ICRF heating and turbulent transport modelling of the WEST L-mode plasma using ETS: interpretative and predictive code validation
| Autor: | Huynh, P, Lerche, E, van Eester, D, Garcia, J, Frazzoli, G, Maget, P, Artaud, J, Ferreira, J, Johnson, T, Yadykin, D, Strand, P |
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| Přispěvatelé: | Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Culham Centre for Fusion Energy (CCFE), Laboratoire de physique des plasmas de l'ERM, Laboratorium voor plasmafysica van de KMS (LPP ERM KMS), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Instituto de Plasmas e Fusão Nuclear [Lisboa] (IPFN), Instituto Superior Técnico, Universidade Técnica de Lisboa (IST), Department of Fusion Plasma Physics [Stockholm] (KTH), Royal Institute of Technology [Stockholm] (KTH ), Chalmers University of Technology [Göteborg], Chalmers University of Technology [Gothenburg, Sweden], The WEST team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014) |
| Jazyk: | angličtina |
| Rok vydání: | 2022 |
| Předmět: | |
| Zdroj: | 48th EPS conference on plasma physics 48th EPS conference on plasma physics, Jun 2022, Maastricht (Virtual event), Netherlands |
| Popis: | International audience; The European Transport Simulator (“ETS”) is a suite of codes designed to simulate tokamak plasma discharges. Not only it highlights the evolution of particle density and energy due to transport effects accounting for particle, heat and current sources, but it equally provides insight into fast ion dynamics resulting from ICRH (and - if present – beams), and the impact these high-energy populations have on the plasma core. This tool allows to help understand the plasma dynamics in WEST and is being used for optimizing the plasma discharge. In particular, attention is being devoted to identify means to avoid a radiative collapse by ensuring an efficient electron RF induced heating and to help finding favourable conditions to enable the L-H transition. The first step was to verify and validate the simulator in interpretative and predictive mode for some relevant WEST L-mode plasmas. Cyrano and StixRedist are used as ICRH modules, while transport is assumed to be due to turbulence and is described exploiting the TGLF module. Collisional electron power computed with the ICRF modules was compared with the experimental one obtained by using the Break In Slope method. Scans in minority density and ICRF power were performed in interpretative mode in order to determine the electron/ion heating ratio, revealing dominant electron heating and highlighting that the neutron rate is a sensitive function of the power absorbed by the deuterons. Seeking for the highest possible compatibility between the various available measurements (electron temperature profiles, stored energy and neutron rate) while staying within realistic error bars, predictive modelling which describes the evolution of particle density and temperatures allows to estimate the ion temperature profiles (not yet available on WEST) and to establish a firm link between the WEST experimental data (e.g. energy & neutron rate) on the one hand and the thermal and fast particle profiles resulting from simulation on the other. |
| Databáze: | OpenAIRE |
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