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

Franke, Thomas; Agostinetti, Piero; Aiello, G.; Avramidis, Konstantinos A.; Bachmann, C.; Bruschi, A.; Federici, G.; Garavaglia, S.; Granucci, G.; Grossetti, G.; Jelonnek, John; Noterdaeme, Jean-Marie; Simonin, A.; Scherer, T.; Sonato, P.; Strauß, D.; Tran, M.Q.; Valentine, A.; Vincenzi, P.; Wenninger, R.; Zheng, S.

doi:10.1109/tps.2018.2800405

Cited by 11 publications

(7 citation statements)

References 33 publications

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“…The realization of the world's first 1 MeV negative-ion-based injector requires the development of a system prototype, which is currently ongoing [10]. Due to its reliability and the availability of long-term operational experience, NBI is one of the H&CD systems currently being considered to provide auxiliary power to the EU DEMO plasma [11,12]. This work focuses on the study of NBI for the DEMO1 plasma.…”

Section: Introductionmentioning

confidence: 99%

Optimization-oriented modelling of neutral beam injection for EU pulsed DEMO

Vincenzi¹,

Agostinetti²,

Artaud³

et al. 2021

Plasma Phys. Control. Fusion

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Neutral beam injection (NBI) is one of the auxiliary power systems considered for the EU DEMO pulsed plasma ('DEMO1'). In this paper, we discuss the characteristics of optimized NBI in terms of the DEMO1 requirements, relating physics and engineering contexts in a novel parameter range compared to current NBI systems and in a larger plasma volume than ITER. Different injection options are investigated to account for various concepts discussed in the literature. The investigation is carried out using a wide range of sensitivity studies by means of the METIS 0.5D transport code and ASCOT Monte Carlo simulations of injected neutral-beam particles. This investigation has generated a series of recommendations for the NBI design, contributing to the system optimization process. We show how tangential injection aimed at the plasma core, with an energy ≳800 keV, is recommended to maintain high fusion power performance and fulfill the requirements for bulk heating. Compliance with engineering constraints on the NBI design, e.g., the least interference with breeding blanket modules or compatibility with solutions for the beamline components, imposes some restrictions when discussing the beam geometry. The minimum density at which an NBI can be safely operated without harmful shine-through losses is investigated for different injection energies and compared to the ITER case. The NBI operational window for DEMO is shown to be significantly extended to transient, low-density phases, also highlighting the importance of NBI systems designed for modular energy and power output. NBI can therefore sustain the plasma during a considerable portion of the transient phases, i.e., the current ramp-up and ramp-down phases. The final decision on the DEMO heating mix will be made on the basis of system operability and performance: the optimized NBI is shown to be a suitable and effective option for the EU DEMO inductive scenario.

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Section: Introductionmentioning

confidence: 99%

Optimization-oriented modelling of neutral beam injection for EU pulsed DEMO

Vincenzi¹,

Agostinetti²,

Artaud³

et al. 2021

Plasma Phys. Control. Fusion

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“…To reduce the antenna power density and the associated high voltage in low coupling conditions, TWA antennas distributed around the periphery of the tokamak are presently considered for the DEMO reactor [5,6]. A TWA section consists of an array of parallel grounded straps, each terminated by a self-integrated tuning reactance.…”

Section: A Traveling Wave Array Antenna (Twa)mentioning

confidence: 99%

A travelling wave array system as solution for the ion cyclotron resonance frequencies heating of DEMO

Ragona¹,

Messiaen²,

Ongena³

et al. 2019

Nucl. Fusion

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Travelling Wave Array (TWA) antennas distributed along the periphery of the tokamak are presently considered as Ion Cyclotron Resonance Frequencies (ICRF) heating solution for the DEMO reactor. Compared to the conventional ICRF antenna systems currently in use or designed for future machines like ITER, the TWA consists of antenna sections integrated in the breeding blanket scattered around the machine, each one fed through a variable coupler in a resonant ring configuration. Previous modelling of an antenna system for DEMO with 16 quadruple TWA sections of 8 straps shows that a power capability exceeding 50 MW can be obtained in the frequency band of interest using the reference low coupling plasma profile of ITER. The described system optimizes the coupling to the plasma by providing a large number of radiating elements, which results in enhanced antenna directivity hereby decreasing the antenna power density. This results in a maximum strap voltage amplitude of only 15 kV and maximum inter-strap voltage amplitude of 18 kV. The generators remain matched for all loading conditions: the system is totally load resilient. Following the recommendation of the work package heating and current drive (WPHCD) Review Panel, a TWA ICRH system consisting in fewer sections concentrated in front of the equatorial ports is analysed in this paper and compared to the previous design. Reducing the number of sections increases the power density and its associated voltages. To couple 50 MW on the ITER density profile, voltages up to 30 kV are now required. Some aspects like the coupling between sections and its repercussion on the feeding network are briefly discussed. To assess the feasibility of the TWA fed by a resonant ring as ICRH system for a DEMO reactor, a test on an existing medium size tokamak is under study.

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“…Within the Work Package Heating and Current Drive (WPHCD), coordinated by the Power Plant Physics and Technology Department of EUROfusion, extensive studies are ongoing, which cover three different systems for plasma heating and current drive. These are, namely, systems using electron cyclotron waves, ion cyclotron waves, and neutral beam injection [1]- [2]. The studies are in line with the European Fusion Roadmap towards a demonstration power plant (DEMO).…”

Section: Introductionmentioning

confidence: 98%