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

Falchetto, G.; Coster, D.; Coelho, R.; Scott, B.; Figini, L.; Kalupin, D.; Nardon, E.; Nowak, S.; Alves, L. L.; Artaud, J.F.; Basiuk, V.; Bizarro, João P. S.; Boulbe, Cédric; Dinklage, A.; Farina, D.; Faugeras, Blaise; Ferreira, J.; Figueiredo, A.; Huynh, P.; Imbeaux, F.; Ivanova‐Stanik, I.; Jonsson, T.; Klingshirn, H.-J.; Konz, C.; Kus, A.; Marushchenko, N. B.; Pereverzev, G.; Owsiak, Michał; Poli, E.; Peysson, Y.; Reimer, R.; Signoret, J.; Sauter, O.; Stankiewicz, R.; Strand, Pär; Voitsekhovitch, I.; Westerhof, E.; Żok, Tomasz; Zwingmann, W.; Contributors, Itm-Tf; Contributors, Jet‐Efda

doi:10.1088/0029-5515/54/4/043018

Cited by 67 publications

(66 citation statements)

References 47 publications

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“…This feature will make use of new Interface Data Structures (IDSs), which have been designed for plasma edge codes. These dedicated data structures, similar to the Consistent Physical Objects (CPOs) proposed by the earlier EU Integrated Tokamak Modelling Task Force (ITM TF) framework [13], will allow for standardized archival and retrieval of SOLPS-ITER run results, as well as the incorporation of SOLPS-ITER (or at least B2.5-Eirene) as an actor into wider integrated modelling physics workflows within the ITER Integrated Modelling Analysis Suite (IMAS) framework [14].…”

Section: The Solps-iter Run Environment and Workflowmentioning

confidence: 99%

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Bonnin¹,

Dekeyser²,

Pitts³

et al. 2016

Plasma and Fusion Research

221

200

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We present in this paper the code package SOLPS-ITER, initially introduced by S. Wiesen et al. [J. Nucl. Mater. 463, 480 (2015)], dedicated to simulations of plasmas in the edge region of fusion devices. This package brings together previously existing SOLPS implementations and aims to become the new standard SOLPS version. We summarize the benchmarking work done to ensure backward compatibility with previous work, with a strong requirement on maintaining the viability and usability of the already extensive database of SOLPS runs used for the ITER divertor design and edge plasma physics studies worldwide over the years. The SOLPS-ITER package includes not only the plasma (B2.5) and neutral (Eirene) transport solvers, but also a large set of software tools for input file build-up, conversion of old runs, inline run analysis, and post-processing, all within a standardized portable run environment and version control system. Ongoing and planned upgrades to the code, such as extending the computational domain to the full vacuum vessel wall and a new graphical user interface, are also discussed.

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Section: The Solps-iter Run Environment and Workflowmentioning

confidence: 99%

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Bonnin¹,

Dekeyser²,

Pitts³

et al. 2016

Plasma and Fusion Research

221

200

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“…The status of the development of this tool and recent physics applications are described in Ref. 37, while a short summary of the CPT technical achievements in support of this tool is given here. The CPT is in charge of the development and maintenance of the framework for the IM tool based on a generic data structure consisting of standardized physics-oriented I/O units, CPOs (Ref.…”

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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“…Due to the role of density fluctuations at the edge on the wave heating performance, a turbulence code also has to be used. This can be done iteratively using an integrated tokamak modelling, as in CRONOS (Artaud et al 2010) or in the European ITM platform (Falchetto et al 2014). At this moment, we are rather far from this situation.…”

Section: Heating Simulationmentioning

confidence: 99%

“…They started being integrated in a platform (e.g. ITM platform (Falchetto et al 2014)) able to provide the changes of the macroscopic plasma parameters induced by wave heating or current-drive. Following an iterative process, we can generally have access to an asymptotic state that allows predicting the behaviour of an experiment.…”

Section: Conclusion and New Developmentsmentioning

confidence: 99%

Simulation as a tool to improve wave heating in fusion plasmas

et al. 2015

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(Received ?; revised ?; accepted ?. -To be entered by editorial office)Firstly, a brief overview will be given on different models that are able to describe the behaviour of wave propagation as a function of specific frequency ranges. Each range corresponds to different heating systems, namely, 20-100 MHz for the Ion Cyclotron Resonant Heating (ICRH), 2-20 GHz for Lower Hybrid Heating or Current Drive (LHCD), and 100-250 GHz for Electron Cyclotron Resonant Heating (ERCH) or Current Drive (ECCD) systems. Every systems' specifications will be explained in detail, including the typical set of equations and the assumptions needed to describe the properties of these heating or current drive systems, as well as their specific domains of validity. In these descriptions, special attention will be paid to the boundary conditions. A review about specific physical problems associated with the wave heating systems will also be provided. Such review will detail the role of simulation in answering questions coming from experiments on magnetized plasma devices devoted to Fusion. A few examples which will be covered are the impact of edge turbulence on wave propagation and its consequences on the heating system performances, effects of the fast particles, ponderomotive effects, among others. A study that is more focused on Radio Frequency (RF) sheath effects will also be discussed. It shows that such simulations require very sophisticated tools to gain a partial understanding of the observations undertaken in dedicated experiments. To conclude this review, an overview will be given about the requirements and progress necessary to obtain relevant predictive simulation tools able to describe the wave heating systems used in fusion devices.

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

Cited by 67 publications

References 47 publications

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

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

Simulation as a tool to improve wave heating in fusion plasmas

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