Speaker
Saul Garavaglia
Description
See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P4.1071.pdf
Expected performances of the DTT heating systems
G. Granucci , S. Garavaglia , P. Agostinetti , T. Bolzonella , A. Cardinali , C. Castaldo , S.
1 1 2 2 3 3
Ceccuzzi , D. Farina , L. Figini , R. Maggiora , D. Milanesio , A. Moro , G. L. Ravera , M.
3 1 1 4 4 1 3
Vallar , P. Vincenzi
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1
Istituto di Fisica del Plasma IFP-CNR, Milano, Italy
2
Consorzio RFX, Padova, Italy
3
ENEA, Dipartimento FSN, Frascati (RM), Italy
4
Politecnico di Torino, Dipartimento di Elettronica, Torino, Italy
The main purpose of the Divertor Tokamak Test is to study solutions to mitigate the issue
of power exhaust in conditions relevant for DEMO. The tokamak proposed by Italy, I-DTT
[1] (BT=6T, IP=5MA, ne~2⋅1020m-3, R0=2.05m, a=0.7m and pulse duration of ~100s), is
being designed to allocate the optimal divertor magnetic configuration under reactor
relevant power flow (P /R>15 MW/m) in the scrape off layer. To achieve this goal it is
SEP
planned to equip the machine with a significant amount of auxiliary heating power (45
MW). The heating power foreseen to get the target value of 45 MW at the plasma will
consist of a mix of ECRH (28-40MW), ICRH (8-12MW) and NNBI (10MW). The final
choice of each system contribution will be fixed at the end of the design review phase.
In this work we present the preliminary studies on the capability of each system to couple
the target power to the plasma. The EC system is based on gyrotrons sources
(1MW/170GHz/100s) and front steerable launchers to fulfill several requirements as bulk
electron heating, additional current drive generation, avoidance of impurities accumulation
and MHD control. The IC (f=60-90MHz) system is mainly dedicated to central plasma
heating with the use of antennas designed to maximize the coupled power. NNBI with
beam energy of 300 keV will be provided by two injectors with optimized tangential
injection geometry to support plasma current generation.
A description of the three systems and estimations of the deposition profiles will be
discussed in this work, underlining the specific technical solutions adopted to fulfill the
requirements and maximize the performances.
[1] R. Albanese et al, Fusion Eng. Des. 122 (2017) pp. 274-284.
