The current European DEMO design, with a fusion power of 1.8 GW and up to 51 MW of external NBI heating, will produce copious amounts of energetic particles both in 3.5 MeV fusion-born alphas as well as 800 keV NBI ions. Good confinement of these particles is necessary not only for efficient heating and current drive, but also for machine protection. Losses introduced by the toroidal ripple can result in localized heat loads on the first wall, the design of which is already constrained by the requirements for tritium breeding and power plant operation [1]. To study the 3D effects of the toroidal ripple on fast particles, a high-resolution vacuum magnetic field was constructed from realistic coil geometry. Additionally, the ripple-mitigating effect of ferritic inserts was included by modelling the perturbations using the finite element solver COMSOL, previously applied to similar studies for ITER [2]. Fast ion confinement and losses were simulated using the Monte Carlo orbit following code ASCOT both for thermonuclear alpha particles as well as NBI ions, for which an injector model was developed based on the latest DEMO reference design [3]. The fast ion confinement in the European DEMO design was found to be good, with alpha power losses remaining below 500 kW and wall loads below 100 kW/m2 in all cases. The ferritic inserts effectively mitigated the toroidal ripple, reducing the losses nearly to the level of an axisymmetric field. Finally, the confinement of the NBI particles was found to be excellent, with losses remaining below 0.1 %, resulting in minimal deterioration in power deposition and current drive.

Effect of 3D magnetic perturbations on fast ion confinement in the European DEMO

Agostinetti P;Vincenzi P
2017

Abstract

The current European DEMO design, with a fusion power of 1.8 GW and up to 51 MW of external NBI heating, will produce copious amounts of energetic particles both in 3.5 MeV fusion-born alphas as well as 800 keV NBI ions. Good confinement of these particles is necessary not only for efficient heating and current drive, but also for machine protection. Losses introduced by the toroidal ripple can result in localized heat loads on the first wall, the design of which is already constrained by the requirements for tritium breeding and power plant operation [1]. To study the 3D effects of the toroidal ripple on fast particles, a high-resolution vacuum magnetic field was constructed from realistic coil geometry. Additionally, the ripple-mitigating effect of ferritic inserts was included by modelling the perturbations using the finite element solver COMSOL, previously applied to similar studies for ITER [2]. Fast ion confinement and losses were simulated using the Monte Carlo orbit following code ASCOT both for thermonuclear alpha particles as well as NBI ions, for which an injector model was developed based on the latest DEMO reference design [3]. The fast ion confinement in the European DEMO design was found to be good, with alpha power losses remaining below 500 kW and wall loads below 100 kW/m2 in all cases. The ferritic inserts effectively mitigated the toroidal ripple, reducing the losses nearly to the level of an axisymmetric field. Finally, the confinement of the NBI particles was found to be excellent, with losses remaining below 0.1 %, resulting in minimal deterioration in power deposition and current drive.
2017
Istituto gas ionizzati - IGI - Sede Padova
Inglese
44th European Physical Society Conference on Plasma Physics
4
9781510849303
http://ocs.ciemat.es/EPS2017PAP/pdf/P2.147.pdf
European Physical Society (EPS)
Mulhouse
FRANCIA
26-30 June 2017
Belfast, Northern Ireland
DEMO
P2.147 / 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.
1
none
Varje J.; Agostinetti P.; KurkiSuonio T.; Snicker A.; Sonato P.; Särkimäki K.; Vincenzi P.
273
info:eu-repo/semantics/conferenceObject
04 Contributo in convegno::04.01 Contributo in Atti di convegno
   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/20.500.14243/335781
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