Optimizing the current ramp-up phase for the hybrid ITER scenario. Hogeweij, G., M., D., Artaud, J., Casper, T., A., Citrin, J., Imbeaux, F., K枚chl, F., Litaudon, X., Voitsekhovitch, I., & the ITM-TF ITER Scenario Modelling Group Nuclear Fusion, 53(1):13008, 2013.
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Website abstract bibtex
Paper Website abstract bibtex The current ramp-up phase for the ITER hybrid scenario is analysed
with the CRONOS integrated modelling suite. The simulations presented
in this paper show that the heating systems available at ITER allow,
within the operational limits, the attainment of a hybrid q profile
at the end of the current ramp-up. A reference ramp-up scenario is
reached by a combination of NBI, ECCD (UPL) and LHCD. A heating scheme
with only NBI and ECCD can also reach the target q profile; however,
LHCD can play a crucial role in reducing the flux consumption during
the ramp-up phase. The optimum heating scheme depends on the chosen
transport model, and on assumptions of parameters like n e peaking,
edge T e,i and Z eff . The sensitivity of the current diffusion on
parameters that are not easily controlled, shows that development
of real-time control is important to reach the target q profile.
A first step in that direction has been indicated in this paper.
Minimizing resistive flux consumption and optimizing the q profile
turn out to be conflicting requirements. A trade-off between these
two requirements has to be made. In this paper it is shown that fast
current ramp with L-mode current overshoot is at the one extreme,
i.e. the optimum q profile at the cost of increased resistive flux
consumption, whereas early H-mode transition is at the other extreme.
@article{
title = {Optimizing the current ramp-up phase for the hybrid ITER scenario},
type = {article},
year = {2013},
pages = {13008},
volume = {53},
websites = {http://stacks.iop.org/0029-5515/53/i=1/a=013008},
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abstract = {The current ramp-up phase for the ITER hybrid scenario is analysed
with the CRONOS integrated modelling suite. The simulations presented
in this paper show that the heating systems available at ITER allow,
within the operational limits, the attainment of a hybrid q profile
at the end of the current ramp-up. A reference ramp-up scenario is
reached by a combination of NBI, ECCD (UPL) and LHCD. A heating scheme
with only NBI and ECCD can also reach the target q profile; however,
LHCD can play a crucial role in reducing the flux consumption during
the ramp-up phase. The optimum heating scheme depends on the chosen
transport model, and on assumptions of parameters like n e peaking,
edge T e,i and Z eff . The sensitivity of the current diffusion on
parameters that are not easily controlled, shows that development
of real-time control is important to reach the target q profile.
A first step in that direction has been indicated in this paper.
Minimizing resistive flux consumption and optimizing the q profile
turn out to be conflicting requirements. A trade-off between these
two requirements has to be made. In this paper it is shown that fast
current ramp with L-mode current overshoot is at the one extreme,
i.e. the optimum q profile at the cost of increased resistive flux
consumption, whereas early H-mode transition is at the other extreme.},
bibtype = {article},
author = {Hogeweij, G M D and Artaud, J.-F. and Casper, T A and Citrin, J and Imbeaux, F and K枚chl, F and Litaudon, X and Voitsekhovitch, I and the ITM-TF ITER Scenario Modelling Group, undefined},
journal = {Nuclear Fusion},
number = {1}
}Downloads: 0
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