Superfluid helium bath cooling of a tokamak reactor toroidal field coil system

Technical Report · Wed Jul 01 04:00:00 EDT 1981

OSTI ID:6084197

Hsu, Y H; Purcell, J; Alcorn, J

A conceptual design of a FED reactor compatible toroidal field (TF) coil system employing NbTi alloy conductor and superfluid helium bath cooling is discussed. In order to achieve 11 tesla, NbTi alloy conductor must operate at a temperature below 4.2 K. After a year of comparative analytical and experimental studies, General Atomic has concluded that He II (superfluid) operation may be preferable to subatmospheric, subcooled He I conditions. Some of the features of this system are described.

• Research Organization: General Atomic Co., San Diego, CA (USA)
• DOE Contract Number: AT03-76ET51011
• OSTI ID: 6084197
• Report Number(s): GA-A-16422; ON: DE81028341
• Country of Publication: United States
• Language: English

Related Subjects

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71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
COOLING
CRYOGENICS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ENERGY TRANSFER
EQUIPMENT
EVEN-EVEN NUCLEI
FLUIDS
HEAT TRANSFER
HELIUM 4
HELIUM II
HELIUM ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETS
NUCLEI
QUANTUM FLUIDS
REFRIGERATION
STABLE ISOTOPES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
SUPERFLUIDITY
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS