Status of the EU domestic agency electromagnetic analyses of ITER vacuum vessel and blanket modules

Testoni, Pietro; Albanese, R.; Lucca, F.; Roccella, M.; Portone, A.; Rubinacci, G.; Ventre, Salvatore; Villone, F.

doi:10.1016/j.fusengdes.2012.11.004

Cited by 11 publications

(5 citation statements)

References 7 publications

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“…Being the first barrier to accept the outburst of the electromagnetic energy, the wall reaction (tremendous induced currents) strongly affects the process and should be properly treated. This is confirmed by observations of strong disruption forces on the wall observed on JET tokamak [4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19] and in various theoretical studies that predict the existence of such forces [4,5,7,[20][21][22][23][24][25][26][27][28][29][30][31][32][33][34] and end up in formidable extrapolations to ITER…”

Section: Introductionsupporting

confidence: 56%

“…If instead a simplified description of the plasma would be used without guaranteed force balance on the plasma, this might not be true anymore. The example that deserves careful study under this angle is the plasma described as a set of current-carrying filaments (either toroidally directed [27,45] or tilted and shifted [5,11]). If their choice is not subject to the constraint that the total force acting on the full set of such filaments is zero, the force calculated on the perfect wall would be wrong of the same amount.…”

Section: Disruption Studiesmentioning

confidence: 99%

“…Equation (27) states that the current in the VV, after getting 'instantaneously' to a high initial value due to the disruption, decays very rapidly, on a time scale τ A even shorter than τ V due to the magnetic coupling with DFD. The current in the DFD starts from zero, then it rapidly grows to a maximum value with the fast time constant τ A , from which it decays with the slow time constant τ B .…”

Section: Disruption Force Damper (Dfd)mentioning

confidence: 99%

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On the computation of the disruption forces in tokamaks

2017

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The currents and forces induced in the tokamak vacuum vessel (wall) during the disruption are calculated for different values of wall resistivity. Several consequences and new developments are derived from the general result that the global disruption force acting on the perfectly conducting wall must be exactly opposite to the similar force acting on the plasma, which is inherently small in tokamaks. This theoretical prediction is tested and confirmed here for the ITER tokamak with disruption modelled as the fast thermal quench followed by slower current quench that develops into the vertical displacement event. The plasma is simulated by the evolutionary equilibrium code CarMa0NL. One of the results is that the computed integral force on a perfectly conducting wall is zero at each instant during a disruption. This in turn highlights the importance of having good models for the plasma (in which the equilibrium constraint is explicitly imposed) and for the structures (able to correctly describe the induced currents and the resistive effects). The dependence of the disruption force on the magnetic field penetration through the wall is demonstrated. Also the concept of a disruption force damper is proposed, able to ‘absorb’ a significant part of the force that would arise on a resistive wall during a disruption.

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Section: Introductionsupporting

confidence: 56%

Section: Disruption Studiesmentioning

confidence: 99%

Section: Disruption Force Damper (Dfd)mentioning

confidence: 99%

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On the computation of the disruption forces in tokamaks

2017

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“…This condition and its consequence F(w−) = 0, where F is the same integral as in (1), but taken on w−, are automatically satisfied when B is found in solving the full equilibrium problem with proper matching of the internal and external solutions. On the contrary, when the plasma is introduced as a rigid ring [3,4,8] or wire [36][37][38] or a set of filaments [21,22,[39][40][41][42][43][44][45][46] with a current J, the tilt and CQ treated as dJ/dt = 0 result in a magnetic field different from B needed for the gaseous (absolutely non-rigid!) plasma equilibrium.…”

Section: Models For the Sideways Forcementioning

confidence: 99%

Models and scalings for the disruption forces in tokamaks

Pustovitov¹

2022

Nucl. Fusion

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The study is devoted to theoretical analysis of the models for calculating the disruption forces in tokamaks. It is motivated by the necessity of reliable predictions for ITER. The task includes the evaluation of the existing models, resolution of the conflicts between them, elimination of contradictions by proper improvements, elaboration of recommendations for dedicated studies. Better qualities of the modelling and higher accuracy are the ultimate theoretical goals. In recent years, there was a steady progress in developing a physics basis for calculating the forces, which gave rise to new trends and ideas. It was discovered, in particular, that the wall resistivity, penetration of the magnetic perturbation through the wall, the poloidal current induced in the wall, the kink-mode coupling, plasma position in the vacuum vessel must be the elements essentially affecting the disruption forces. These and related predictions along with earlier less sophisticated concepts and results are analyzed here

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“…Sometimes it is not clear whether this current is properly accounted for [50,51], and very often it is plainly ignored [19,[24][25][26][27][28] in the disruption tasks. The latter occurs in calculations when the wall is replaced by a set of isolated toroidal conductors, as described in the applications of the DINA code [19,25,28].…”

Section: The Disruption Force and Its Partial Contributionsmentioning

confidence: 99%

Local and integral disruption forces on the tokamak wall

Pustovitov¹,

Kiramov²

2018

Plasma Phys. Control. Fusion

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The disruption-induced forces on the tokamak wall are evaluated analytically within the standard large-aspect-ratio model that implies axisymmetry, circular plasma and wall, and absence of halo currents. Additionally, the ideal-wall reaction is assumed. The disruptions are modelled as rapid changes in the plasma pressure (thermal quench (TQ)) and net current (current quench (CQ)). The force distribution over the poloidal angle is found as a function of these inputs. The derived formulas allow comparison of the TQ-and CQ-produced forces calculated differently, with and without account of the poloidal current induced in the wall. The latter variant represents the inherent property of the codes treating the wall as a set of toroidal filaments. It is proved here that such a simplification leads to unacceptably large errors in the simulated forces for both TQs and CQs. It is also shown that the TQ part of the force must prevail over that due to CQ in the high-β scenarios developed for JT-60SA and ITER.

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Status of the EU domestic agency electromagnetic analyses of ITER vacuum vessel and blanket modules

Cited by 11 publications

References 7 publications

On the computation of the disruption forces in tokamaks

On the computation of the disruption forces in tokamaks

Models and scalings for the disruption forces in tokamaks

Local and integral disruption forces on the tokamak wall

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