Superconducting coil design for Large Helical Devices

Conference · Fri Mar 01 04:00:00 EST 1991 · IEEE Transactions on Magnetics (Institute of Electrical and Electronics Engineers); (United States)

OSTI ID:6088554

Yamamoto, J; Motojima, O; Satow, T; Mito, T ^[1]

---

1. National Inst. for Fusion Science, Furocho, Chikusa, Nagoya 464-01 (JP)

This paper reports that as a next inter-university magnetic confined fusion research device, a fully superconducting Large Helical Device will be constructed in a 7 year project from 1990. Major and minor radius of the helical coil is 3.9 m and 0.975 m, respectively. The helical coil is made of pool cooled conductor, and its conductor experienced field is 7.2 T at Phase I, and 9.6 T at Phase II. Three pairs of poloidal coils are also superconducting. Both coils will be made of NbTi conductor.

• OSTI ID: 6088554
• Report Number(s): CONF-900944--
• Conference Information: Journal Name: IEEE Transactions on Magnetics (Institute of Electrical and Electronics Engineers); (United States) Journal Volume: 27:2
• Country of Publication: United States
• Language: English

Related Subjects

665412* -- Superconducting Devices-- (1992-)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700430 -- Fusion Technology-- Magnet Coils & Fields-- (1992-)
75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
ALLOYS
CLOSED PLASMA DEVICES
CONFIGURATION
CONSTRUCTION
DESIGN
ELECTRIC CONDUCTIVITY
ELECTRICAL PROPERTIES
HELICAL CONFIGURATION
NIOBIUM ALLOYS
PHYSICAL PROPERTIES
SUPERCONDUCTING COILS
SUPERCONDUCTIVITY
THERMONUCLEAR DEVICES
TITANIUM ALLOYS