The CRONOS suite of codes for integrated tokamak modelling

Artaud, J.F.; Basiuk, V.; Imbeaux, F.; Schneider, M.; García, J.; Giruzzi, G.; Huynh, P.; Aniel, T.; Albajar, F.; Ané, J.M.; Bécoulet, A.; Bourdelle, C.; Casati, A.; Colas, L.; Decker, J.; Dümont, R.; Eriksson, L.‐G.; Garbet, X.; Guirlet, R.; Hertout, P.; Hoang, G. T.; Houlberg, W. A.; Huysmans, G.; Joffrin, E.; Kim, S.H.; Köchl, F.; Lister, J.B.; Litaudon, X.; Maget, P.; Masset, R.; Pégouriè, B.; Peysson, Y.; Thomas, Paul R.; Tsitrone, E.; Turco, F.

doi:10.1088/0029-5515/50/4/043001

Cited by 254 publications

(258 citation statements)

References 82 publications

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“…Five 1.5D transport evolution codes (including either fixed or free-boundary equilibrium computation) have been involved in simulations for ITER: ASTRA, 51,52 CRONOS, 53 ONETWO, 54 FASTRAN, 55 TOPICS-IB, 56,57 and TSC/TRANSP. 58 Initially, a set of parameters of an ITER hybrid scenario and the heat transport 021804- 14 Sips et al…”

Section: Benchmarking Hybrid and Steady-state Simulationsmentioning

confidence: 99%

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Sips

Giruzzi²,

Ide

et al. 2014

Physics of Plasmas

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The development of operating scenarios is one of the key issues in the research for ITER which aims to achieve a fusion gain (Q) of ∼10, while producing 500 MW of fusion power for ≥300 s. The ITER Research plan proposes a success oriented schedule starting in hydrogen and helium, to be followed by a nuclear operation phase with a rapid development towards Q ∼ 10 in deuterium/tritium. The Integrated Operation Scenarios Topical Group of the International Tokamak Physics Activity initiates joint activities among worldwide institutions and experiments to prepare ITER operation. Plasma formation studies report robust plasma breakdown in devices with metal walls over a wide range of conditions, while other experiments use an inclined EC launch angle at plasma formation to mimic the conditions in ITER. Simulations of the plasma burn-through predict that at least 4 MW of Electron Cyclotron heating (EC) assist would be required in ITER. For H-modes at q95 ∼ 3, many experiments have demonstrated operation with scaled parameters for the ITER baseline scenario at ne/nGW ∼ 0.85. Most experiments, however, obtain stable discharges at H98(y,2) ∼ 1.0 only for βN = 2.0–2.2. For the rampup in ITER, early X-point formation is recommended, allowing auxiliary heating to reduce the flux consumption. A range of plasma inductance (li(3)) can be obtained from 0.65 to 1.0, with the lowest values obtained in H-mode operation. For the rampdown, the plasma should stay diverted maintaining H-mode together with a reduction of the elongation from 1.85 to 1.4. Simulations show that the proposed rampup and rampdown schemes developed since 2007 are compatible with the present ITER design for the poloidal field coils. At 13–15 MA and densities down to ne/nGW ∼ 0.5, long pulse operation (>1000 s) in ITER is possible at Q ∼ 5, useful to provide neutron fluence for Test Blanket Module assessments. ITER scenario preparation in hydrogen and helium requires high input power (>50 MW). H-mode operation in helium may be possible at input powers above 35 MW at a toroidal field of 2.65 T, for studying H-modes and ELM mitigation. In hydrogen, H-mode operation is expected to be marginal, even at 2.65 T with 60 MW of input power. Simulation code benchmark studies using hybrid and steady state scenario parameters have proved to be a very challenging and lengthy task of testing suites of codes, consisting of tens of sophisticated modules. Nevertheless, the general basis of the modelling appears sound, with substantial consistency among codes developed by different groups. For a hybrid scenario at 12 MA, the code simulations give a range for Q = 6.5–8.3, using 30 MW neutral beam injection and 20 MW ICRH. For non-inductive operation at 7–9 MA, the simulation results show more variation. At high edge pedestal pressure (Tped ∼ 7 keV), the codes predict Q = 3.3–3.8 using 33 MW NB, 20 MW EC, and 20 MW ion cyclotron to demonstrate the feasibility of steady-state operation with the day-1 heating systems in ITER. Simulations using a lower edge pedestal temperature (∼3 keV) but improved core confinement obtain Q = 5–6.5, when ECCD is concentrated at mid-radius and ∼20 MW off-axis current drive (ECCD or LHCD) is added. Several issues remain to be studied, including plasmas with dominant electron heating, mitigation of transient heat loads integrated in scenario demonstrations and (burn) control simulations in ITER scenarios.

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Section: Benchmarking Hybrid and Steady-state Simulationsmentioning

confidence: 99%

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Sips

Giruzzi²,

Ide

et al. 2014

Physics of Plasmas

Self Cite

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“…[41,42]) and models used in offline profile reconstruction algorithms (e.g. ASTRA [30], CRONOS [43]) are not directly suitable for the task of real-time density reconstruction, since their execution time generally exceeds the discharge duration. It has been shown in [2][3][4][5]39,40] that low-complexity 1D models can be used for reconstruction and control of the temperature and safety factor profiles.…”

Section: Control-oriented 0+1d Model Of the Particle Transportmentioning

confidence: 99%

Control-oriented modeling of the plasma particle density in tokamaks and application to real-time density profile reconstruction

Blanken

Felici

Rapson

et al. 2018

Fusion Engineering and Design

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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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The CRONOS suite of codes for integrated tokamak modelling

Cited by 254 publications

References 82 publications

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Control-oriented modeling of the plasma particle density in tokamaks and application to real-time density profile reconstruction

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

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