JINTRAC: A System of Codes for Integrated Simulation of Tokamak Scenarios

Romanelli, M.; Corrigan, G.; Parail, V.; Wiesen, S.; Ambrosino, R.; Belo, P.; Garzotti, L.; Harting, D.; Köchl, F.; Koskela, T.; Lauro-Taroni, L.; Marchetto, C.; Mattei, M.; Militello-Asp, E.; Nave, M. F. F.; Pamela, S.; Salmi, A.; Strand, Pär; Szepesi, G.

doi:10.1585/pfr.9.3403023

Cited by 167 publications

(184 citation statements)

References 16 publications

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“…The idea of increasing the diffusion in the region of the island to mimic its effect on transport has been previously validated with the JETTO [28] transport code, in the case of predicting the effects of islands on neutron yield in JET-ILW Hybrid pulses [29]. In this paper we present an initial analysis of the effect of a (3,2) island on the transport of tungsten localised off-axis on the low field side.…”

Section: Increased Tungsten Diffusion Due To the Islandmentioning

confidence: 99%

The role of MHD in causing impurity peaking in JET hybrid plasmas

et al. 2016

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In Hybrid plasma operation in JET with its ITER-like wall (JET-ILW) it is found that n>1 tearing activity can significantly enhance the rate of on-axis peaking of tungsten impurities, which in turn significantly degrades discharge performance. Core n=1 instabilities can be beneficial in removing tungsten impurities from the plasma core (e.g. sawteeth or fishbones), but can conversely also degrade core confinement (particularly in combination with simultaneous n=3 activity). The nature of MHD instabilities in JET Hybrid discharges, with both its previous Carbon wall and subsequent JET-ILW, is surveyed statistically and the character of the instabilities is examined. Possible qualitative models for how the n>1 islands can enhance on-axis tungsten transport accumulation processes are presented.

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Section: Increased Tungsten Diffusion Due To the Islandmentioning

confidence: 99%

The role of MHD in causing impurity peaking in JET hybrid plasmas

et al. 2016

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“…It shall be remarked that the CREATE-NL? equilibrium code [70] can be integrated with transport solvers [70], in order to receive as input the plasma internal profiles, hence running coupled nonlinear simulations.…”

Section: The Input Voltages Vector;mentioning

confidence: 99%

Plasma Magnetic Control in Tokamak Devices

Tommasi

2018

J Fusion Energ

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In tokamak experimental reactors, the magnetic control system is one of the main plasma control systems that is required, together with the density control, since the very beginning, even before first operations. Indeed, the magnetic control drives the current in the external poloidal circuits in order to first achieve the breakdown conditions and, after plasma formation, to track the desired plasma current, shape and position. Furthermore, when the plasma poloidal cross-section is vertically elongated, the magnetic control takes also care of the vertical stabilization of the plasma column, and therefore it is an essential system for operation. This chapter introduces a reference architecture for plasma magnetic control in tokamaks. Given the proposed architecture, the techniques to design all the required control algorithms is also presented. Experimental results obtained on the JET and EAST tokamaks and simulations for machines currently under construction are shown to prove the effectiveness of the proposed architecture and control algorithms.

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“…39), an automated physics actor generator for KEPLER software presently used as a graphical WF engine for the IM tool, and other infrastructure functionalities. Such an infrastructure is by essence completely generic and can treat any problem which can be described by the data model, in contrast to integrated transport codes [40][41][42] which are typically focused on solving a specific physics problem (mainly, solving time-dependent core transport equations coupled to a variety of sources and transport components). Recently, the performance of the complex CPS17.177-5c IM WFs was optimized by developing a generic coupling method between a multiphysics WF engine and an optimization framework.…”

Section: Toward a Numerical Tokamak: Support To The Development Omentioning

confidence: 99%

Recent EUROfusion Achievements in Support of Computationally Demanding Multiscale Fusion Physics Simulations and Integrated Modeling

Voitsekhovitch

Hatzky

Coster

et al. 2018

Fusion Science and Technology

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-Integrated modeling (IM) of present experiments and future tokamak reactors requires the provision of computational resources and numerical tools capable of simulating multiscale spatial phenomena as well as fast transient events and relatively slow plasma evolution within a reasonably short computational time. Recent progress in the implementation of the new computational resources for fusion applications in Europe based on modern supercomputer technologies (supercomputer MARCONI-FUSION), in the optimization and speedup of the EU fusion-related first-principle codes, and in the *E-mail: Irina.Voitsekhovitch@ukaea.uk This is an Open Access article distributed under the terms of the Creative Commons Attribution-NonCommercial-NoDerivatives License (http://creativecommons.org/licenses/by-nc-nd/4.0/), which permits non-commercial re-use, distribution, and reproduction in any medium, provided the original work is properly cited, and is not altered, transformed, or built upon in any way. FUSION SCIENCE AND TECHNOLOGY

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JINTRAC: A System of Codes for Integrated Simulation of Tokamak Scenarios

Cited by 167 publications

References 16 publications

The role of MHD in causing impurity peaking in JET hybrid plasmas

The role of MHD in causing impurity peaking in JET hybrid plasmas

Plasma Magnetic Control in Tokamak Devices

Recent EUROfusion Achievements in Support of Computationally Demanding Multiscale Fusion Physics Simulations and Integrated Modeling

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