MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- OSTI Identifier:
- 6244555
- Report Number(s):
- ORNL/FEDC-88/7
ON: DE89012902
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; POLOIDAL FIELD DIVERTORS; DESIGN; TOKAMAK TYPE REACTORS; SYSTEMS ANALYSIS; CALCULATION METHODS; COST; MHD EQUILIBRIUM; OPTIMIZATION; PERFORMANCE; DIVERTORS; EQUILIBRIUM; THERMONUCLEAR REACTORS; 700202* - Fusion Power Plant Technology- Magnet Coils & Fields
Citation Formats
Strickler, D J, Galambos, J D, and Peng, Y K.M. MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis. United States: N. p., 1989.
Web. doi:10.2172/6244555.
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. United States. https://doi.org/10.2172/6244555
Strickler, D J, Galambos, J D, and Peng, Y K.M. 1989.
"MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis". United States. https://doi.org/10.2172/6244555. https://www.osti.gov/servlets/purl/6244555.
@article{osti_6244555,
title = {MHD equilibrium methods for ITER (International Thermonuclear Experimental Reactor) PF (poloidal field) coil design and systems analysis},
author = {Strickler, D J and Galambos, J D and Peng, Y K.M.},
abstractNote = {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.},
doi = {10.2172/6244555},
url = {https://www.osti.gov/biblio/6244555},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Mar 01 00:00:00 EST 1989},
month = {Wed Mar 01 00:00:00 EST 1989}
}
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