2018
DOI: 10.1088/1741-4326/aacbdd
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Non-linear MHD simulations of sawteeth and their control by current and power depositions

Abstract: Sawteeth in tokamak plasmas correspond to periodic relaxations of the temperature and density in the central region of the plasma, caused by the internal kink mode. They are a key player in core confinement and impurity transport in the central region of a tokamak discharge, and can trigger secondary instabilities. Being able to control their dynamics is therefore important. In this article, we explore by means of MHD simulations the control of sawteeth, relying on Electron Cyclotron Resonant Heating (ECRH) or… Show more

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Cited by 6 publications
(3 citation statements)
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“…Linear studies in toroidal geometry have revealed the importance of toroidal mode coupling as well as the diamagnetic drift for mode growth [52]. The sawtooth crash is found to lead to an increase in the Δ′ value of the driven mode [53].…”
Section: Numerical Study On Toroidal Mode Coupling and Triggering Of ...mentioning
confidence: 99%
“…Linear studies in toroidal geometry have revealed the importance of toroidal mode coupling as well as the diamagnetic drift for mode growth [52]. The sawtooth crash is found to lead to an increase in the Δ′ value of the driven mode [53].…”
Section: Numerical Study On Toroidal Mode Coupling and Triggering Of ...mentioning
confidence: 99%
“…We use for the bootstrap current the ad-hoc formulation J bs = J eq bs |∇p|/|∇p eq |b where the initial equilibrium bootstrap is computed within the CHEASE code [61]. The non-inductive current density source J CD = J CD e ϕ is then prescribed as J CD = (J ϕ − J bs,ϕ − E 0 /η) t=0 with E 0 a constant prescribed at the edge such that E 0 /(η(0) J ϕ (0)) = 0.75 (see Février et al [37]), i.e. the ohmic current represents 75% of the total current at the plasma center, and about 54% of it at q = 3/2.…”
Section: Equations Solvedmentioning
confidence: 99%
“…A criterion on the required RF current drive and power needed for full stabilization is derived and illustrated for the ITER situation. In a second part, we present full MHD non linear simulations using the XTOR code [36] where a stiff transport model [17] and RF-heating and -current drive are implemented [10,37]. The MHD model that is considered includes ion and electron diamagnetic rotations as well as an ad-hoc bootstrap current, and we consider a simplified ITER-like configuration (section 3) where the (3,2) NTM saturates at about 10% of the minor plasma radius due to the bootstrap drive (section 4).…”
Section: Introductionmentioning
confidence: 99%