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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Bibliographic Details
Main Authors: Yutthapong Pinanroj, Thawattchai Onjun
Format: Article
Language:English
Published: Prince of Songkla University 2014-04-01
Series:Songklanakarin Journal of Science and Technology (SJST)
Subjects:
SOL
Online Access:http://rdo.psu.ac.th/sjstweb/journal/36-2/36-2-11.pdf
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spelling 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
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