Preliminary conceptual design of DEMO EC system

Garavaglia, S.; Bin, W.; Bruschi, A.; Granucci, G.; Grossetti, G.; Jelonnek, John; Moro, A.; Rispoli, N.; Strauß, D.; Tran, Quang D.; Franke, T.

doi:10.1063/1.4936546

Cited by 10 publications

(5 citation statements)

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“…One of the most important activities performed with METIS has been the assessment in terms of performance, calcul ation of density, temperature and toroidal velocity profiles or magnetic characteristics of tokamak devices which recently started operation, such as WEST [52,53] or will do it in the future as JT-60SA [54], ITER [55][56][57] or DEMO [58][59][60][61].…”

Section: Some Applications Of Metismentioning

confidence: 99%

Metis: a fast integrated tokamak modelling tool for scenario design

et al. 2018

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METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It combines 0-D scaling-law normalised heat and particle transport with 1-D current diffusion modelling and 2-D equilibria. It contains several heat, particle and impurities transport models, as well as heat, particle, current and momentum sources, which allow faster than real time scenario simulations. This paper gives a first comprehensive description of the METIS suite: overall structure of the code, main available models, details on the simulation workflow and numerical implementation. Some examples of applications to the analysis of experimental discharges and the predictions of ITER scenarios are also given.

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Section: Some Applications Of Metismentioning

confidence: 99%

Metis: a fast integrated tokamak modelling tool for scenario design

et al. 2018

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“…A number of physics studies (not discussed here) were conducted together with conceptual layout studies [21], [22]. Also different options for the configurations were investigated [23]. The EC physics functions to be fulfilled for DEMO and investigated so far are on the EC plasma breakdown, EC current drive, L-H heating, ramp-up anddown assistance, neo-classical tearing mode (NTM) and sawtooth (ST) control and control of radiative instabilities.…”

Section: Electron Cyclotron (Ec) Configurations Formentioning

confidence: 99%

Review of the Innovative H&CD Designs and the Impact of Their Configurations on the Performance of the EU DEMO Fusion Power Plant Reactor

Franke

Agostinetti

Aiello

et al. 2018

IEEE Trans. Plasma Sci.

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Heating & Current Drive (H&CD) systems are being investigated for a demonstration fusion power plant DEMO to deliver net electricity for the grid around 2050 [1],[2]. Compared to ITER, which has to show the generation of 500 MW thermal power, the target of DEMO is the successful production of 300 to 500 MW electrical power to the grid and to aim for a self-sufficient Tritium fuel cycle [3]. Three H&CD systems are under development for DEMO in Europe, the Electron Cyclotron (EC) System, the Neutral Beam Injection (NBI) System and the Ion Cyclotron (IC) System. Based on present studies [4] for plasma ramp-up, rampdown and flat top phases, to be further validated in more detailed simulations, the assumed total launched power needed from the H&CD system in DEMO is in the range of 50-100 MW, to be provided for plasma heating and control. The paper describes the designs and R&D status of selected H&CD systems considered for their deployment in the EU DEMO. It was always considered that different H&CD Manuscript submitted on 28 th June 2016. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The reviews and opinions expressed herein do not necessarily reflect those of the European Commission.

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“…launcher radius, launcher cut length, and Brillouin angle) at different frequencies. Based on this study, the selected operating frequencies and their corresponding applications for different aspect ratios of DEMO [11][12] are listed in Table 2 along with the selected modes for the multi-frequency operation. Initially, the operating modes for 170 GHz and 203 GHz were suggested and successfully tested by the JAEA gyrotron team [20].…”

Section: Mode Selection Considering Multi-frequency Multi-purpose Opmentioning

confidence: 99%

“…It is beneficial to use the same gyrotron as a multi-purpose tube in a fusion facility, with respect to the various operational stages, which require different microwave frequencies (e. g. plasma start-up, non-inductive current drive, and bulk heating). Furthermore, the same operational stage in facilities with different torus aspect ratios would require different microwave frequencies, as indicated in [10][11][12]. It is understood that the above mentioned requirements can be fulfilled by a proper "multi-frequency" gyrotron design.…”

Section: Introductionmentioning

confidence: 99%