Progress toward commissioning and plasma operation in NSTX-U
作者: M. OnoJ. ChrzanowskiL. DudekS. GerhardtP. HeitzenroederR. KaitaJ.E. MenardE. PerryT. StevensonR. StrykowskyP. TitusA. von HalleM. WilliamsN.D. AtnafuW. BlanchardM. CropperA. DialloD.A. GatesR. EllisK. EricksonJ. HoseaR. HatcherS.Z. JurczynskiS. KayeG. LabikJ. LawsonB. LeBlancR. MaingiC. NeumeyerR. RamanS. RaftopoulosR. RamakrishnanA.L. RoquemoreS.A. SabbaghP. SichtaH. SchneiderM. SmithB. StrattonV. SoukhanovskiiG. TaylorK. Trese
作者单位: 1Princeton Plasma Physics Laboratory, PO Box 451, Princeton, NJ 08543, USA
2University of Washington at Seattle, Seattle, WA 98195, USA
3Columbia University, New York, NY 10027, USA
4Lawrence Livermore National Laboratory, Livermore, CA 94551, USA
刊名: Nuclear Fusion, 2015, Vol.55 (7)
来源数据库: Institute of Physics Journal
DOI: 10.1088/0029-5515/55/7/073007
原始语种摘要: The National Spherical Torus Experiment-Upgrade (NSTX-U) is the most powerful spherical torus facility at PPPL, Princeton USA. The major mission of NSTX-U is to develop the physics basis for an ST-based Fusion Nuclear Science Facility (FNSF). The ST-based FNSF has the promise of achieving the high neutron fluence needed for reactor component testing with relatively modest tritium consumption. At the same time, the unique operating regimes of NSTX-U can contribute to several important issues in the physics of burning plasmas to optimize the performance of ITER. NSTX-U further aims to determine the attractiveness of the compact ST for addressing key research needs on the path toward a fusion demonstration power plant (DEMO). The upgrade will nearly double the toroidal magnetic field B ... to 1 T at a major radius of R 0 = 0.93 m, plasma current I p to 2 MA and neutral beam injection (NBI) heating power to 14 MW. The anticipated plasma performance enhancement is a quadrupling of the plasma stored energy and near doubling of the plasma confinement time, which would result in a 5–10 fold increase in the fusion performance parameter n τ T . A much more tangential 2nd NBI system, with 2–3 times higher current drive efficiency compared to the 1st NBI system, is installed to attain the 100% non-inductive operation needed for a compact FNSF design. With higher fields and heating powers, the NSTX-U plasma collisionality will be reduced by a factor of 3–6 to help explore the favourable trend in transport towards the low collisionality FNSF regime. The NSTX-U first plasma is planned for the Summer of 2015, at which time the transition to plasma operations will occur.
全文获取路径: IOP 

  • operation 运算
  • commissioning 投入运行
  • plasma 深绿玉髓
  • toward 
  • promise 允诺
  • attractiveness 吸引性
  • system 
  • National 国民牌大客车
  • consumption 消耗
  • installed 安装