EU DEMO EC system preliminary conceptual design

Garavaglia, S.; Aiello, G.; Alberti, S.; Avramidis, Konstantinos A.; Bruschi, A.; Chelis, Ioannis; Franck, J.; Gantenbein, G.; Granucci, G.; Grossetti, G.; Hizanidis, Kyriakos; Illy, S.; Jelonnek, John; Kalaria, P.; Latsas, George P.; Moro, A.; Pagonakis, I.; Peponis, Dimitrios V.; Poli, E.; Rispoli, N.; Ruess, S.; Rzesnicki, T.; Scherer, T.; Strauß, D.; Thumm, M.; Tigelis, I. G.; Tsironis, C.; Wu, Chuanren; Franke, Thomas; Tran, M.Q.

doi:10.1016/j.fusengdes.2018.04.097

Cited by 23 publications

(11 citation statements)

References 25 publications

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“…These are, namely, systems using electron cyclotron waves, ion cyclotron waves, and neutral beam injection. The studies are in line with the European Fusion Roadmap towards a DEMO [13,111]. Following the development of 1 MW, CW 140 GHz and 170 GHz gyrotrons for the W7-X stellarator and the ITER tokamak, respectively, the conceptual designs of tubes with frequencies up to approximately GHz were perfomed at KIT-IHM [112][113][114][115][116][117].…”

Section: Eu Developments For Future Demo Gyrotronsmentioning

confidence: 76%

High-power gyrotrons for electron cyclotron heating and current drive

Thumm¹,

Денисов²,

Sakamoto³

et al. 2019

Nucl. Fusion

127

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In many tokamak and stellarator experiments around the globe that are investigating energy production via controlled thermonuclear fusion, electron cyclotron heating and current drive (ECH&CD) are used for plasma start-up, heating, non-inductive current drive and MHD stability control. ECH will be the first auxiliary heating method used on ITER. Megawatt-class, continuous wave (CW) gyrotrons are employed as high-power millimeter (mm)-wave sources. The present review reports on the worldwide state-of-the-art of high-power gyrotrons. Their successful development during the past years changed ECH from a minor to a major heating method. After a general introduction of the various functions of ECH&CD in fusion physics, especially for ITER, Section 2 will explain the fast-wave gyrotron interaction principle. Section 3 discusses innovations on the components of modern long-pulse fusion gyrotrons (magnetron injection electron gun (MIG), beam tunnel, cavity, quasi-optical output coupler, synthetic diamond output window, single-stage depressed collector) and auxiliary components (superconducting magnets, gyrotron diagnostics, high-power calorimetric dummy loads). Section 4 deals with present megawatt-class gyrotrons for ITER, W7-X, LHD, EAST, KSTAR and JT-60SA, and also includes tubes for moderate pulse length machines as, ASDEX-U, DIII-D, HL-2A, TCV, QUEST and GAMMA-10. In Section 5 the development of future advanced fusion gyrotrons is discussed. These are tubes with higher frequencies for DEMO, multi-frequency (multi-purpose) gyrotrons, stepwise frequency tunable tubes for plasma stabilization, injection-locked and coaxial-cavity multi-megawatt gyrotrons, as well as sub-THz gyrotrons for collective Thomson scattering (CTS). Efficiency enhancement via multi-stage depressed collectors, fast oscillation recovery methods and reliability, availability, maintainability and inspectability (RAMI) will be discussed at the end of this section.

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Section: Eu Developments For Future Demo Gyrotronsmentioning

confidence: 76%

High-power gyrotrons for electron cyclotron heating and current drive

Thumm¹,

Денисов²,

Sakamoto³

et al. 2019

Nucl. Fusion

127

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“… Gyrotron requirements (G = Gauss) [24]- [26]: B R < 2 G (radial), B Z < 5 G (axial), up to 10 G (still acceptable, to be confirmed)  Torus-Gyrotron distance as simulated (see Fig. 11…”

Section: A Ec Plant Layoutmentioning

confidence: 87%

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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“…The work breakdown structure of WPHCD, launched in 2014, includes branches dedicated to the conceptual design of the electron cyclotron wave system [5], as well to R&D focused mainly on the microwave source, the gyrotron [6]. Gyrotron R&D is a necessary step to bridge the gap between today's state-of-the-art gyrotrons and future gyrotrons for DEMO.…”

Section: Introductionmentioning

confidence: 99%