The CEDRES++ equilibrium code and its application to ITER, JT-60SA and Tore Supra

Hertout, P.; Boulbe, Cédric; Nardon, E.; Blum, Jacques; Brémond, S.; Bucalossi, J.; Faugeras, Blaise; Grandgirard, V.; Moreau, Philippe

doi:10.1016/j.fusengdes.2011.03.092

Cited by 13 publications

(8 citation statements)

References 9 publications

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“…is the flux at the control points of plasma boundary, Γ d is the desired plasma boundary, Ω X is the region near the Xpoint, w M , w X , and w i are weighting coefficients specified by user. [15] defining the shape of plasma and boundary control points It is derived that the equation (3) can be converted into an overdetermined equation system, which is composed of a group of least square solutions, and it is given by…”

Section: Fixed Boundary Equilibrium Solvermentioning

confidence: 99%

Plasma shape optimization for EAST tokamak using orthogonal method

Chen¹,

Bao²,

Fu³

et al. 2019

Chinese Phys. B

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It is necessary to reduce the currents of poloidal field (PF) coils as small as possible, during the static equilibrium design procedure of Experimental Advanced Superconductive Tokamak (EAST). The quasi-snowflake (QSF) divertor configuration is studied in this paper. Starting from a standard QSF plasma equilibrium, a new QSF equilibrium with 300 kA total plasma current is designed. In order to reduce the currents of PF6 and PF14, the influence of plasma shape on PF coil current distribution is analyzed. A fixed boundary equilibrium solver based on a non-rigid plasma model is used to calculate the flux distribution and PF coil current distribution. Then the plasma shape parameters are studied by the orthogonal method. According to the result, the plasma shape is redefined, and the calculated equilibrium shows that the currents of PF6 and PF14 are reduced by 3.592 kA and 2.773 kA, respectively.

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Section: Fixed Boundary Equilibrium Solvermentioning

confidence: 99%

Plasma shape optimization for EAST tokamak using orthogonal method

Chen¹,

Bao²,

Fu³

et al. 2019

Chinese Phys. B

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“…This allows including important operational limits and real-time magnetic control issues in the design of scenarios [54]. The ETS now has such a capability thanks to the inclusion of a Free-Boundary Equilibrium (FBE) solver, at present, either CEDRES++ [55] or FREEBIE [56] [57]. The circuit equations for the PF coils and passive structures are embedded in the FBE code.…”

Section: Free Boundary Equilibrium Coupled To Transportmentioning

confidence: 99%

The European Integrated Tokamak Modelling (ITM) effort: achievements and first physics results

Falchetto¹,

Coster²,

Coelho³

et al. 2014

Nucl. Fusion

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Abstract.A selection of achievements and first physics results are presented of the European Integrated Tokamak Modelling Task Force (EFDA ITM-TF) simulation framework, which aims to provide a standardized platform and an integrated modelling suite of validated numerical codes for the simulation and prediction of a complete plasma discharge of an arbitrary tokamak. The framework developed by the ITM-TF, based on a generic data structure including both simulated and experimental data, allows for the development of sophisticated integrated simulations (workflows) for physics application. The equilibrium reconstruction and linear MHD stability simulation chain was applied, in particular, to the analysis of the edge MHD stability of ASDEX Upgrade type-I ELMy Hmode discharges and ITER hybrid scenario, demonstrating the stabilizing effect of an increased Shafranov shift on edge modes. Interpretive simulations of a JET hybrid discharge were performed with two electromagnetic turbulence codes within ITM infrastructure showing the signature of trapped-electron assisted ITG turbulence. A successful benchmark among five EC beam/ray-tracing codes was performed in the ITM framework for an ITER inductive scenario for different launching conditions from the Equatorial and Upper Launcher, showing good agreement of the computed * See the Appendix.

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“…The very first conception of CEDRES++, that used the same methods as SCED and Proteus, was developed in (Grandgirard 1999). Various simulations with this old version of CEDRES++ are reported in Grandgirard (1999) and Hertout et al (2011).…”

Section: Introductionmentioning

confidence: 99%

Quasi-static free-boundary equilibrium of toroidal plasma with CEDRES++: Computational methods and applications

et al. 2015

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We present a comprehensive survey of the various computational methods in CEDRES++ for finding equilibria of toroidal plasma. Our focus is on free-boundary plasma equilibria, where either poloidal field coil currents or the temporal evolution of voltages in poloidal field circuit systems are given data. Centered around a piecewise linear finite element representation of the poloidal flux map, our approach allows in large parts the use of established numerical schemes. The coupling of a finite element method and a boundary element method gives consistent numerical solutions for equilibrium problems in unbounded domains. We formulate a new Newton method for the discretized nonlinear problem to tackle the various non-linearities, including the free plasma boundary. The Newton method guarantees fast convergence and is the main building block for the inverse equilibrium problems that we can handle in CEDRES++ as well. The inverse problems aim at finding either poloidal field coil currents that ensure a desired shape and position of the plasma or at finding the evolution of the voltages in the poloidal field circuit systems that ensure a prescribed evolution of the plasma shape and position. We provide equilibrium simulations for the tokamaks ITER and WEST to illustrate the performance of CEDRES++ and its application areas.Here again, this is a straightforward and simple calculation for all mappings except one: the mapping J P,h that is related to the non-linear current profile in the plasma domain. The mapping J P,h is given by

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The CEDRES++ equilibrium code and its application to ITER, JT-60SA and Tore Supra

Cited by 13 publications

References 9 publications

Plasma shape optimization for EAST tokamak using orthogonal method

Plasma shape optimization for EAST tokamak using orthogonal method

The European Integrated Tokamak Modelling (ITM) effort: achievements and first physics results

Quasi-static free-boundary equilibrium of toroidal plasma with CEDRES++: Computational methods and applications

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