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Title: Design considerations for ITER (International Thermonuclear Experimental Reactor) magnet systems: Revision 1

Abstract

The International Thermonuclear Experimental Reactor (ITER) is now completing a definition phase as a beginning of a three-year design effort. Preliminary parameters for the superconducting magnet system have been established to guide further and more detailed design work. Radiation tolerance of the superconductors and insulators has been of prime importance, since it sets requirements for the neutron-shield dimension and sensitively influences reactor size. The major levels of mechanical stress in the structure appear in the cases of the inboard legs of the toroidal-field (TF) coils. The cases of the poloidal-field (PF) coils must be made thin or segmented to minimize eddy current heating during inductive plasma operation. As a result, the winding packs of both the TF and PF coils includes significant fractions of steel. The TF winding pack provides support against in-plane separating loads but offers little support against out-of-plane loads, unless shear-bonding of the conductors can be maintained. The removal of heat due to nuclear and ac loads has not been a fundamental limit to design, but certainly has non-negligible economic consequences. We present here preliminary ITER magnet systems design parameters taken from trade studies, designs, and analyses performed by the Home Teams of the four ITER participants,more » by the ITER Magnet Design Unit in Garching, and by other participants at workshops organized by the Magnet Design Unit. The work presented here reflects the efforts of many, but the responsibility for the opinions expressed is the authors'. 4 refs., 3 figs., 4 tabs.« less

Authors:
;
Publication Date:
Research Org.:
Lawrence Livermore National Lab., CA (USA)
OSTI Identifier:
6342856
Report Number(s):
UCRL-98539-Rev.1; CONF-881031-51-Rev.1
ON: DE89006236; TRN: 89-006925
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: 8. topical meeting on technology of fusion energy, Salt Lake City, UT, USA, 9 Oct 1988; 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; 71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; SUPERCONDUCTING MAGNETS; DESIGN; CURRENT DENSITY; ELECTRICAL PROPERTIES; MECHANICAL PROPERTIES; TOKAMAK TYPE REACTORS; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; EQUIPMENT; MAGNETS; PHYSICAL PROPERTIES; SUPERCONDUCTING DEVICES; THERMONUCLEAR REACTORS; 700202* - Fusion Power Plant Technology- Magnet Coils & Fields; 420201 - Engineering- Cryogenic Equipment & Devices

Citation Formats

Henning, C D, and Miller, J R. Design considerations for ITER (International Thermonuclear Experimental Reactor) magnet systems: Revision 1. United States: N. p., 1988. Web.
Henning, C D, & Miller, J R. Design considerations for ITER (International Thermonuclear Experimental Reactor) magnet systems: Revision 1. United States.
Henning, C D, and Miller, J R. 1988. "Design considerations for ITER (International Thermonuclear Experimental Reactor) magnet systems: Revision 1". United States. https://www.osti.gov/servlets/purl/6342856.
@article{osti_6342856,
title = {Design considerations for ITER (International Thermonuclear Experimental Reactor) magnet systems: Revision 1},
author = {Henning, C D and Miller, J R},
abstractNote = {The International Thermonuclear Experimental Reactor (ITER) is now completing a definition phase as a beginning of a three-year design effort. Preliminary parameters for the superconducting magnet system have been established to guide further and more detailed design work. Radiation tolerance of the superconductors and insulators has been of prime importance, since it sets requirements for the neutron-shield dimension and sensitively influences reactor size. The major levels of mechanical stress in the structure appear in the cases of the inboard legs of the toroidal-field (TF) coils. The cases of the poloidal-field (PF) coils must be made thin or segmented to minimize eddy current heating during inductive plasma operation. As a result, the winding packs of both the TF and PF coils includes significant fractions of steel. The TF winding pack provides support against in-plane separating loads but offers little support against out-of-plane loads, unless shear-bonding of the conductors can be maintained. The removal of heat due to nuclear and ac loads has not been a fundamental limit to design, but certainly has non-negligible economic consequences. We present here preliminary ITER magnet systems design parameters taken from trade studies, designs, and analyses performed by the Home Teams of the four ITER participants, by the ITER Magnet Design Unit in Garching, and by other participants at workshops organized by the Magnet Design Unit. The work presented here reflects the efforts of many, but the responsibility for the opinions expressed is the authors'. 4 refs., 3 figs., 4 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/6342856}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Oct 09 00:00:00 EDT 1988},
month = {Sun Oct 09 00:00:00 EDT 1988}
}

Conference:
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