Discussion About the Size of a Future Fusion Demonstration Reactor: The Impact of the Toroidal Magnetic Field
| Autor: | J. Johner, J.L. Duchateau, P. Hertout |
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| Rok vydání: | 2007 |
| Předmět: |
Physics
Thermonuclear fusion Tokamak Toroid Power station Nuclear engineering Magnetic confinement fusion Solenoid Superconducting magnet Condensed Matter Physics Electronic Optical and Magnetic Materials law.invention Nuclear physics Physics::Plasma Physics law Magnet Electrical and Electronic Engineering |
| Zdroj: | IEEE Transactions on Applied Superconductivity. 17:1342-1347 |
| ISSN: | 1051-8223 |
| Popis: | In parallel to ITER preparation, power plant conceptual studies have been carried out in Europe as a guideline for the main design parameters of a fusion demonstration reactor, the construction of which is scheduled to start twenty years hence. A key component of this fusion demonstration reactor is the superconducting magnetic system, which represents in ITER 30% of the investment cost. A high toroidal confinement field Bt, can help to moderate the major radius of the tokamak, and thereby the investment cost of the machine. Two versions of such a demonstration reactor, with different values of Bt will be compared in terms of volume, radial extension for the toroidal field magnet inner leg, central solenoid available flux swing and investment cost. |
| Databáze: | OpenAIRE |
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