MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis

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Description

Two versions of the Fusion Engineering Design Center (FEDC) free-boundary equilibrium code designed to computer the poloidal field (PF) coil current distribution of elongated, magnetically limited tokamak plasmas are demonstrated and applied to the systems analysis of the impact of plasma elongation on the design point of the International Thermonuclear Experimental Reactor (ITER). These notes were presented at the ITER Specialists' Meeting on the PF Coil System and Operational Scenario, held at the Max Planck Institute for Plasma Physics in Garching, Federal Republic of Germany, May 24--27, 1988. 8 refs., 6 figs., 4 tabs.

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Pages: 26

Creation Information

Strickler, D.J.; Galambos, J.D. & Peng, Y.K.M. March 1, 1989.

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Description

Two versions of the Fusion Engineering Design Center (FEDC) free-boundary equilibrium code designed to computer the poloidal field (PF) coil current distribution of elongated, magnetically limited tokamak plasmas are demonstrated and applied to the systems analysis of the impact of plasma elongation on the design point of the International Thermonuclear Experimental Reactor (ITER). These notes were presented at the ITER Specialists' Meeting on the PF Coil System and Operational Scenario, held at the Max Planck Institute for Plasma Physics in Garching, Federal Republic of Germany, May 24--27, 1988. 8 refs., 6 figs., 4 tabs.

Physical Description

Pages: 26

Notes

NTIS, PC A03/MF A01 - OSTI; 1.

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  • Other Information: Portions of this document are illegible in microfiche products

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  • Other: DE89012902
  • Report No.: ORNL/FEDC-88/7
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/6244555 | External Link
  • Office of Scientific & Technical Information Report Number: 6244555
  • Archival Resource Key: ark:/67531/metadc1108752

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • March 1, 1989

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • March 20, 2018, 5:59 p.m.

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Strickler, D.J.; Galambos, J.D. & Peng, Y.K.M. MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis, report, March 1, 1989; United States. (digital.library.unt.edu/ark:/67531/metadc1108752/: accessed July 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.