Effects of asymmetric vertical disruptions on ITER components

Albanese, R.; Carpentieri, Bruno; Cavinato, M.; Minucci, S.; Palmaccio, R.; Portone, A.; Rubinacci, G.; Testoni, Pietro; Ventre, Salvatore; Villone, F.

doi:10.1016/j.fusengdes.2015.02.034

Cited by 34 publications

(17 citation statements)

References 11 publications

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“…As seen in figure 9, the vertical force arises in a time scale given by the L/R time of the vacuum vessel (∼ 500 ms). Note that the time traces of the vertical forces are very similar to the ones obtained in [1] for ITER disruptions with volumetric walls. Both cases show similar vertical maximal forces in the range of 11-14 MN despite the different directions for the vertical displacement.…”

Section: Wall Forces After the Current Quenchsupporting

confidence: 72%

Complete 3D MHD simulations of the current quench phase of ITER mitigated disruptions

Artola¹,

Loarte²,

Hoelzl³

et al. 2021

Preprint

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Complete 3D simulations of the current quench phase of ITER disruptions are key to predict asymmetric forces acting into the ITER wall. We present for the first time such simulations for ITER mitigated disruptions at realistic Lundquist numbers. For these strongly mitigated disruptions, we find that the safety factor remains above 2 and the maximal integral horizontal forces remain below 1 MN. The maximal integral vertical force is found to be 13 MN and arises in a time scale given by the resistive wall time as expected from theoretical considerations. In this respect, the vertical force arises after the plasma current has completely decayed, showing the importance of continuing the simulations also in the absence of plasma current. We conclude that the horizontal wall force rotation is not a concern for these strongly mitigated disruptions in ITER, since when the wall forces form, there are no remaining sources of rotation.

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Section: Wall Forces After the Current Quenchsupporting

confidence: 72%

Complete 3D MHD simulations of the current quench phase of ITER mitigated disruptions

Artola¹,

Loarte²,

Hoelzl³

et al. 2021

Preprint

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“…If the divertor geometries of AUG and JET are responsible for reducing the impact of halo currents in downwardmoving VDEs, then we must also conclude that the various lower divertor geometries of C-Mod (1995)(1996), DIII-D (1997), and NSTX do not have a similar short-circuiting effect on the halo currents. Further study of the halo current paths in each device, using either experimental or numerical tools [45,46], would be required to verify this assertion.…”

Section: Projection To Itermentioning

confidence: 99%

A multi-machine scaling of halo current rotation

et al. 2017

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Halo currents generated during unmitigated tokamak disruptions are known to develop rotating asymmetric features that are of great concern to ITER because they can dynamically amplify the mechanical stresses on the machine. This paper presents a multi-machine analysis of these phenomena. More specifically, data from C-Mod, NSTX, ASDEX Upgrade, DIII-D, and JET are used to develop empirical scalings of three key quantities: (1) the machine-specific minimum current quench time, τ CQ ; (2) the halo current rotation duration, trot; and (3) the average halo current rotation frequency, f h. These data reveal that the normalized rotation duration, trot/τ CQ , and the average rotation velocity, v h , are surprisingly consistent from machine to machine. Furthermore, comparisons between carbon and metal wall machines show that metal walls have minimal impact on the behavior of rotating halo currents. Finally, upon projecting to ITER, the empirical scalings indicate that substantial halo current rotation above f h = 20 Hz is to be expected. More importantly, depending on the projected value of τ CQ in ITER, substantial rotation could also occur in the resonant frequency range of 6-20 Hz. As such, the possibility of damaging halo current rotation during unmitigated disruptions in ITER cannot be ruled out.

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“…The decay of plasma diamagnetism induces skin poloidal currents in the first wall component (as close as possible to the plasma) and in the VV aiming to preserve the toroidal flux. At the same time, after the beta decay, the external field gets larger than the value needed for the equilibrium, shrinks the plasma inducing a fast inward movement of the plasma center . As a result, poloidal field variation occurs in the in‐vessel components.…”

Section: Physical Model and Descriptionmentioning

confidence: 99%

“…Amount of handsome work has already been published contingent with plasma shape, control systems and plasma equilibrium properties by numerical techniques. The work contained includes the following aspects, Plasma shaping . Positive or negative radial electric fields . MHD stability, disruptions and operational limits . Plasma energy and stabilities . Plasma current, shape controller and identification, and plasma scenario of small aspect ratio . …”

Section: Introductionmentioning

confidence: 99%

Development of theoretical model for 3D plasma energy behavior and characteristics

Khan

Song

Liu

et al. 2015

Int. J. Energy Res.

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Summary In this paper, research has been conducting on calculating full plasma energy and magnetic field cross sections in static as well as in tilting position for analyzing plasma vertical displacement event behavior. Consequently, the main concern of the research is to developed plasma energy and shape model. First, the developed 3D shape model allows an effective way to study the shape of plasma behavior of main plasma characteristics under controlled conditions including sensitive dependent on initial condition based on isolated points. Secondly, the developed 3D plasma energy model denotes every calculated point and analyze magnetic field of each cross section under different values of α and β according to magnetic field produced by a circular current loop. This theoretical approach showed that the individual points ((a, b) & (r, z)) with static and tilting moments are able to develop the three‐dimension coordinates system, based on R0 = 1.7 ∼ 1.8, B0 = 3.5T and plasma current IP ≤ 1MA. Furthermore, 195 × 12 (both states) circle current loop of magnetic field has been calculated as well. The ‘sinβ cross section’ for every 30° in both states (static and tilt with alpha variations) calculates the total plasma energy. Therefore, we have developed computational codes in Matlab program to calculate the values of full plasma energy in EAST. Energy from initial to final state, VDE and external force behavior, poloidal and toroidal fix degree of every cross section that depends on each current loop of magnetic field have been analyzed based on whole plasma energy data. Copyright © 2015 John Wiley & Sons, Ltd.

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Effects of asymmetric vertical disruptions on ITER components

Cited by 34 publications

References 11 publications

Complete 3D MHD simulations of the current quench phase of ITER mitigated disruptions

Complete 3D MHD simulations of the current quench phase of ITER mitigated disruptions

A multi-machine scaling of halo current rotation

Development of theoretical model for 3D plasma energy behavior and characteristics

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