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Discussion About the Size of a Future Fusion Demonstration Reactor: The Impact of the Toroidal Magnetic Field
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...
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Published in: | IEEE transactions on applied superconductivity 2007-06, Vol.17 (2), p.1342-1347 |
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Main Authors: | , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
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Summary: | 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 B t , 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 B t will be compared in terms of volume, radial extension for the toroidal field magnet inner leg, central solenoid available flux swing and investment cost. |
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ISSN: | 1051-8223 1558-2515 |
DOI: | 10.1109/TASC.2007.898465 |