• DocumentCode
    3200525
  • Title

    Results of Compact Stellarator engineering trade studies

  • Author

    Brown, T. ; Bromberg, L. ; Cole, M.

  • Author_Institution
    Princeton Plasma Phys. Lab., Princeton, NJ, USA
  • fYear
    2009
  • fDate
    1-5 June 2009
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    A number of technical requirements and performance criteria can drive stellarator costs, e.g., tight tolerances, accurate coil positioning, low aspect ratio (compactness), choice of assembly strategy, metrology, and complexity of the stellarator coil geometry. With the completion of a seven-year design and construction effort of the National Compact Stellarator Experiment (NCSX) it is useful to interject the NCSX experience along with the collective experiences of the NCSX stellarator community to improving the stellarator configuration. Can improvements in maintenance be achieved by altering the stellarator magnet configuration with changes in the coil shape or with the combination of trim coils? Can a mechanical configuration be identified that incorporates a partial set of shaped fixed stellarator coils along with some removable coil set to enhance the overall machine maintenance? Are there other approaches that will simplify the concepts, improve access for maintenance, reduce overall cost and improve the reliability of a stellarator based power plant? Using ARIES-CS and NCSX as reference cases, alternative approaches have been studied and developed to show how these modifications would favorably impact the stellarator power plant and experimental projects. The current status of the alternate stellarator configurations being developed will be described and a comparison made to the recently designed and partially built NCSX device and the ARIES-CS reactor design study.
  • Keywords
    fusion reactor design; nuclear power stations; nuclear reactor maintenance; stellarators; superconducting coils; superconducting magnets; ARIES-CS reactor design; NCSX; National Compact Stellarator Experiment; coil positioning; compact stellarator engineering trade; machine maintenance; mechanical configuration; metrology; shaped fixed stellarator coils; stellarator based power plant; stellarator coil geometry; stellarator configuration; stellarator magnet configuration; tight tolerances; trim coils; Assembly; Availability; Coils; Costs; Fusion reactor design; Laboratories; Maintenance; Plasmas; Power generation; Tokamaks;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    978-1-4244-2635-5
  • Electronic_ISBN
    978-1-4244-2636-2
  • Type

    conf

  • DOI
    10.1109/FUSION.2009.5226447
  • Filename
    5226447