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Modeling of resisti...
Modeling of resistive wall mode and its control in experiments and ITER
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- Liu, Yueqiang, 1971 (författare)
- Chalmers tekniska högskola,Chalmers University of Technology
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- Chu, M. S. (författare)
- General Atomics
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- Garofalo, A. M. (författare)
- General Atomics
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visa fler...
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- La Haye, R. J. (författare)
- General Atomics
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Gribov, Y. (författare)
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- Gryaznevich, M. (författare)
- Euratom Ukaea Fusion Association
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- Hender, T. C. (författare)
- Euratom Ukaea Fusion Association
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- Howell, D. F. (författare)
- Euratom Ukaea Fusion Association
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- De Vries, P. (författare)
- Euratom Ukaea Fusion Association
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- Okabayashi, M. (författare)
- Princeton University
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- Pinches, S. D. (författare)
- Max Planck Gesellschaft zur Förderung der Wissenschaften e.V. (MPG),Max Planck Society for the Advancement of Science (MPG)
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- Reimerdes, H. (författare)
- Columbia University in the City of New York
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(creator_code:org_t)
- AIP Publishing, 2006
- 2006
- Engelska.
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Ingår i: Physics of Plasmas. - : AIP Publishing. - 1089-7674 .- 1070-664X. ; 13:5
- Relaterad länk:
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http://dx.doi.org/10...
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https://research.cha...
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https://doi.org/10.1...
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Abstract
Ämnesord
Stäng
- Active control of the resistive wall mode (RWM) for DIII-D [Luxon and Davis, Fusion Technol. 8, 441 (1985)] plasmas is studied using the MARS-F code [Y. Q. Liu, Phys. Plasmas 7, 3681 (2000)]. Control optimization shows that the mode can be stabilized up to the ideal wall beta limit, using the internal control coils (I-coils) and poloidal sensors located at the outboard midplane, in combination with an ideal amplifier. With the present DIII-D power supply model, the stabilization is achieved up to 70% of the range between no-wall and ideal-wall limits. Reasonably good quantitative agreement is achieved between MARS-F simulations and experiments on DIII-D and JET (Joint European Torus) [P. H. Rebut, Nucl. Fusion 25, 1011 (1985)] on critical rotation for the mode stabilization. Dynamics of rotationally stabilized plasmas is well described by a single mode approximation; whilst a strongly unstable plasma requires a multiple mode description. For ITER [R. Aymar, P. Barabaschi, and Y. Shimomura, Plasma Phys. Controlled Fusion 44, 519 (2002)], the MARS-F simulations show the plasma rotation may not provide a robust mechanism for the RWM stabilization in the advanced scenario. With the assumption of ideal amplifiers, and using optimally tuned controllers and sensor signals, the present feedback coil design in ITER allows stabilization of the n=1 RWM for plasma pressures up to 80% of the range between the no-wall and ideal-wall limits.
Ämnesord
- TEKNIK OCH TEKNOLOGIER -- Maskinteknik (hsv//swe)
- ENGINEERING AND TECHNOLOGY -- Mechanical Engineering (hsv//eng)
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- ref (ämneskategori)
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Till lärosätets databas
- Av författaren/redakt...
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Liu, Yueqiang, 1 ...
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Chu, M. S.
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Garofalo, A. M.
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La Haye, R. J.
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Gribov, Y.
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Gryaznevich, M.
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visa fler...
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Hender, T. C.
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Howell, D. F.
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De Vries, P.
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Okabayashi, M.
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Pinches, S. D.
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Reimerdes, H.
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visa färre...
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Chalmers tekniska högskola