The feasibility of laser-induced breakdown spectroscopy (LIBS) for measuring fuel retention was demonstrated for the first time in a tokamak operating with tritiumusing a remotely controlled in-situ application in JET. In JET as well as in future fusion reactors such as ITER and DEMO, thick co-deposited layers will be formed onthe inner wall during extended plasma operations. Experiments in present-day fusion devices indicate that these layers consist of eroded plasma-facing materials,various impurities and plasma fuel species such as deuterium and tritium. Accumulation of radioactive tritium in the reactor vacuum vessel is a particularly criticalsafety issue requiring active monitoring. LIBS is one of the few techniques available for monitoring the tritium content and the composition of co-deposited layersduring maintenance breaks. This paper will provide an overview of the LIBS experiment that was performed post DTE3 campaign, and D and H cleanup at JET inOctober 2024. 840 different spatial locations on the main wall and divertor area were investigated, with measurements of more than 100 laser pulses per locationexecuted to ensure good depth resolution.
Likonen et al. (Wed,) studied this question.
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