FED/INTOR critical issues assessment of toroidal field coil options
Technical Report
·
OSTI ID:6614460
This report is an assessment of the TF-coil options generally regarded as appropriate for near-term tokamak reactors such as FED and INTOR, which require peak fields in the 10 to 10 T range, and which feature external equilibrium field coils. The basic TF-coil options reviewed are: forced flow cable-in-conduit; 4.2 K bath-cooled Nb/sub 3/Sn/NbTi cable; superfluid (He II) bath-cooled NbTi cable. Two forced-flow conductor/coolant configurations are reviewed: Nb/sub 3/Sn cable-in-conduit, 4 K outlet to produce 11 to 12 T (INTOR); NbTi cable-inconduit, 3 K outlet to produce 10 T (FED). Also, the 4 K bath-cooled Nb/sub 3/Sn/NbTi monolithic conductor option for FED was reviewed. Toroidal field coil requirements for FED and INTOR are presented. A comparison of cooling, superconductor, and configuration alternatives is presented, independently of specific option configurations. Alternatives discussed are bath cooling vs forced flow; He I vs He II bath; NbTi vs Nb/sub 3/Sn; monolithic vs cabled conductor; distributed vs case support of winding pack and out-of-plane load support. Reference and normalized option configurations are presented. Reference configurations for FED and INTOR are the manifestation of each concept as developed by its originator. (For example, the NbTi cable-in-conduit forced-flow configuration identified by the Design Center staff as the baseline design for FED 81.) In order to provide a mutually consistent basis for comparison of the option configurations, certain normalization adjustments were performed upon the reference FED concepts. The basic TF-coil/cooling/structure option configurations are evaluated as to their relative appropriateness for FED and INTOR. In order to present the assessment in coherent manner, the various aspects are grouped as follows: technology maturity; reactor compatibility; reliability; and cost.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET51011
- OSTI ID:
- 6614460
- Report Number(s):
- GA-A-16896; ON: DE83005703
- Country of Publication:
- United States
- Language:
- English
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Comparative evaluation of existing concepts for a 10-tesla FED toroidal field coil. [Nb-Ti and Nb/sub 3/ Sn-NbTi]
Comparative evaluation of existing concepts for a 10 tesla FED toroidal field coil
Oak Ridge Tokamak experimental power reactor study, 1976. Part 3. Magnet systems
Conference
·
Tue Nov 30 23:00:00 EST 1982
·
OSTI ID:6399003
Comparative evaluation of existing concepts for a 10 tesla FED toroidal field coil
Journal Article
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Sun May 01 00:00:00 EDT 1983
· IEEE Trans. Magn.; (United States)
·
OSTI ID:5746989
Oak Ridge Tokamak experimental power reactor study, 1976. Part 3. Magnet systems
Technical Report
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Mon Jan 31 23:00:00 EST 1977
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OSTI ID:7115582
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700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
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COST
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TECHNOLOGY ASSESSMENT
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