Equilibrium and vertical-instability considerations for vertical strike-point shifts on the ITER divertor targets

The study of operation with raised strike points on the first ITER divertor target plates is motivated by the need to gain experience with operation with strike points on tungsten (W) surfaces during the non-active phases (in the case of an initial carbon fibre composite (CFC)/W divertor); or (if IT...

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Bibliographic Details
Published in:Nuclear fusion 2013-08, Vol.53 (8), p.83021-11
Main Authors: Kolesnikov, R.A., Bulmer, R.H., LoDestro, L.L., Casper, T.A., Pitts, R.A.
Format: Article
Language:English
Subjects:
70 PLASMA PHYSICS AND FUSION
Chlorofluorocarbons
Damage
Gain
Nuclear fusion
Phases
Plasma currents
Strikes
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Summary:The study of operation with raised strike points on the first ITER divertor target plates is motivated by the need to gain experience with operation with strike points on tungsten (W) surfaces during the non-active phases (in the case of an initial carbon fibre composite (CFC)/W divertor); or (if ITER begins with a full-W divertor), to gain experience with plasma control and transients while operating with raised strike points to avoid damaging the baseline strike regions in preparation for the nuclear phase, and to provide a means for operation should damage occur in the baseline strike zone. For operation with raised strike points, we use the Corsica code to investigate the range of possible H- and L-mode equilibria, with emphasis on the maximum plasma current, achievable shapes, etc. With raised strike points the maximum achievable plasma current is close to 14 MA. The operating space (βp − li) for raised strike points has been studied. The size of the βp − li operating space shrinks (compared to using standard strike-point positions) at 14 MA. For 12 MA, however, the operating space is not affected when using raised strike points. For equilibria with elevated strike points (at roughly the CFC/W transitions, following the 2007 ITER Design Review) the vertical-instability growth-rates at high plasma current (14 MA) are somewhat high but are within the 20 s−1 which studies indicate are controllable in ITER. At lower currents (12 MA) in H-mode, the vertical-instability growth rates stay below 10.0 s−1 for most of βp − li space. At 12 MA in H-mode, multiple equilibria which meet our constraints have been found in overlapping regions of the βp − li operating space.
ISSN:0029-5515
1741-4326
DOI:10.1088/0029-5515/53/8/083021