Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER
Combining dynamic models and measurements into a consistent plasma state estimate is an important challenge for ITER and DEMO, due to the inherent limitations regarding diagnostic coverage in a nuclear fusion reactor environment. In this work, a model-based estimation algorithm is proposed to improv...
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| Format: | Article |
| Language: | English |
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IOP Publishing
2025-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/add16e |
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| author | S. Van Mulders F. Felici S.C. McIntosh F. Carpanese C.E. Contré R. Coosemans O. Kudláček F. Pastore S.D. Pinches M. Reisner O. Sauter |
| author_facet | S. Van Mulders F. Felici S.C. McIntosh F. Carpanese C.E. Contré R. Coosemans O. Kudláček F. Pastore S.D. Pinches M. Reisner O. Sauter |
| author_sort | S. Van Mulders |
| collection | DOAJ |
| description | Combining dynamic models and measurements into a consistent plasma state estimate is an important challenge for ITER and DEMO, due to the inherent limitations regarding diagnostic coverage in a nuclear fusion reactor environment. In this work, a model-based estimation algorithm is proposed to improve real-time and post-shot estimation of tokamak plasma profiles. The RAPTOR rapid transport solver is employed as a dynamic state observer for the parallel current density $j_\mathrm {par}$ , the electron temperature $T_\mathrm e$ and the electron density $n_\mathrm e$ , applying an Extended Kalman Filter (EKF). The implementation of an EKF which, in addition to the plasma profiles, estimates model disturbances and model parameters has enabled us to account for systematic model-reality mismatches and provides an avenue to automatically validate simple transport models that are easily interpretable and machine-independent, based on raw experimental data. Estimates of transport model coefficients can be directly used to find adequate settings for launching a predictive simulation, accelerating inter-discharge scenario design. Furthermore, a method for maximum likelihood identification of model uncertainty statistics from a database of recorded measurement data is proposed. The RAPTOR EKF is tested for reconstruction of the $j_\mathrm {par}$ , $T_\mathrm e$ and $n_\mathrm e$ profile evolution for an ITER Q = 10 plasma discharge, from ramp-up to ramp-down, based on synthetic Thomson scattering and boundary poloidal flux measurements, generated by adding realistic measurement noise to a DINA-JINTRAC simulation. This approach enables improved safety factor profile estimation in the absence of direct internal current density measurements. |
| format | Article |
| id | doaj-art-cad03efcbd7649d48a18da689436e35c |
| institution | Kabale University |
| issn | 0029-5515 |
| language | English |
| publishDate | 2025-01-01 |
| publisher | IOP Publishing |
| record_format | Article |
| series | Nuclear Fusion |
| spelling | doaj-art-cad03efcbd7649d48a18da689436e35c2025-08-20T03:48:57ZengIOP PublishingNuclear Fusion0029-55152025-01-0165606600610.1088/1741-4326/add16eModel-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITERS. Van Mulders0https://orcid.org/0000-0003-3184-3361F. Felici1https://orcid.org/0000-0001-7585-376XS.C. McIntosh2F. Carpanese3C.E. Contré4R. Coosemans5https://orcid.org/0000-0001-8110-3156O. Kudláček6https://orcid.org/0009-0008-0356-115XF. Pastore7S.D. Pinches8https://orcid.org/0000-0003-0132-945XM. Reisner9O. Sauter10https://orcid.org/0000-0002-0099-6675ITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandMax-Planck-Institut für Plasmaphysik , 85748 Garching bei München, GermanyÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceMax-Planck-Institut für Plasmaphysik , 85748 Garching bei München, GermanyÉcole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC) , CH-1015 Lausanne, SwitzerlandCombining dynamic models and measurements into a consistent plasma state estimate is an important challenge for ITER and DEMO, due to the inherent limitations regarding diagnostic coverage in a nuclear fusion reactor environment. In this work, a model-based estimation algorithm is proposed to improve real-time and post-shot estimation of tokamak plasma profiles. The RAPTOR rapid transport solver is employed as a dynamic state observer for the parallel current density $j_\mathrm {par}$ , the electron temperature $T_\mathrm e$ and the electron density $n_\mathrm e$ , applying an Extended Kalman Filter (EKF). The implementation of an EKF which, in addition to the plasma profiles, estimates model disturbances and model parameters has enabled us to account for systematic model-reality mismatches and provides an avenue to automatically validate simple transport models that are easily interpretable and machine-independent, based on raw experimental data. Estimates of transport model coefficients can be directly used to find adequate settings for launching a predictive simulation, accelerating inter-discharge scenario design. Furthermore, a method for maximum likelihood identification of model uncertainty statistics from a database of recorded measurement data is proposed. The RAPTOR EKF is tested for reconstruction of the $j_\mathrm {par}$ , $T_\mathrm e$ and $n_\mathrm e$ profile evolution for an ITER Q = 10 plasma discharge, from ramp-up to ramp-down, based on synthetic Thomson scattering and boundary poloidal flux measurements, generated by adding realistic measurement noise to a DINA-JINTRAC simulation. This approach enables improved safety factor profile estimation in the absence of direct internal current density measurements.https://doi.org/10.1088/1741-4326/add16eextended Kalman filterdata assimilationITERintegrated tokamak simulationparameter estimationreal-time control |
| spellingShingle | S. Van Mulders F. Felici S.C. McIntosh F. Carpanese C.E. Contré R. Coosemans O. Kudláček F. Pastore S.D. Pinches M. Reisner O. Sauter Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER Nuclear Fusion extended Kalman filter data assimilation ITER integrated tokamak simulation parameter estimation real-time control |
| title | Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER |
| title_full | Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER |
| title_fullStr | Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER |
| title_full_unstemmed | Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER |
| title_short | Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER |
| title_sort | model based estimation of tokamak plasma profiles and physics parameters algorithm overview and application to iter |
| topic | extended Kalman filter data assimilation ITER integrated tokamak simulation parameter estimation real-time control |
| url | https://doi.org/10.1088/1741-4326/add16e |
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