Heating and current drive systems such as high energy Neutral Beam Injection (NBI) are being considered for pulsed EU DEMO ("DEMO1") pre-conceptual design. Their aim is to provide auxiliary power, not only during flat-top, but also during transient phases (i.e. plasma current ramp-up and ramp-down). In this work, NBI fast particle power loads on DEMO1 first wall, due to shine-through and orbit losses, are calculated for the diverted plasma ramp-up phase. Numerical simulations are performed using BBNBI and ASCOT Monte Carlo codes. The simulations have been done using a complete 3D wall geometry, and implementing the latest DEMO NBI design, which foresees NBI at 800 keV particle energy. Location and power density of NBI-related power loads at different ramp-up time steps are evaluated and compared with the maximum tolerable heat flux taken from ITER case. Since NBI shine-through losses (dominant during low density phases) depend mainly on the beam energy, plasma density and volume, DEMO has a more favourable situation than ITER, enlarging NBI operational window. Using ITER criteria, DEMO NBI at full energy and power could be switched on during ramp-up at <ne> ~ 1.3 × 1019 m-3. This increases the appeal of neutral beam injectors as auxiliary power systems for DEMO.

Estimate of 3D power wall loads due to Neutral Beam Injection in EU DEMO ramp-up phase

Vincenzi P;Agostinetti P;
2019

Abstract

Heating and current drive systems such as high energy Neutral Beam Injection (NBI) are being considered for pulsed EU DEMO ("DEMO1") pre-conceptual design. Their aim is to provide auxiliary power, not only during flat-top, but also during transient phases (i.e. plasma current ramp-up and ramp-down). In this work, NBI fast particle power loads on DEMO1 first wall, due to shine-through and orbit losses, are calculated for the diverted plasma ramp-up phase. Numerical simulations are performed using BBNBI and ASCOT Monte Carlo codes. The simulations have been done using a complete 3D wall geometry, and implementing the latest DEMO NBI design, which foresees NBI at 800 keV particle energy. Location and power density of NBI-related power loads at different ramp-up time steps are evaluated and compared with the maximum tolerable heat flux taken from ITER case. Since NBI shine-through losses (dominant during low density phases) depend mainly on the beam energy, plasma density and volume, DEMO has a more favourable situation than ITER, enlarging NBI operational window. Using ITER criteria, DEMO NBI at full energy and power could be switched on during ramp-up at ~ 1.3 × 1019 m-3. This increases the appeal of neutral beam injectors as auxiliary power systems for DEMO.
2019
Istituto gas ionizzati - IGI - Sede Padova
Inglese
18
188
192
5
https://www.sciencedirect.com/science/article/pii/S2352179118300991
Sì, ma tipo non specificato
Conceptual design
Heat flux
Monte Carlo methods
Particle beams
Plasma density
Tokamak devices
Current drive system
High-energy neutrals
Monte Carlo codes
Neutral beam injection
Neutral beam injectors
Operational windows
Plasma current ramps
Transient phasis
Particle beam injection
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 number 633053. This work has been supported by a EUROfusion Engineering Grant. / https://www.scopus.com/inward/record.uri?eid=2-s2.0-85059203278&doi=10.1016%2fj.nme.2018.12.031&partnerID=40&md5=4593d7a60ca02cb8548883ca916a99f4
1
info:eu-repo/semantics/article
262
Vincenzi, P.; Varje, J.; Agostinetti, P.; Artaud, J.F.; Bolzonella, T.; KurkiSuonio, T.; Mattei, M.; Sonato, P.; Vallar, M.
01 Contributo su Rivista::01.01 Articolo in rivista
none
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/343441
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