ITER design features serving for suppression of eddy- and halo related electromagnetic loads

Sadakov, S.; Furmanek, A.; Calcagno, B.; Bertolini, Clara; Khomiakov, S.; Kolganov, V.; Poddubnyi, I.

doi:10.1016/j.fusengdes.2015.06.023

Cited by 1 publication

(1 citation statement)

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“…Fast losses of the plasma confinement-disruptions [1]-may threaten future power plant-relevant tokamaks on numerous fronts: through generation of runaway beams piercing the first wall armor [2], deposition of significant thermal and particle loads leading to melting and erosion of the plasma facing components [3] and exertion of substantial electromagnetic forces (resulting from eddy and halo currents) that can compromise the integrity of device structural components [4]. As such, disruptions will have to be mitigated, or ultimately avoided when necessary, in devices such as ITER [5] and SPARC [6].…”

Section: Introductionmentioning

confidence: 99%

DECAF cross-device characterization of tokamak disruptions indicated by abnormalities in plasma vertical position and current

Zamkovska,

Sabbagh,

Tobin

et al. 2024

Nucl. Fusion

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Abnormal (deviating from target) variations in the plasma vertical position Z and current Ip (such as vertical displacements, transient Ip 'spikes' and quenches) constitute common elements of a disruption, a phenomenon that is to be mitigated, or ultimately avoided in future reactor-relevant tokamaks. While those abnormalities are generally recognized cross-shot and cross-device, details in terms of appearance (or not) and order of those abnormalities in disruption event chains is bound with the plasma state at the time of the chain initiation. Detection of those abnormalities is thus indicative not only of the onset of the plasma collapse itself, but also of the disruption driving cause that is promoted at the particular plasma state. Here, occurrence of disruptions, explored via detection of a Ip quench, and analysis of disruption event chains constituted by Ip and Z abnormalities, is reported for in total 7 full years of operation of 3 devices (KSTAR, MAST-U and NSTX-U) using the DECAFTM code expanded tools and capabilities. It is shown that the disruption occurrence depends not only on details of the plasma state, but also on (device-dependent) technical elements of the shot exit scenario. A year-to-year change in main disruption causes and a reduction of the disruptivity rate, bound with device and operation upgrades, are reported. Particular trigger instances of disruption event chains (and the full chains, when applicable) are shown to occupy different parts of the operation space diagrams, in accordance with prior expectation. Plasma elongation is identified as an important factor influencing details of the chains and its role will be further explored.

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