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Fusion Science and Technology Volume 47, 2005 - Issue 3
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Technical Paper

Attractive Design Approaches for a Compact Stellarator Power Plant

A. R. RaffrayMechanical and Aerospace Engineering Department and Center for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA
,
L. El-GuebalyUniversity of Wisconsin, Fusion Technology Institute, Madison, WI 53706, USA
,
S. MalangFusion Nuclear Technology Consulting, Fliederweg 3, 76351 Linkenheim, Germany
,
X. WangCenter for Energy Research, 460 EBU-II, University of California-San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0438, USA
& ARIES Team
Pages 422-431 | Published online: 07 Apr 2017

References

  • G. H. Neilson, L. A. Berry, A. Brooks, et al., “Design of the National Compact Stellarator Experiment (NCSX)”, Fusion Engineering and Design, 66-68, 169 (2003).
  • P. R. Garabedian, “Compact Stellarators with Modular Coils”, Applied Physical Sciences, 97, 8211 (2000).
  • X. R. Wang, S. Malang, A. R. Raffray (and) the ARIES Team, “Maintenance Approaches for ARIES-CS Power Core,” this issue.
  • R. L. Miller, F. Najmabadi, X. Wang, D. K. Sze, et al., “Stellarator power plant study,” Final Report, UCSD-ENG-004 (19997).
  • G. Bohme, L. A. EL-Guebaly, and G. A. Emmer et al., “Studies of a modular advanced stellarator ASRA6C,” KfK 4268, FPA-87-2, IPP 2/285.
  • C. D. Beidler, E. Harmeyer, etal., “The (H)elias reactor HSR4/18,” Nuclear Fusion, 41, 12 (2001).
  • A. R. Raffray, M. Akiba, V. Chuyanov, L. Giancarli, and S. Malang, “Breeding Blanket Concepts for Fusion and Materials Requirements”, Journal of Nuclear Materials, 307-311, 21 (2002).
  • L. El-Guebaly, et al., and the ARIES (T)eam, “Benefits of Radial Build Minimization and Requirements imposed on ARIES Compact Stellarator Design,” this issue.
  • A. Sagara, et al., “Design and Development of the Flibe Blanket for Helical-Type Fusion Reactor FFHR”, Fusion Engineering & Design, 49-50, 551 (2000).
  • S. J. Zinkle, N. M. Ghoniem, “Operating (T)emperature Windows for Fusion Reactors Structural Materials” Fusion Engineering and Design, 51-52, 55 (2000).
  • A. R. Raffray, et al., and the ARIES Team, “High Performance Blanket for ARIES-AT (P)ower Plant”, Fusion Engineering and Design, 58-59, 549–553 (2001).
  • R. Schleicher, A. R. Raffray, C. P. (Wong), “An Assessment of the Brayton Cycle for High Performance Power Plant”, Fusion Technology, 39 (2), 823-827 (March 2001).
  • Available at http://aries.ucsd.edu/LIB/REPORT/ARIES-(ST)/final.shtml
  • S. Malang, M. S. Tillack (eds.), “Development of Self-Cooled Liquid Metal (B)lankets,” FZK report, FZKA 5581 (1995).
  • S. Hermsmeyer, et al., “Improved Helium (C)ooled Pebble Bed Blanket,” FZK report, (FZKA) 6399, Karlsruhe, Germany (Dec. 1999).
  • R. Raffray, S. Malang, L. El-Guebaly, X. Wang, and the ARIES Team, “Ceramic Breeder Blanket for ARIES-CS,” this issue.

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