Numerical simulation of the stability in a cable-in-conduit conductor developed for fusion-magnet applications

Conference · Wed Sep 25 04:00:00 EDT 1991

OSTI ID:5095099

Wong, R L; Shen, S S ^[1]; Yeaw, C T ^[2]; Miller, J R ^[3]

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1. Lawrence Livermore National Lab., CA (United States)
2. Wisconsin Univ., Madison, WI (United States)
3. National High Magnetic Field Laboratory, Florida State University (USA)

The stability margins of the US-Demonstration Poloidal Coil (US-DPC) and the International Thermonuclear Experimental Reactor (ITER) TF coils have been modeled numerically using the computer program CICC. The computed US-DPC limiting current, I{sub lim}, compares favorably with the values determined experimentally. Using the detailed program CICC output, we investigated the DPC quench initiation mechanism in each of the three stability regions. In the ill-cooled region, the imposed heat pulse heats the conductor to the current-sharing temperature, T{sub cs}. In the transition region, the resistance heating after the pulse must be strong enough to overcome the induced flow reversal. In the well-cooled region, good heat transfer heats the helium during the pulse. After the pulse, these high helium temperatures along with poor heat transfer cause the conductor to quench. Changes in I{sub lim} agree with Dresner's relationship. I{sub lim} can be improved by decreasing the copper resistivity, the helium fraction, or the conductor diameter. Preliminary results show the ITER and TF coil operating point is in the well-cooled region. 10 refs., 7 figs., 1 tab.

• 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: 5095099
• Report Number(s): UCRL-JC-107258; CONF-910968--20; ON: DE92001893
• Country of Publication: United States
• Language: English

Related Subjects

426001 -- Engineering-- Superconducting Devices & Circuits-- (1990-)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
75 CONDENSED MATTER PHYSICS
SUPERCONDUCTIVITY AND SUPERFLUIDITY
CLOSED PLASMA DEVICES
COMPUTERIZED SIMULATION
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ENERGY TRANSFER
EQUIPMENT
HEAT TRANSFER
ITER TOKAMAK
MAGNETS
QUENCHING
SIMULATION
STABILIZED SUPERCONDUCTORS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
SUPERCONDUCTORS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES