ITER conductor tests. [International Thermonuclear Experimental Reactor (ITER)]

Conference · Mon Oct 21 04:00:00 EDT 1991

OSTI ID:5807568

Shen, S S

The International Thermonuclear Experimental Reactor (ITER) project has just completed the Conceptual Design Activities (CDA) and is proceeding to a five year phase of the Engineering Design Activities (EDA). Meanwhile, an extensive superconducting magnet R D program has also been initiated. The program is deemed necessary to meet needs for both ignition and steady burn of the plasma in ITER. Toroidal-field coils of 12 T and of a large size require high-current niobium-tin superconductors to operate under conditions of high stress, cyclic loading, ac losses, and nuclear heating. As for the poloidal coil systems, the conductors must operate near 40 kA and at more than 13 T in the central solenoids to provide sufficient flux swing for plasma startup and burning. Furthermore, TF magnets need to be made radiation tolerant. Employing advanced insulators, forced-flow cooled magnets should posses high heat-removal capability and sufficient stability.

• Research Organization: Lawrence Livermore National Lab., CA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5807568
• Report Number(s): UCRL-JC-108527; CONF-9110306--3; ON: DE92008622
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700430* -- Fusion Technology-- Magnet Coils & Fields-- (1992-)
ALLOYS
CLOSED PLASMA DEVICES
CRYOGENICS
DESIGN
ELECTRIC CONDUCTORS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
ITER TOKAMAK
MAGNETS
NIOBIUM ALLOYS
NIOBIUM BASE ALLOYS
PERFORMANCE TESTING
SUPERCONDUCTING COILS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TESTING
THERMONUCLEAR DEVICES
TIN ALLOYS
TOKAMAK DEVICES