The reconstruction of tokamak plasma equilibrium is a fundamental step in the understanding of fusion plasma physics since it sets the starting point for all subsequent plasma modelling applications and experimental data interpretation. The verification and validation of the numerical codes used to reconstruct plasma equilibrium, using as many available input experimental data, e.g., magnetic field or flux measurements, density and temperature diagnostics and polarimetry diagnostics, is essential both for physics model interpretation and when qualifying and extrapolating for ITER. In the framework of the EUROfusion Work Package on Code Development for Integrated Modelling, a scientific Kepler r1s workflow for the reconstruction of Tokamak plasma equilibrium was prototyped, using the ITER Integrated Modelling and Analysis Suite (IMAS) r2, 3s. The workflow can seamlessly use any sort of data from tokamak experiments and call reconstruction codes such as EQUAL r4s, CLISTE r5s, EQUINOX r6s and SDSS r7s, all using the same physics and engineering data ontology and methods for accessing the data. In this work, we address plasma equilibrium reconstructions on dedicated JET plasma discharges, performing a code benchmark using, at first, magnetic data only and subsequently considering also other constrains such as polarimetry (Stokes vector based or motional Stark effect). First results with magnetic only give good qualitative and quantitative agreement between the codes.

Plasma Equilibrium Reconstruction of JET Discharges Using the IMAS Modelling Infrastructure

Terranova D
2018

Abstract

The reconstruction of tokamak plasma equilibrium is a fundamental step in the understanding of fusion plasma physics since it sets the starting point for all subsequent plasma modelling applications and experimental data interpretation. The verification and validation of the numerical codes used to reconstruct plasma equilibrium, using as many available input experimental data, e.g., magnetic field or flux measurements, density and temperature diagnostics and polarimetry diagnostics, is essential both for physics model interpretation and when qualifying and extrapolating for ITER. In the framework of the EUROfusion Work Package on Code Development for Integrated Modelling, a scientific Kepler r1s workflow for the reconstruction of Tokamak plasma equilibrium was prototyped, using the ITER Integrated Modelling and Analysis Suite (IMAS) r2, 3s. The workflow can seamlessly use any sort of data from tokamak experiments and call reconstruction codes such as EQUAL r4s, CLISTE r5s, EQUINOX r6s and SDSS r7s, all using the same physics and engineering data ontology and methods for accessing the data. In this work, we address plasma equilibrium reconstructions on dedicated JET plasma discharges, performing a code benchmark using, at first, magnetic data only and subsequently considering also other constrains such as polarimetry (Stokes vector based or motional Stark effect). First results with magnetic only give good qualitative and quantitative agreement between the codes.
2018
Istituto gas ionizzati - IGI - Sede Padova
Inglese
27th IAEA Fusion Energy Conference (FEC 2018)
1
8
8
https://hal.archives-ouvertes.fr/hal-01947230/document
22-27 October 2018
Ahmedabad, India
Plasma Equilibrium Reconstruction
JET Discharges
IMAS Modelling
Contribution and poster ID: TH / P5-27 / https://www.iaea.org/sites/default/files/18/10/cn-258-abstracts.pdf
11
none
Coelho, R; Zwingmann, W; Faugeras, B; Giovannozzi, E; Mccarthy, P; Suchkov, Ep; Zaitsev, Fs; Hollocombe, J; Hawkes, N; Szepesi, G; Terranova, D...espandi
273
info:eu-repo/semantics/conferenceObject
04 Contributo in convegno::04.01 Contributo in Atti di convegno
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/351767
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