SMuK 2023 – wissenschaftliches Programm

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P: Fachverband Plasmaphysik

P 16: Plasma Wall Interaction II/Codes and Modeling I

P 16.1: Hauptvortrag

Donnerstag, 23. März 2023, 14:00–14:30, CHE/0091

Development of a Laser-based Diagnostic for in situ Monitoring of Fuel Retention in ITER and future fusion devices — •Alexander Huber, M. Zlobinski, G. Sergienko, J. Assmann, D. Castano, S. Friese, I. Ivashov, Y. Krasikov, H. Lambertz, Ph. Mertens, K. Mlynczak, M. Schrader, A. Terra, S. Brezinsek, and Ch. Linsmeier — Institut für Energie- und Klimaforschung - Plasmaphysik, Forschungszentrum Jülich GmbH, Jülich

One of the most serious challenges for the operation of ITER and future fusion devices is the control of the inventory of tritium stored in the vessel walls which surround the plasma. For the operation of ITER and of a fusion reactor in general, the determination of the tritium inventory and the knowledge of its spatial distribution is essential. Its control without removal of wall tiles is also of paramount importance. A laser-based T-monitor diagnostic system is under development at Forschungszentrum Jülich (FZJ) to remotely provide information about the tritium content in the deposited layer on the inner divertor tiles of ITER. The T-inventory builds up through the interaction of wall erosion and co-deposition of hydrogen isotopes together with redeposited material. The limitation of the tritium content in the reactor is of course a safety requirement for the operation. The measurement concept is based on laser-induced desorption (LID) and detection of the released gases by Residual Gas Analysis (RGA).

The present contribution summarizes the results of an R&D programme on the LID method carried out at FZJ for the integration of this laser-based tool into ITER and future reactors.