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

0557628 - ÚFP 2023 RIV CH eng J - Článek v odborném periodiku
Biel, W. - Ariola, M. - Bolshakova, I. - Brunner, K. - Cecconello, M. - Ďuran, Ivan - Franke, T. - 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.
Development of a concept and basis for the DEMO diagnostic and control system.
Fusion Engineering and Design. Roč. 179, June (2022), č. článku 113122. ISSN 0920-3796. E-ISSN 1873-7196
GRANT EU: European Commission(XE) 633053 - EUROfusion
Institucionální podpora: RVO:61389021
Klíčová slova: research-and-development * alcator c-mod * hall sensors * density-measurements * iter diagnostics * magnetic control * burn control * design * plasma * spectroscopy * demo * Tokamak * Plasma diagnostics * Plasma control
Obor OECD: Fluids and plasma physics (including surface physics)
Impakt faktor: 1.7, rok: 2022
Způsob publikování: Open access
https://www.sciencedirect.com/science/article/pii/S0920379622001223?via%3Dihub

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.
Trvalý link: https://hdl.handle.net/11104/0341112