Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER
作者: T. EichA.W. LeonardR.A. PittsW. FundamenskiR.J. GoldstonT.K. GrayA. HerrmannA. KirkA. KallenbachO. KardaunA.S. KukushkinB. LaBombardR. MaingiM.A. MakowskiA. ScarabosioB. SieglinJ. TerryA. ThorntonASDEX Upgrade TeamJET EFDA Contributors
作者单位: 1JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK
2Max-Planck-Institut für Plasma Physik, Boltzmannstr.2, 85748 Garching, Germany
3General Atomics, PO Box 85608, San Diego, CA 92186-5608, USA
4ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France
5CCFE, EURATOM-Association, Culham Science Centre, Abingdon,UK
6Princeton, Plasma Physics Laboratory, Princeton, NJ 08543,USA
7Oak Ridge National Laboratory, Oak Ridge, TN 37831, USA
8MIT Plasma Science and Fusion Center, Cambridge, MA 02139,USA
9Lawrence Livermore National Laboratory, Livermore, CA 94551,USA
刊名: Nuclear Fusion, 2013, Vol.53 (9)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/53/9/093031
原始语种摘要: A multi-machine database for the H-mode scrape-off layer power fall-off length, λ q in JET, DIII-D, ASDEX Upgrade, C-Mod, NSTX and MAST has been assembled under the auspices of the International Tokamak Physics Activity. Regression inside the database finds that the most important scaling parameter is the poloidal magnetic field (or equivalently the plasma current), with λ q decreasing linearly with increasing B pol. For the conventional aspect ratio tokamaks, the regression finds , yielding λ q ,ITER ≅ 1 mm for the baseline inductive H-mode burning plasma scenario at I p = 15 MA. The experimental divertor target heat flux profile data, from which λ q is derived, also yield a divertor power spreading factor ( S )...
全文获取路径: IOP 
分享到:

×
关键词翻译
关键词翻译
  • tokamak 托卡马克
  • database 资料库
  • width 幅度
  • scaling 按比例缩小
  • scrape 擦过
  • agreement 协议
  • divertor 分流偏滤器
  • power 功率
  • aspect 季相
  • layer