Abstract
JET is the world's largest tokamak and has operated with tritium plasma. In the Deuterium-Tritium Experiment (DTE1) about 30% of tritium fed to the tokamak was retained in the vessel and in-vessel components. It is expected that in a several years time JET will cease experimental operations and enter a decommissioning phase. In situ detritiation of the vacuum vessel is likely to be needed prior to its dismantling. To reduce cost of subsequent storage and disposal, post-dismantling detritiation of components and waste will be needed. The United Kingdom Atomic Energy Authority, which operates the JET machine, has been carrying out studies of various detritiation techniques in order to select and experimentally prove technologies for in situ and ex situ detritiation of potential waste. This paper summarises the results.
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