Speaker
Jorge Morales
Description
See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P4.1077.pdf
Predictive integrated modelling simulations in preparation of the JET
Deuterium-Tritium campaign
J. Morales1, J. Garcia1, C. Challis2, J.-F. Artaud1 and JET contributors∗
EUROfusion Consortium, JET, Culham Science Centre, Abingdon, OX14 3DB, UK
1
CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France
2
CCFE, Culham Science Centre, Abingdon, OX14 3DB, UK
(*) See the author list of X Litaudon et al. 2017 Nucl. Fusion 57 102001
The main objective of the future JET tokamak experimental campaigns is to prepare the
future D-T scenarios of JET and ITER. Together with these experiments an important effort
in modelling is needed to be able to test and improve the predictive capability of integrated
modelling tools for D-T burning plasmas. Alpha particles along with isotope effects [1] on
plasma confinement need to be further studied and understood. A particular topic of interest
is the validity of first principle models for predicting turbulence in D-T conditions.
Therefore, a significant effort towards that direction is required by analysing the physics of
extrapolated D-T plasmas. Weakness of the models can be mitigated by proposing
experiments specifically designed to improve such predictive capabilities in plasmas
different than D, for instance in the future T campaign.
To help in the present modelling effort of D-T tokamak plasmas we have carried out
integrated modelling simulations with the CRONOS code [2] using GLF23 [3], TGLF [4]
and QuaLiKiz [5] turbulence transport models. A baseline JET shot (92436) has been
extrapolated to higher power and D-T plasma conditions. This shot has been chosen because
it is one with the highest neutron rate yield from the last campaign. In the present study we
have carried out simulations varying the injected NBI power, first in deuterium and then in
D-T plasmas. A scan in plasma current and in toroidal rotation velocity is performed. The
results show the improvement of the plasma confinement with increasing toroidal rotation
and the decrease of transport for D-T plasmas in some particular plasma regions (inner core
and edge) compared to pure deuterium. The fusion power calculated from the different D-T
plasmas simulations range between 13 and 16 MW for 41 MW of total injected power (6 MW
of ICRH and 35 MW of NBI).
[1] J. Garcia et al. 2017 Nucl. Fusion 57 014007, [2] J.-F. Artaud et al. 2010 Nucl. Fusion 50 043001, [3] R. E.
Waltz et al. 1997 Phys. of Plasmas 4 2482, [4] G. M. Staebler et al. 2005 Phys. of Plasmas 12 102508, [5] C.
Bourdelle et al. 2016 Plasma Phys. And Control. Fusion 58 014036
