Initial port integration concept for EC and NB systems in EU DEMO tokamak

Franke, Thomas; Agostinetti, Piero; Bachmann, Christian; Bruschi, A.; Carr, M.; Cismondi, F.; Čufar, Aljaž; Esch, H.P.L. de; Federici, G.; Harder, N. den; Garavaglia, S.; Grossetti, G.; Granucci, G.; Meakins, A.; Moro, A.; Mozzillo, Rocco; Sartori, E.; Siccinio, M.; Sonato, P.; Strauß, D.; Tran, M.Q.; Valentine, A.; Zheng, S.

doi:10.1016/j.fusengdes.2019.03.007

Cited by 16 publications

(15 citation statements)

References 26 publications

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“…The required beam radius at the mirror location is w = 125 mm, while the beam radius footprint elongation (in the incidence plane) on the launching mirror is 125 mm/cosq where q is the incidence angle. The required deposition in [7] is Drt = 0.01 while the obtained deposition is Drt = 0.0075. The CD efficiency is poor due to the small toroidal angle (16.5°) and to the local low temperature, but a larger beta angle would increase the deposition width.…”

Section: Front Steering Antennamentioning

confidence: 99%

“…The present unfeasibility of RSA for NTM required a study on the minimum dimensions for a front steering mirror placed behind the blanket shield module and capable to focus the EC wave enough to drive current inside the NTM island to be stabilized, according with [7]. For the calculation we selected a frequency of 170 GHz and a suitable toroidal injection angle of 16.5°.…”

Section: Front Steering Antennamentioning

confidence: 99%

“…The EC power required for NTM control is 30 MW, 15 MW for each main instability located at q = 2 (rt @ 0.77) and q = 3/2 (rt @ 0.64) rational surfaces, in addition to the 50 MW. For this specific task the driven current required to stabilize the (2,1) mode is @ 180 kA [6] together with strong localization of the deposition profile (full width at 1/e of the power density of about 6 cm [7]) and the capability to be steered around the required position. For more information about the power requirements versus functions during the different plasma phases for DEMO see [7].…”

Section: Introductionmentioning

confidence: 99%

“…For this specific task the driven current required to stabilize the (2,1) mode is @ 180 kA [6] together with strong localization of the deposition profile (full width at 1/e of the power density of about 6 cm [7]) and the capability to be steered around the required position. For more information about the power requirements versus functions during the different plasma phases for DEMO see [7]. Although before the ST/NTM control was assumed to be alternating for localized ECCD, the same power level is still required, but only for NTM control.…”

Section: Introductionmentioning

confidence: 99%

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EU DEMO EC equatorial launcher pre-conceptual performance studies

Garavaglia

Baiocchi

Bruschi

et al. 2020

Fusion Engineering and Design

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The preliminary conceptual design for the Electron Cyclotron (EC) system of the future European DEMOnstration fusion power plant is ongoing in the EUROfusion Consortium. This represents one of the key aspects in order to assess the performances and the integration capabilities of such a system in EU DEMO as well as in the alternative reactor configuration Flexi-DEMO. Different options for the antenna, namely remote steering antenna (RSA), open ended waveguides (OEWG) and the front steering antenna (FSA) later on renamed in mid steering antenna (MSA) to notify that the MSA is protected behind the breeding blanket (BB) in DEMO, are investigated, analyzing their performance for several injection angles and launch points. This activity considers the constraints given by physics and engineering requirements, as for example the maximum power per port and the necessary local current drive to stabilize neo-classical tearing modes (NTMs) with a proper deposition width. The beam tracing calculations have been performed on different scenarios, providing information on plasma accessibility and deposited power. The microwave design and initial ideas about the ex-vessel EC transmission lines routing will be shown.

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Section: Front Steering Antennamentioning

confidence: 99%

Section: Front Steering Antennamentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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EU DEMO EC equatorial launcher pre-conceptual performance studies

Garavaglia

Baiocchi

Bruschi

et al. 2020

Fusion Engineering and Design

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“…In support of the integration of EC heating system [1] neutronic simulations were performed to check the design requirements are met and to trigger potential design optimizations. In this process the reduction in the T breeding performance of the breeding blanket as well as shielding performance of the design was assessed.…”

Section: Introductionmentioning

confidence: 99%

Equatorial electron cyclotron port plug neutronic analyses for the EU DEMO

Čufar

Bruschi

Fischer

et al. 2019

Fusion Engineering and Design

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Within the Power Plant Physics and Technology (PPPT) programme in the EUROfusion Consortium design activities are currently in progress for the development of a DEMOnstration Fusion Power Plant (DEMO). The design of the machine and the integration of in-vessel components require neutronics analyses to verify the tritium selfsufficiency, the shielding requirements, and the structural integrity of its components. In particular, the effect of penetrations in the blanket and in equatorial port plug introduced by the electron cyclotron (EC) heating system, namely due to openings for the antenna waveguides (WGs), were analyzed. In this study three-dimensional MCNP calculations were conducted for the pre-conceptual designs of the EC port plugs and shielding optimization were performed in order to ensure that the DEMO design limits are not exceeded. Two configurations of the EC heating system were performed using a DEMO Water Cooled Lithium Lead (WCLL) with integrated EC configurations model of a half of the sector (i.e. 10° model) and relevant ones repeated with a full sector model (i.e. 20° model) to test the reliability of results. Additionally, the effect of the radiation on the WGs closest to the plasma was analyzed as well as the impact on Tritium Breeding Ratio (TBR).

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