Plasma Scenarios for the DTT Tokamak with Optimized Poloidal Field Coil Current Waveforms

被引:16
作者
Castaldo, Antonio [1 ]
Albanese, Raffaele [1 ,2 ,3 ]
Ambrosino, Roberto [1 ,2 ,3 ]
Crisanti, Flavio [4 ]
机构
[1] Consorzio CREATE, Via Claudio 21, I-80125 Naples, Italy
[2] Univ Napoli Federico II, Dipartimento Ingn Elettr & Tecnol informaz, Via Claudio 21, I-80125 Napol, Italy
[3] DTT SC Arl, Consorzio Attuaz Progetto Divertor Tokamak Test, I-00044 Frascati, Italy
[4] Univ Tuscia, Dept Econ Engn Soc & Business Org DEIM, Largo Univ, I-01100 Viterbo, Italy
关键词
DTT tokamak; plasma scenarios; power exhaust;
D O I
10.3390/en15051702
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
In the field of nuclear fusion, the power exhaust problem is still an open issue and represents one of the biggest problems for the realization of a commercial fusion power plant. According to the "European Fusion Roadmap", a dedicated facility able to investigate possible solutions to heat exhaust is mandatory. For this purpose, the mission of the Divertor Tokamak Test (DTT) tokamak is the study of different solutions for the divertor. This paper presents the plasma scenarios for standard and alternative configurations in DTT. The Single Null scenario is described in detail. The alternative configurations are also presented, showing the good flexibility of the machine.
引用
收藏
页数:14
相关论文
共 16 条
[1]   DTT: a divertor tokamak test facility for the study of the power exhaust issues in view of DEMO [J].
Albanese, R. .
NUCLEAR FUSION, 2017, 57 (01)
[2]   CREATE-NL plus : A robust control-oriented free boundary dynamic plasma equilibrium solver [J].
Albanese, R. ;
Ambrosino, R. ;
Mattei, M. .
FUSION ENGINEERING AND DESIGN, 2015, 96-97 :664-667
[3]   The linearized CREATE-L plasma response model for the control of current, position and shape in tokamaks [J].
Albanese, R ;
Villone, F .
NUCLEAR FUSION, 1998, 38 (05) :723-738
[4]   Sweeping control performance on DEMO device [J].
Ambrosino, R. ;
Ariola, M. ;
Bachmann, C. ;
Castaldo, A. ;
Maviglia, F. ;
Mattei, M. ;
Tartaglione, G. .
FUSION ENGINEERING AND DESIGN, 2021, 171
[5]   DTT-Divertor Tokamak Test facility: A testbed for DEMO [J].
Ambrosino, R. .
FUSION ENGINEERING AND DESIGN, 2021, 167
[6]   Achievement of Reactor-Relevant Performance in Negative Triangularity Shape in the DIII-D Tokamak [J].
Austin, M. E. ;
Marinoni, A. ;
Walker, M. L. ;
Brookman, M. W. ;
deGrassie, J. S. ;
Hyatt, A. W. ;
McKee, G. R. ;
Petty, C. C. ;
Rhodes, T. L. ;
Smith, S. P. ;
Sung, C. ;
Thome, K. E. ;
Turnbull, A. D. .
PHYSICAL REVIEW LETTERS, 2019, 122 (11)
[7]   Development of DTT single null divertor scenario [J].
Balbinot, L. ;
Rubino, G. ;
Innocente, P. .
NUCLEAR MATERIALS AND ENERGY, 2021, 27
[8]   Impact of plasma triangularity and collisionality on electron heat transport in TCV L-mode plasmas [J].
Camenen, Y. ;
Pochelon, A. ;
Behn, R. ;
Bottino, A. ;
Bortolon, A. ;
Coda, S. ;
Karpushov, A. ;
Sauter, O. ;
Zhuang, G. .
NUCLEAR FUSION, 2007, 47 (07) :510-516
[9]   VOLT-SECOND ANALYSIS AND CONSUMPTION IN DOUBLET-III PLASMAS [J].
EJIMA, S ;
CALLIS, RW ;
LUXON, JL ;
STAMBAUGH, RD ;
TAYLOR, TS ;
WESLEY, JC .
NUCLEAR FUSION, 1982, 22 (10) :1313-1319
[10]  
ENEA, 2019, INT DES REP DTT GRE