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Title: Design and analysis of a superconducting cable-in-conduit test coil for operation at 15 T and 40 Ater dot mm sup -2

Abstract

The International Thermonuclear Experimental Reactor (ITER) Design Team may use coil current densities as high as 40 A{center dot}mm{sup -2} and peak magnetic fields of 12--15 T to size superconducting coils in a tokamak reactor design. To verify that these values are within the present superconducting magnet technology state-of-the-art, we are building a Proof of Principles (PoP) test coil. The PoP will be inserted into the bore of an existing High-Field Test Facility Solenoid magnet at LLNL. The PoP insert will be a solenoid coil with approximate dimensions of: 1-m, outside diameter; 0.5-m, inside diameter; about 0.5-m, height. The overall coil fabrication will use the insulate-wind-react-impregnate method. The quartz-cloth-tape insulation material will be wrapped onto the conductor as part of the coil-winding process. The coil will be layer-wound using cable-in-conduit conductor (CICC) with all splices and connections located at the coil ends. The Ti-modified, internal-tin process, MF-Nb{sub 3}Sn technique will be used to produce the superconducting composite wire for the CICC. After reaction, the epoxy component of the insulation system will be added by vacuum impregnation. We describe details of the coil design and analysis and relate them to needs within the engineering data base supporting the design of magnetmore » systems for ITER. 5 refs., 8 figs., 1 tab.« less

Authors:
; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
DOE/DP
OSTI Identifier:
5396219
Report Number(s):
UCRL-100532; CONF-890850-3
ON: DE90002812
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: 11. international conference on magnet technology, Tsukuba (Japan), 28 Aug - 1 Sep 1989
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND SUPERFLUIDITY; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; ELECTROMAGNETS; SUPERCONDUCTING COILS; RESEARCH PROGRAMS; CURRENT DENSITY; THERMONUCLEAR REACTORS; ALLOYS; DESIGN; GEOMETRY; INTERNATIONAL COOPERATION; JAPAN; MATHEMATICAL MODELS; PERFORMANCE; SOLENOIDS; SPECIFICATIONS; TESTING; ASIA; COOPERATION; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; MAGNETS; MATHEMATICS; 700202* - Fusion Power Plant Technology- Magnet Coils & Fields; 426001 - Engineering- Superconducting Devices & Circuits- (1990-); 990200 - Mathematics & Computers

Citation Formats

Heim, J. R., Shen, S. S., Patrick, R. E., Miller, J. R., Chaplin, M. R., Kerns, J. A., Wong, R. L., Slack, D. S., and Summers, L. T. Design and analysis of a superconducting cable-in-conduit test coil for operation at 15 T and 40 Ater dot mm sup -2. United States: N. p., 1989. Web.
Heim, J. R., Shen, S. S., Patrick, R. E., Miller, J. R., Chaplin, M. R., Kerns, J. A., Wong, R. L., Slack, D. S., & Summers, L. T. Design and analysis of a superconducting cable-in-conduit test coil for operation at 15 T and 40 Ater dot mm sup -2. United States.
Heim, J. R., Shen, S. S., Patrick, R. E., Miller, J. R., Chaplin, M. R., Kerns, J. A., Wong, R. L., Slack, D. S., and Summers, L. T. 1989. "Design and analysis of a superconducting cable-in-conduit test coil for operation at 15 T and 40 Ater dot mm sup -2". United States. https://www.osti.gov/servlets/purl/5396219.
@article{osti_5396219,
title = {Design and analysis of a superconducting cable-in-conduit test coil for operation at 15 T and 40 Ater dot mm sup -2},
author = {Heim, J. R. and Shen, S. S. and Patrick, R. E. and Miller, J. R. and Chaplin, M. R. and Kerns, J. A. and Wong, R. L. and Slack, D. S. and Summers, L. T.},
abstractNote = {The International Thermonuclear Experimental Reactor (ITER) Design Team may use coil current densities as high as 40 A{center dot}mm{sup -2} and peak magnetic fields of 12--15 T to size superconducting coils in a tokamak reactor design. To verify that these values are within the present superconducting magnet technology state-of-the-art, we are building a Proof of Principles (PoP) test coil. The PoP will be inserted into the bore of an existing High-Field Test Facility Solenoid magnet at LLNL. The PoP insert will be a solenoid coil with approximate dimensions of: 1-m, outside diameter; 0.5-m, inside diameter; about 0.5-m, height. The overall coil fabrication will use the insulate-wind-react-impregnate method. The quartz-cloth-tape insulation material will be wrapped onto the conductor as part of the coil-winding process. The coil will be layer-wound using cable-in-conduit conductor (CICC) with all splices and connections located at the coil ends. The Ti-modified, internal-tin process, MF-Nb{sub 3}Sn technique will be used to produce the superconducting composite wire for the CICC. After reaction, the epoxy component of the insulation system will be added by vacuum impregnation. We describe details of the coil design and analysis and relate them to needs within the engineering data base supporting the design of magnet systems for ITER. 5 refs., 8 figs., 1 tab.},
doi = {},
url = {https://www.osti.gov/biblio/5396219}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Aug 24 00:00:00 EDT 1989},
month = {Thu Aug 24 00:00:00 EDT 1989}
}

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