NSTX/NSTX-U theory, modeling and analysis results
作者: S.M. KayeD.J. BattagliaD. BaverE. BelovaJ.W. BerkeryV.N. DuarteN. FerraroE. FredricksonN. GorelenkovW. GuttenfelderG.Z. HaoW. HeidbrinkO. IzacardD. KimI. KrebsR. La HayeJ. LestzD. LiuL.A. MortonJ. MyraD. PfefferleM. PodestaY. RenJ. RiquezesS.A. SabbaghM. SchnellerF. ScottiV. SoukhanovskiiS.J. ZwebenJ.W. AhnJ.P. AllainR. BarchfeldF. BedoyaR.E. BellN. BertelliA. BhattacharjeeM.D. BoyerD. BrennanG. CanalJ. CanikN. CrockerD. Darro
作者单位: 1Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, United States of America
2Lodestar Research Corporation, Boulder, CO, United States of America
3Columbia University, New York, NY, United States of America
4University of California at Irvine, Irvine, CA, United States of America
5Princeton University, Princeton, NJ, United States of America
6General Atomics, San Diego, CA, United States of America
7University of Wisconsin, Madison, WI, United States of America
8Lawrence Livermore National Laboratory, Livermore, CA, United States of America
9Oak Ridge National Laboratory, Oak Ridge, TN 37831, United States of America
10University of Illinois at Urbana-Champaign, Urbana, IL, United States of America
11University of California at Davis, Davis, CA, United States of America
12Massachusetts Institute of Technology, Cambridge, MA, United States of America
13Institute of Physics, University of Sao Paolo, Sao Paolo, Brazil
14University of California at Los Angeles, Los Angeles, CA, United Stat
刊名: Nuclear Fusion, 2019, Vol.59 (11)
来源数据库: Institute of Physics Journal
DOI: 10.1088/1741-4326/ab023a
原始语种摘要: The mission of the spherical tokamak NSTX-U is to explore the physics that drives core and pedestal transport and stability at high- and low collisionality, as part of the development of the spherical tokamak (ST) concept towards a compact, low-cost ST-based pilot plant. NSTX-U will ultimately operate at up to 2 MA and 1 T with up to 12 MW of neutral beam injection power for 5 s. NSTX-U will operate in a regime where electromagnetic instabilities are expected to dominate transport, and beam-heated NSTX-U plasmas will explore a portion of energetic particle parameter space that is relevant for both -heated conventional and low aspect ratio burning plasmas. NSTX-U will also develop the physics understanding and control tools to ramp-up and sustain high performance plasmas in a...
全文获取路径: IOP 

  • develop 发展
  • theory 理论
  • sustain 支持
  • expected 预期
  • operate 操纵
  • tokamak 托卡马克
  • analysis 分析
  • modeling 制祝型
  • understanding 理解
  • divertor 分流偏滤器