A conceptual design of the International Thermonuclear Experimental Reactor for the Central Solenoid

Conference · Fri Sep 21 00:00:00 EDT 1990

OSTI ID:6474645

Heim, J R; Parker, J M

Conceptual design of the International Thermonuclear Experimental Reactor (ITER) superconducting magnet system is nearing completion by the ITER Design Team, and one of the Central Solenoid (CS) designs is presented. The CS part of this magnet system will be a vertical stack of eight modules, approximately 16 m high, each having a approximate dimensions of: 4.1-m o.d., 2.8-m i.d., 1.9-m h. The peak field at the bore is approximately 13.5 T. Cable-in-conduit conductor with Nb{sub 3}Sn composite wire will be used to wind the coils. The overall coil fabrication will use the insulate-wind-react-impregnate method. Coil modules will be fabricated using double-pancake coils with all splice joints located in the low-field region on the outside of the coils. All coils will be structurally graded with high-strength steel reinforcement which is co-wound with the conductor. We describe details of the CS coil design and analysis.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6474645
• Report Number(s): UCRL-JC-103490; CONF-900944-8; ON: DE91000655; TRN: 91-000100
• Resource Relation: Conference: Applied superconductivity conference, Aspen, CO (USA), 24-28 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
SUPERCONDUCTING MAGNETS
DESIGN
FABRICATION
ITER TOKAMAK
NIOBIUM BASE ALLOYS
TIN ALLOYS
ALLOYS
CLOSED PLASMA DEVICES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
MAGNETS
NIOBIUM ALLOYS
SUPERCONDUCTING DEVICES
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700202* - Fusion Power Plant Technology- Magnet Coils & Fields