Articolo in rivista, 2022, ENG, 10.1016/j.fusengdes.2022.113122

Development of a concept and basis for the DEMO diagnostic and control system

Biel W.; Ariola M.; Bolshakova I.; Brunner K.J.; Cecconello M.; Duran I.; Franke Th.; Giacomelli L.; Giannone L.; Janky F.; Krimmer A.; Luis R.; Malaquias A.; Marchiori G.; Marchuk O.; Mazon D.; Pironti A.; Quercia A.; Rispoli N.; El Shawish S.; Siccinio M.; Silva A.; Sozzi C.; Tartaglione G.; Todd T.; Treutterer W.; Zohm H.

Institut fur Energie- und Klimaforschung, Forschungszentrum Julich GmbH, Germany; Department of Applied Physics, Ghent University, Belgium; Universita' di Napoli Parthenope, Consorzio CREATE, Italy; Magnetic sensor laboratory, Lviv, Ukraine; Max-Planck-Institut fur Plasmaphysik, Greifswald, Germany; Department of Physics and Astronomy, Uppsala University, Sweden; Institute of Plasma Physics, Czech Academy of Science, Praha, Czech Republic; Max-Planck-Institut fur Plasmaphysik, Garching, Germany; EUROfusion Power Plant Physics and Technology (PPPT) Department, Garching, Germany; ISTP-CNR, Istituto per la Scienza e Tecnologia dei Plasmi, Milano, Italy; Instituto de Plasmas e Fusao Nuclear, IST, Universidade de Lisboa, Portugal; Consorzio RFX (CNR, ENEA, INFN, Università di Padova), Padova, Italy; CNR ISTP - Istituto per la Scienza e Tecnologia dei Plasmi, Sede di Padova, Italy; CEA, IRFM, Saint Paul-lez-Durance, France; Università degli Studi di Napoli Federico II, Consorzio CREATE, Italy; Jozef Stefan Institute, Ljubljana, Slovenia.

An initial concept for the plasma diagnostic and control (D&C) system has been developed as part of European studies towards the development of a demonstration tokamak fusion reactor (DEMO). The main objective is to develop a feasible, integrated concept design of the DEMO D&C system that can provide reliable plasma control and high performance (electricity output) over extended periods of operation. While the fusion power is maximized when operating near to the operational limits of the tokamak, the reliability of operation typically improves when choosing parameters significantly distant from these limits. In addition to these conflicting requirements, the D&C development has to cope with strong adverse effects acting on all in vessel components on DEMO (harsh neutron environment, particle fluxes, temperatures, electromagnetic forces, etc.). Moreover, space allocation and plasma access are constrained by the needs for first wall integrity and optimization of tritium breeding. Taking into account these boundary conditions, the main DEMO plasma control issues have been formulated, and a list of diagnostic systems and channels needed for plasma control has been developed, which were selected for their robustness and the required coverage of control issues. For a validation and refinement of this concept, simulation tools are being refined and applied for equilibrium, kinetic and mode control studies.

Fusion engineering and design (Print) 179 , pp. 113122-1–113122-21

Keywords

DEMO, Tokamak, Plasma diagnostics, Plasma control

CNR authors

Sozzi Carlo, Rispoli Natale, Marchiori Giuseppe

CNR institutes

ISTP – Istituto per la Scienza e Tecnologia dei Plasmi

ID: 466499

Year: 2022

Type: Articolo in rivista

Creation: 2022-04-22 12:39:44.000

Last update: 2024-01-09 07:26:06.000

External IDs

CNR OAI-PMH: oai:it.cnr:prodotti:466499

DOI: 10.1016/j.fusengdes.2022.113122

Scopus: 2-s2.0-85127747568

ISI Web of Science (WOS): 000793698700005