Status and Plans for the National Spherical Torus Experimental Research Facility

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Abstract

An overview of the research capabilities and the future plans on the MA-class National Spherical Torus Experiment (NSTX) at Princeton is presented. NSTX research is exploring the scientific benefits of modifying the field line structure from that in more conventional aspect ratio devices, such as the tokamak. The relevant scientific issues pursued on NSTX include energy confinement, MHD stability at high β, non-inductive sustainment, solenoid-free start-up, and power and particle handling. In support of the NSTX research goal, research tools are being developed by the NSTX team. In the context of the fusion energy development path being formulated in the US, an ST-based Component Test Facility (CTF) and, ultimately a high β Demo device based on the ST, are being considered. For these, it is essential to develop high performance (high β and high confinement), steady-state (non-inductively driven) ST operational scenarios and an efficient solenoid-free start-up concept. We will also briefly describe the Next-Step-ST (NSST) device being designed to address these issues in fusion-relevant plasma conditions.

Journal

  • IEEJ Transactions on Fundamentals and Materials

    IEEJ Transactions on Fundamentals and Materials 125(11), 868-880, 2005

    The Institute of Electrical Engineers of Japan

Codes

  • NII Article ID (NAID)
    130000085471
  • NII NACSIS-CAT ID (NCID)
    AN10136312
  • Text Lang
    ENG
  • Article Type
    特集 // 会議録・学会報告
  • ISSN
    0385-4205
  • NDL Article ID
    7690630
  • NDL Source Classification
    ZN31(科学技術--電気工学・電気機械工業)
  • NDL Call No.
    Z16-793
  • Data Source
    NDL  J-STAGE 
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