Development of the PARASOL Code and Full Particle Simulation of Tokamak Plasma with an Open-Field SOL-Divertor Region Using PARASOL

T. TAKIZUKA

Plasma Science and Technology > 2011 > 13(3): 316-325.

T. TAKIZUKA. Development of the PARASOL Code and Full Particle Simulation of Tokamak Plasma with an Open-Field SOL-Divertor Region Using PARASOL[J]. Plasma Science and Technology, 2011, 13(3): 316-325.

Citation:

PDF (12160 KB)

Development of the PARASOL Code and Full Particle Simulation of Tokamak Plasma with an Open-Field SOL-Divertor Region Using PARASOL

T. TAKIZUKA(T. TAKIZUKA)

Japan Atomic Energy Agency, Naka Fusion Institute, Naka 311-0193, Japan

Funds: supported partly by the JSPS-CAS Core-University Program in the ¯eld of `Plasma and Nuclear Fusion', and partly by the Grant-in-Aid for Scienti¯c Research of Japan Society for the Promotion of Science

More Information

Received Date: October 04, 2010

Graphical Abstract

Abstract

Abstract

The PARASOL code and the simulation by using PARASOL are introduced briefly. The PARASOL code with particle-in-cell (PIC) method and binary collision model was developed in JAERI and JAEA. Simulations using PARASOL code were carried out in order to investigate the power and particle control with diveror system in fusion reactors. The one-dimensional (1D) version of PARASOL was adopted to investigate the Bohm criterion, the supersonic flow, the SOL heat conduction, and so on. The heat propagation due to edge localized mode (ELM) was studied with the 1D-dynamic PARASOL. The two-dimensional version of PARASOL for the whole tokamak plasma including scrape-off-layer (SOL)-divertor region was useful for simulating the SOL °ow pattern, the electric ¯eld formation etc. Based on PARASOL simulation results, improved physics modeling for the °uid simulation was built up.
- tokamak plasma,
- scrape-off layer,
- divertor,
- sheath,
- heat transport,
- plasma flow,
- radial electric field,
- particle simulation,
- collision model

FullText(HTML)

References (0)

[1]	Wenjia WANG (王文家), Deng ZHOU (周登), Yue MING (明玥). The residual zonal flow in tokamak plasmas with a poloidal electric field[J]. Plasma Science and Technology, 2019, 21(1): 15101-015101. DOI: 10.1088/2058-6272/aadd8e
[2]	Wei YOU (尤玮), Hong LI (李弘), Wenzhe MAO (毛文哲), Wei BAI (白伟), Cui TU (涂翠), Bing LUO (罗兵), Zichao LI (李子超), Yolbarsop ADIL (阿迪里江), Jintong HU (胡金童), Bingjia XIAO (肖炳甲), Qingxi YANG (杨庆喜), Jinlin XIE (谢锦林), Tao LAN (兰涛), Adi LIU (刘阿娣), Weixing DING (丁卫星), Chijin XIAO (肖持进), Wandong LIU (刘万东). Design of the poloidal field system for KTX[J]. Plasma Science and Technology, 2018, 20(11): 115601. DOI: 10.1088/2058-6272/aac8d5
[3]	Xudong WANG (王旭东), Liuwei XU (许留伟), Peng FU (傅鹏), Ji LI (李冀), Yanan WU (吴亚楠). Harmonics analysis of the ITER poloidal field converter based on a piecewise method[J]. Plasma Science and Technology, 2017, 19(12): 125602. DOI: 10.1088/2058-6272/aa86a5
[4]	YUAN Hongwen (袁红文), FU Peng (傅鹏), GAO Ge (高格), HUANG Liansheng (黄连生), SONG Zhiquan (宋执权), HE Shiying (何诗英), WU Yanan (吴亚楠), DONG Lin (董琳), WANG Min (王敏), FANG Tongzhen (房同珍). On the Sequential Control of ITER Poloidal Field Converters for Reactive Power Reduction[J]. Plasma Science and Technology, 2014, 16(12): 1147-1152. DOI: 10.1088/1009-0630/16/12/11
[5]	LI Jinchao(李金超), Song Zhiquan(宋执权), XU Liuwei(许留伟), FU Peng(傅鹏), GUO Bin(郭斌), LI Sen(李森), DONG Lin(董琳), WANG Min(王敏). Current Sharing Analysis of Arm Prototype for ITER PF Converter Bridge[J]. Plasma Science and Technology, 2014, 16(3): 283-287. DOI: 10.1088/1009-0630/16/3/20
[6]	LI Weixin (李炜昕), YUAN Zhensheng (袁振圣), WU Wenjing (武文晶), CHEN Zhenmao (陈振茂). Numerical Analysis on the Magneto-Elastic Stability of Current -Carrying Conductors: Aiming at Applications for the Tokamak System[J]. Plasma Science and Technology, 2013, 15(2): 175-178. DOI: 10.1088/1009-0630/15/2/20
[7]	ZHU Zhe (朱哲), ZHU Yinfeng (朱银锋), HUANG Ronglin (黄荣林), FU Peng (傅鹏), DING Yixiao(丁逸骁). Study on the Current-sharing Control System of the TF Power Supply for a Superconducting Tokamak[J]. Plasma Science and Technology, 2012, 14(10): 941-946. DOI: 10.1088/1009-0630/14/10/16
[8]	Long Feng(龙风), Liu Fang(刘方), Wu Yu(武玉), Ni Zhipeng(倪志鹏). The First Benchmarking of ITER BR Nb3Sn Strand of CNDA[J]. Plasma Science and Technology, 2012, 14(9): 847-849. DOI: 10.1088/1009-0630/14/9/14
[9]	CHEN Peng, FU Peng, SONG Zhiquan. An Improvement on Current Sharing Characteristics of Poloidal Field (PF) AC-DC Converters[J]. Plasma Science and Technology, 2011, 13(4): 497-501.
[10]	LIU Bo, WU Yu. Test and Analysis of China's First Short Conductor Sample for ITER Toroidal Field Coils[J]. Plasma Science and Technology, 2011, 13(1): 106-110.