The European Transport Solver

Coster, D.; Basiuk, V.; Pereverzev, G.; Kalupin, D.; Zagórksi, R; Stankiewicz, R.; Huynh, Philippe; Imbeaux, F.

doi:10.1109/tps.2010.2056707

Cited by 38 publications

(39 citation statements)

References 3 publications

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“…Because the sources can affect the plasma temperature and density and, consequently, the ionization and slowing down of the neutral beam, the NBI source has to be operated in a continuous fashion, with thermalized particles leaving and freshly ionized ones continuously entering the system. This is how NUBEAM operates within TRANSP, and also how ASCOT operates when it is used as the fast ion module within the JINTRAC simulation environment [30,31] and, in the future, within the European Transport Simulator (ETS) [32,33]. In this work, however, we want to find the steady-state profiles of various quantities of interest.…”

Section: Nbi Ion Slowing Down Simulationsmentioning

confidence: 99%

“…at JET. Future work also includes using BBNBI and ASCOT to cater for the neutral beam ionization and slowing down modelling needs of European Transport Simulator (ETS) [33,32] within the EFDA Integrated Tokamak Modelling framework (ITM) [11]. Benchmarking BBNBI and ASCOT against other similar tools adapted to the ITM standards will be an integral part of this effort.…”

Section: Summary and Future Workmentioning

confidence: 99%

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Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Asunta

Govenius

Budny

et al. 2015

Computer Physics Communications

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Neutral beam injection (NBI) will be one of the main sources of heating and non-inductive current drive in ITER. Due to high level of injected power the beam induced heat loads present a potential threat to the integrity of the first wall of the device, particularly in the presence of non-axisymmetric perturbations of the magnetic field. Neutral beam injection can also destabilize Alfvén eigenmodes and energetic particle modes, and act as a source of plasma rotation. Therefore, reliable and accurate simulation of NBI is important for making predictions for ITER, as well as for any other current or future fusion device. This paper introduces a new beamlet-based neutral beam ionization model called BBNBI. It takes into account the fine structure of the injector, follows the injected neutrals until ionization, and generates a source ensemble of ionized NBI test particles for slowing down calculations. BBNBI can be used as a stand-alone model but together with the particle following code ASCOT it forms a complete and sophisticated tool for simulating neutral beam injection. The test particle ensembles from BBNBI are found to agree well with those produced by PENCIL for JET, and those produced by NUBEAM both for JET and ASDEX Upgrade plasmas. The first comprehensive comparisons of beam slowing down profiles of interest from BBNBI+ASCOT with results from PENCIL and NUBEAM/TRANSP, for both JET and AUG, are presented. It is shown that, for an axisymmetric plasma, BBNBI+ASCOT and NUBEAM agree remarkably well. Together with earlier 3D studies, these results further validate using BBNBI+ASCOT also for studying phenomena that require particle following in a truly three-dimensional geometry.

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Section: Nbi Ion Slowing Down Simulationsmentioning

confidence: 99%

Section: Summary and Future Workmentioning

confidence: 99%

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Asunta

Govenius

Budny

et al. 2015

Computer Physics Communications

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“…The "European Transport Simulator" (ETS) [1,2] is the new modular package for 1-D discharge evolution developed within the EFDA Integrated Tokamak Modelling (ITM) Task Force. It consists of precompiled physics modules combined into a workflow through standardized input/output data-structures.…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis of JET discharges with the European Transport Simulator

Kalupin¹,

Ivanova‐Stanik²,

Voitsekhovitch³

et al. 2013

Nucl. Fusion

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The "European Transport Simulator" (ETS) [1,2] is the new modular package for 1-D discharge evolution developed within the EFDA Integrated Tokamak Modelling (ITM) Task Force. It consists of precompiled physics modules combined into a workflow through standardized input/output data-structures. Ultimately, the ETS will allow for an entire discharge simulation from the start up until the current termination phase, including controllers and sub-systems. The paper presents the current status of the ETS towards this ultimate goal. It discusses the design of the workflow, the validation and verification of its components on the example of impurity solver and demonstrates a proof-of-principles coupling of a local gyrofluid model for turbulent transport to the ETS. It also presents first results on the application of the ETS to JET tokamak discharges with ITER like wall. It studies the correlations of the radiation from impurity to the choice of the sources and transport coefficients. ETS transport solver and workflow designThe ETS adopts a modular approach, where standalone precompiled physics modules ('actors' in the context of the workflow) are coupled into the workflow through standardised interfaces linked with the ITM data-structure. In view of allowing collective development of

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“…It makes the structure of the simulator fully transparent and enforces a standard method for coupling new components, independent of a particular code or programming language. Prototypes of such fine grained transport solver workflows have been demonstrated already by the EU-ITM [1,15] and it is foreseen to use a similar approach on IMAS. Fast data transfer between components, enabled by the memory cache mechanism of the access layer, as well as using a workflow engine written in a compiled language (Java for Kepler) are key elements to avoid a loss of performance with such fine grained workflows.…”

Section: Fine-grained Component Integrationmentioning

confidence: 99%

Design and first applications of the ITER integrated modelling & analysis suite

Imbeaux¹,

Pinches²,

Lister³

et al. 2015

Nucl. Fusion

113

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The ITER Integrated Modelling & Analysis Suite (IMAS) will support both plasma operation and research activities on the ITER tokamak experiment. The IMAS will be accessible to all ITER members as a key tool for the scientific exploitation of ITER. The backbone of the IMAS infrastructure is a standardized, machine-generic data model that represents simulated and experimental data with identical structures. The other outcomes of the IMAS design and prototyping phase are a set of tools to access data and design integrated modelling workflows, as well as first plasma simulators workflows and components implemented with various degrees of modularity.

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The European Transport Solver

Cited by 38 publications

References 3 publications

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Modelling neutral beams in fusion devices: Beamlet-based model for fast particle simulations

Numerical analysis of JET discharges with the European Transport Simulator

Design and first applications of the ITER integrated modelling & analysis suite

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