The fully non - inductive sustainment of high normalized beta plasmas ( ? N ) is a crucial challenge for the steady - state operation of a tokamak reactor. In order to assess the difficulties facing such scenarios, steady - state regimes have been explored on the Tokamak à Configuration Variable (TCV) using the newly available 1MW Neutral Beam Injection (NBI) system. The operating space i s extended towards plasmas that are closer to those expected in JT - 60SA and ITER, i.e. with significant NBI and Electron Cyclotron Resonance Heating and C urrent D rive (ECRH/CD) , bootstrap current and F a st I on (FI) fraction . ? N values up to 1.4 and 1.7 are obtained in lower single null L - mode (H 98 (y,2)~0.8) a nd H - mode (H 98 (y,2)~1) plasmas, respectively, at zero time averaged loop voltage and q 95 ~6 . Fully non - inductive operation i s not achieved with NBI alone, whose injection c an even increase the loop voltage in the presence of EC waves. A strong contribution to the total plasma pr essure of bulk and FIs from NBI is experimentally evidenced and confirmed by interpretative ASTRA and NUBEAM modelling , which further predict s that FI charge - exchange reactions are the main loss channel for NBH/CD efficiency. Internal t ransport b arriers, which are expected to maximize the boo t strap current fraction, are not formed in either the electron or the ion channel i n the plasmas explored to date, despite a significant increase in the toroidal rotation and FI fraction with NBI, which are known to re duce turbulence. First results on scenario development of high - ? N fully non - inductive H - mode plasmas are also presented.

Extension of the Operating Space of High-Beta N Fully Noninductive Scenarios on TCV Using Neutral Beam Injection

Agostini M;Gobbin M;Nowak S;
2018

Abstract

The fully non - inductive sustainment of high normalized beta plasmas ( ? N ) is a crucial challenge for the steady - state operation of a tokamak reactor. In order to assess the difficulties facing such scenarios, steady - state regimes have been explored on the Tokamak à Configuration Variable (TCV) using the newly available 1MW Neutral Beam Injection (NBI) system. The operating space i s extended towards plasmas that are closer to those expected in JT - 60SA and ITER, i.e. with significant NBI and Electron Cyclotron Resonance Heating and C urrent D rive (ECRH/CD) , bootstrap current and F a st I on (FI) fraction . ? N values up to 1.4 and 1.7 are obtained in lower single null L - mode (H 98 (y,2)~0.8) a nd H - mode (H 98 (y,2)~1) plasmas, respectively, at zero time averaged loop voltage and q 95 ~6 . Fully non - inductive operation i s not achieved with NBI alone, whose injection c an even increase the loop voltage in the presence of EC waves. A strong contribution to the total plasma pr essure of bulk and FIs from NBI is experimentally evidenced and confirmed by interpretative ASTRA and NUBEAM modelling , which further predict s that FI charge - exchange reactions are the main loss channel for NBH/CD efficiency. Internal t ransport b arriers, which are expected to maximize the boo t strap current fraction, are not formed in either the electron or the ion channel i n the plasmas explored to date, despite a significant increase in the toroidal rotation and FI fraction with NBI, which are known to re duce turbulence. First results on scenario development of high - ? N fully non - inductive H - mode plasmas are also presented.
2018
Istituto di fisica del plasma - IFP - Sede Milano
Istituto gas ionizzati - IGI - Sede Padova
Inglese
27th IAEA Fusion Energy Conference (FEC 2018)
1
8
8
https://nucleus.iaea.org/sites/fusionportal/Shared%20Documents/FEC%202018/fec2018-preprints/preprint0169.pdf
22-27 October 2018
Ahmedabad, India
Tokamac Configuration Variable
TCV
Neutral Beam Injection
NBI
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. // IAEA - CN - 258/ EX/P1 - 30 // https://www.iaea.org/sites/default/files/18/10/cn-258-abstracts.pdf
17
none
Piron, C; Garcia, J; Goodman, Tp; Agostini, M; Fontana, M; Giruzzi, G; Gobbin, M; Karpushov, An; Kong, M; Merle, A; Morales, J; Nowak, S; Pigatto, L; ...espandi
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/20.500.14243/351749
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