Articolo in rivista, 2022, ENG, 10.1016/j.fusengdes.2022.113122
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
DEMO, Tokamak, Plasma diagnostics, Plasma control
Sozzi Carlo, Rispoli Natale, Marchiori Giuseppe
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
CNR authors
CNR institutes
External links
OAI-PMH: Dublin Core
OAI-PMH: Mods
OAI-PMH: RDF
DOI: 10.1016/j.fusengdes.2022.113122
URL: https://www.sciencedirect.com/science/article/pii/S0920379622001223
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