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Real-time-capable prediction of temperature and density profiles in a tokamak using RAPTOR and a first-principle-based transport model

    • Eindhoven University of Technology (TU/e)
    • Dutch Institute for Fundamental Energy Research (DIFFER)
    • Ecole Polytechnique Fédérale de Lausanne (EPFL)
    • Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
    • Max-Planck-Institut für Plasmaphysik (IPP)
    • National Research Council (CNR)
    • Czech Academy of Sciences
    • Universidade de Lisboa
    • University of Naples Federico II
    • University of Cagliari
    • Parthenope University of Naples
    • National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)
    • National Technical University of Athens
    • Laboratorio Nacional de Fusión (LNF)
    • University of Oxford
    • Culham Science Centre
    • European Consortium for the Development of Fusion Energy (EUROfusion)
    • University of Seville
    • Hungarian Academy of Sciences
    • Aalto University
    • University of Helsinki
    • Seoul National University
    • Institute of Plasma Physics (ASIPP CAS)
    • Chalmers University of Technology

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    The RAPTOR code is a control-oriented core plasma profile simulator with various applications in control design and verification, discharge optimization and real-time plasma simulation. To date, RAPTOR was capable of simulating the evolution of poloidal flux and electron temperature using empirical transport models, and required the user to input assumptions on the other profiles and plasma parameters. We present an extension of the code to simulate the temperature evolution of both ions and electrons, as well as the particle density transport. A proof-of-principle neural-network emulation of the quasilinear gyrokinetic QuaLiKiz transport model is coupled to RAPTOR for the calculation of first-principle-based heat and particle turbulent transport. These extended capabilities are demonstrated in a simulation of a JET discharge. The multi-channel simulation requires ∼0.2 s to simulate 1 second of a JET plasma, corresponding to ∼20 energy confinement times, while predicting experimental profiles within the limits of the transport model. The transport model requires no external inputs except for the boundary condition at the top of the H-mode pedestal. This marks the first time that simultaneous, accurate predictions of Te, Ti and ne have been obtained using a first-principle-based transport code that can run in faster-than-real-time for present-day tokamaks.

    Original languageEnglish
    Article number096006
    JournalNuclear Fusion
    Volume58
    Issue number9
    DOIs
    Publication statusPublished - 3 Jul 2018
    MoE publication typeA1 Journal article-refereed

    Funding

    The work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053. This work was also supported in part by the Swiss National Science Foundation.

    UN SDGs

    This output contributes to the following UN Sustainable Development Goals (SDGs)

    1. SDG 7 - Affordable and Clean Energy
      SDG 7 Affordable and Clean Energy

    Keywords

    • integrated tokamak simulation
    • machine learning
    • real-time control
    • tokamak profiles
    • tokamak transport

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