) and from the Joint European Torus (JET). A scanning continuous wave Nd laser beam was focused to ≈ 100 W/mm 2 and scanned at high speed over the codeposits, heating them to temperatures ≈ 2000 °C for about 10 ms in either air or argon atmospheres. Fiber optic coupling between the laser and scanner was implemented. Up to 87% of the codeposited tritium was thermally desorbed from the JET and TFTR samples. This technique appears to be a promising in-situ method for tritium removal in a next step DT device as it avoids oxidation, the associated deconditioning of the plasma facing surfaces and the expense of processing large quantities of tritium oxide.
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