Coupling of nonlinear axisymmetric plasma evolution with three-dimensional volumetric conductors

Villone, F.; Barbato, L.; Mastrostefano, S.; Ventre, S.

doi:10.1088/0741-3335/55/9/095008

Cited by 63 publications

(69 citation statements)

References 30 publications

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“…The CarMa0NL code is described in details in [17]; here, we recall only the main points. The basic idea is that the electromagnetic interaction between the plasma and the conductors is decoupled via a suitable surface located in between.…”

Section: Numerical Codes: Maxfea and Carma0nlmentioning

confidence: 99%

“…In particular, two codes are used: MAXFEA [16], a well assessed 2D evolutionary equilibrium code, and CarMa0NL [17], a recently developed code able to consider three-dimensional conducting structures surrounding the plasma. Using two different approaches, on the one hand we provide a cross-validation and benchmark, and on the other we highlight specific effects which are not always considered in the analysis of disruptions, like the effect of poloidal currents in the conductors and three-dimensional effects due to the deviation of currents from the toroidal direction.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Electromagnetic disruption analysis in IGNITOR

Villone

Ramogida²,

Rubinacci

2015

Fusion Engineering and Design

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Section: Numerical Codes: Maxfea and Carma0nlmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Electromagnetic disruption analysis in IGNITOR

Villone

Ramogida²,

Rubinacci

2015

Fusion Engineering and Design

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“…The procedure has been discussed previously [6]. Therefore, here, for convenience, just a short description of mathematical basis is provided.…”

Section: B Carma0nl Codementioning

confidence: 99%

Error Field Impact on Plasma Boundary in ITER Scenarios

et al. 2016

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Discrepancies in magnetic field maps produced by confinement coils in thermonuclear fusion reactors may drive plasma to lose stability and must be carefully controlled during the whole time evolution of each shot using suitable correction coils. Even when kept below safety thresholds, these error fields (EFs) may alter the geometry of magnetic flux lines, defining the plasma geometry. This paper, using high accuracy 3-D magnetic field computations for confinement coils, addresses the issue of evaluating the effect of EFs on the plasma boundary shape during the shot, modeled as a sequence of equilibrium configurations. In particular, a procedure that can compute the shape perturbations due to given deformations of the coils has been set up and used to carry out an analysis of relationship between the EF and shape perturbations during the time evolution of International Tokamak Experimental Reactor programmed scenario.

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“…A 3D model of the vessel was created by using the CarMa0NL code [10], able to describe the nonlinear evolution of free-boundary axisymmetric plasmas in presence of 3D conducting structures surrounding the plasma.…”

Section: Carma0nl Modelsmentioning

confidence: 99%

First disruption studies and simulations in view of the development of the DEMO Physics Basis

Ramogida

Maddaluno

Villone

et al. 2015

Fusion Engineering and Design

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h i g h l i g h t s• The prediction of disruption features and loads is essential in the design of DEMO.• Different disruptions need to be simulated to evaluate the EM and thermal loads.• Extrapolation of the thermal quench duration to DEMO gives values from 0.8 to 1.1 ms.• Extrapolation of the current quench duration to DEMO gives values from 47 to 107 ms.• First CarMa0NL simulations points out the effect of large 3D conductive structures. a b s t r a c tIn the development of the DEMO Physics Basis an important role is played by the prediction of the plasma disruption features and by the evaluation of the electro-magnetic (EM) and thermal loads associated with these events. Indeed, the kind and number of foreseen plasma disruptions drive the development of the DEMO operation scenarios and the design of vessel and in-vessel components.To characterize a plausible macroscopic plasma dynamics during these events, we will carry out an extrapolation from present-day machines of the main parameters characterizing the disruptions: thermal and current quench time, evolution of plasma current, ˇ and l i , safety factor limits, halo current fraction and width, radiated heat fraction. In particular, we will focus on extrapolations for the thermal and current quench characteristic times, due to their importance for the subsequent simulations aimed at the evaluation of the EM and thermal loads. The different options for DEMO design will be taken into account and the possible range of variation of the parameters will be estimated.The 2D axysimmetric MAXFEA and the 3D CarMa0NL codes will be used to evaluate the effects of the induced currents and the EM loads during a disruptive event and to analyze the various design options obtained by the PROCESS code. The results of these simulations, modeled as worst expected events, will be used as input for the system level analysis and design of the vessel and relevant in-vessel components. First simulations with CarMa0NL code including 3D structures are here presented to show the significant effects due to the large access ports.

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Coupling of nonlinear axisymmetric plasma evolution with three-dimensional volumetric conductors

Cited by 63 publications

References 30 publications

Electromagnetic disruption analysis in IGNITOR

Electromagnetic disruption analysis in IGNITOR

Error Field Impact on Plasma Boundary in ITER Scenarios

First disruption studies and simulations in view of the development of the DEMO Physics Basis

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