Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code
Core-SOL simulations were carried out of plasma in tokamak reactors operating in a low confinement mode (L-mode), for various conditions that match available experimental data. The simulation results were quantitatively compared against experimental data, showing that the average RMS errors for el...
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doaj-1e23fbf938064b94a60a1727137e3e422020-11-24T22:48:11ZengPrince of Songkla UniversitySongklanakarin Journal of Science and Technology (SJST)0125-33952014-04-01362217225Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR codeYutthapong Pinanroj0Thawattchai Onjun1Program in Industrial Management Technology, Faculty of Sciences and Industrial Technology, Prince of Songkla University, Surat Thani Campus, Mueang, Surat Thani, 84000 Thailand.School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology, Thammasat University, Khlong Luang, Pathum Thani, 12121 Thailand.Core-SOL simulations were carried out of plasma in tokamak reactors operating in a low confinement mode (L-mode), for various conditions that match available experimental data. The simulation results were quantitatively compared against experimental data, showing that the average RMS errors for electron temperature, ion temperature, and electron density were lower than 16% or less for 14 L-mode discharges from two tokamaks named DIII-D and TFTR. In the simulations, the core plasma transport was described using a combination of neoclassical transport calculated by NCLASS module and anomalous transport by Multi-Mode-Model version 2001 (MMM2001). The scrape-off-layer (SOL) is the small amount of residual plasma that interacts with the tokamak vessel, and was simulated by integrating the fluid equations, including sources, along open field lines. The SOL solution provided the boundary conditions of core plasma region on low confinement mode (L-mode). The experimental data were for 14 L-mode discharges and from two tokamaks, named DIII-D and TFTR.http://rdo.psu.ac.th/sjstweb/journal/36-2/36-2-11.pdftokamakfusionL-modeSOLand tokamak plasma |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Yutthapong Pinanroj Thawattchai Onjun |
spellingShingle |
Yutthapong Pinanroj Thawattchai Onjun Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code Songklanakarin Journal of Science and Technology (SJST) tokamak fusion L-mode SOL and tokamak plasma |
author_facet |
Yutthapong Pinanroj Thawattchai Onjun |
author_sort |
Yutthapong Pinanroj |
title |
Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code |
title_short |
Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code |
title_full |
Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code |
title_fullStr |
Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code |
title_full_unstemmed |
Core-SOL simulations of L-mode tokamak plasma discharges using BALDUR code |
title_sort |
core-sol simulations of l-mode tokamak plasma discharges using baldur code |
publisher |
Prince of Songkla University |
series |
Songklanakarin Journal of Science and Technology (SJST) |
issn |
0125-3395 |
publishDate |
2014-04-01 |
description |
Core-SOL simulations were carried out of plasma in tokamak reactors operating in a low confinement mode (L-mode),
for various conditions that match available experimental data. The simulation results were quantitatively compared against
experimental data, showing that the average RMS errors for electron temperature, ion temperature, and electron density were
lower than 16% or less for 14 L-mode discharges from two tokamaks named DIII-D and TFTR. In the simulations, the core
plasma transport was described using a combination of neoclassical transport calculated by NCLASS module and anomalous
transport by Multi-Mode-Model version 2001 (MMM2001). The scrape-off-layer (SOL) is the small amount of residual
plasma that interacts with the tokamak vessel, and was simulated by integrating the fluid equations, including sources, along
open field lines. The SOL solution provided the boundary conditions of core plasma region on low confinement mode
(L-mode). The experimental data were for 14 L-mode discharges and from two tokamaks, named DIII-D and TFTR. |
topic |
tokamak fusion L-mode SOL and tokamak plasma |
url |
http://rdo.psu.ac.th/sjstweb/journal/36-2/36-2-11.pdf |
work_keys_str_mv |
AT yutthapongpinanroj coresolsimulationsoflmodetokamakplasmadischargesusingbaldurcode AT thawattchaionjun coresolsimulationsoflmodetokamakplasmadischargesusingbaldurcode |
_version_ |
1725679168203522048 |