Performance of cable-in-conduit conductors in ITER (International Thermonuclear Experimental Reactor) toroidal field coils with varying heat loads
Conference
·
OSTI ID:5537110
The toroidal field (TF) coils in the International Thermonuclear Experimental Reactor (ITER) will operate with varying heat loads generated by ac losses and nuclear heating. The total heat load is estimated to be 2 kW per TF coil under normal operation and can be higher for different operating scenarios. Ac losses are caused by ramping the poloidal field (PF) for plasma initiation, burn, and shutdown; nuclear heating results from neutrons that penetrate into the coil past the shield. Present methods to reduce or eliminate these losses lead to larger and more expensive machines, which are unacceptable with today's budget constraints. A suitable solution is to design superconductors that operate with high heat loads. The cable-in-conduit conductor (CICC) can operate with high heat loads. One CICC design is analyzed for its thermal performance using two computer codes developed at LLNL. One code calculates the steady state flow conditions along the flow path, while the other calculates the transient conditions in the flow. We have used these codes to analyze the superconductor performance during the burn phase of the ITER plasma. The results of these analyses give insight to the choice of flow rate on superconductor performance. 4 refs., 5 figs.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5537110
- Report Number(s):
- UCRL-101136; CONF-891007--15; ON: DE90001514
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
CABLES
CLOSED PLASMA DEVICES
CONDUCTOR DEVICES
DESIGN
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
ITER TOKAMAK
MAGNETS
PERFORMANCE
SUPERCONDUCTING CABLES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TEMPERATURE EFFECTS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700202* -- Fusion Power Plant Technology-- Magnet Coils & Fields
CABLES
CLOSED PLASMA DEVICES
CONDUCTOR DEVICES
DESIGN
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
ITER TOKAMAK
MAGNETS
PERFORMANCE
SUPERCONDUCTING CABLES
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TEMPERATURE EFFECTS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES