Results of Compact Stellarator engineering trade studies
Name
Brown-2009-Results of compact stellarator engineering trade studies.pdf
Size
1.22 MB
Format
Adobe PDF
Checksum (MD5)
37d762b15ac22496399f85ead2afb0a0
Author(s)
Bromberg, Leslie
Cole, M.
Brown, T.
Date Issued
August 2009
Journal
23rd IEEE/NPSS Symposium on Fusion Engineering, 2009. SOFE 2009.
Publisher
Institute of Electrical and Electronics Engineers
Citation
Brown, T., L. Bromberg, and M. Cole. “Results of Compact Stellarator engineering trade studies.” Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on. 2009. 1-4. © 2009 IEEE
Version
Final published version
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.
MIT Department
Massachusetts Institute of Technology. Plasma Science and Fusion Center
Terms of Use
Article is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.
Persistent DSpace Link
DOI of Published Version
http://dx.doi.org/10.1109/FUSION.2009.5226447
