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Articolo in rivista, 2021, ENG, 10.1088/1741-4326/abfe76

Summary of the IAEA technical meeting on plasma disruptions and their mitigation

Bandyopadhyay I.; Barbarino M.; Bhattacharjee A.; Eidietis N.; Huber A.; Isayama A.; Kim J.; Konovalov S.; Lehnen M.; Nardon E.; Pautasso G.; Rea C.; Sozzi C.; Villone F.; Zeng L.

ITER India, Inst Plasma Res, Gandhinagar, Gujarat, India; IAEA, Vienna Int Ctr, Vienna, Austria; Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ USA; Gen Atom, San Diego, CA USA; Forschungszentrum Julich GmbH, Inst Energie & Klimaforsch Plasmaphys, Julich, Germany; Natl Inst Quantum & Radiol Sci & Technol, Naka, Ibaraki, Japan; Korea Inst Fus Energy KFE, Daejeon, South Korea; Natl Res Ctr, Kurchatov Inst, Moscow, Russia; ITER Org, St Paul Les Durance, France; CEA, IRFM, St Paul Les Durance, France; Max Planck Inst Plasma Phys, Garching, Germany; MIT, Plasma Sci & Fus Ctr, Cambridge, MA USA; CNR, Ist Sci & Tecnol Plasmi, Milan, Italy; Univ Napoli Federico II, Consorzio CREATE, DIETI, Naples, Italy; Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China.

This report summarizes the contributions presented at the IAEA technical meeting on plasma disruptions and their mitigation, held virtually, 20-23 July 2020. The meeting brought together more than 120 experts from nuclear fusion research sites worldwide to discuss experimental, theoretical and modelling work in the field of plasma disruptions with special emphasis on developing a solid basis for possible disruption mitigation strategies in ITER and next generation fusion devices. The main topics of the meeting were: (i) disruption consequences, including electromagnetic loads, heat loads, and runaway electrons; (ii) disruption prediction and avoidance, including machine learning and physics-based approaches, and control aspects; and (iii) disruption mitigation, including shattered pellet injection, alternative techniques and general aspects of disruption mitigation.

Nuclear fusion 61 (7), pp. 077001-1–077001-13