Empirical error field control at JET in preparation of ITER start-up

被引:0
|
作者
Piron, L. [1 ,2 ]
Paz-Soldan, Carlos [3 ]
Lennholm, Morten [4 ]
Kirov, Krassimir [4 ]
Valcarcel, Daniel [4 ]
Baruzzo, Matteo [5 ,6 ]
Bolzonella, Tommaso [2 ]
Cicioni, Rachele [2 ,8 ]
De Vries, Peter [9 ]
Ferron, Nicolo [2 ]
Gambrioli, Matteo [2 ,8 ]
Gribov, Y. [9 ]
Henriques, R. [4 ]
Joffrin, Emmanuel [7 ]
Martin, Piero [1 ,2 ]
Mattei, Massimiliano [10 ]
Manduchi, Gabriele [2 ,11 ]
Pangione, Luigi [9 ]
Pigatto, Leonardo [2 ]
Pironti, Alfredo [10 ]
De Tommasi, Gianmaria [10 ]
Zabeo, Luca [9 ]
机构
[1] Univ Padua, Dept Phys & Astron, Via F Marzolo 8, I-35131 Padua, Italy
[2] Univ Padua, Consorzio RFX, CNR, ENEA,INFN,Acciaierie Venete SpA, C So Stati Uniti 4, I-35127 Padua, Italy
[3] Columbia Univ, 116th St & Broadway, New York, NY 10027 USA
[4] UKAEA, Culham Sci Ctr, CCFE, Abingdon OX14 3DB, England
[5] ENEA, Fus & Nucl Safety Dept, CR Frascati, Rome, Italy
[6] ENEA Frascati, CP 65, I-00044 Frascati, Italy
[7] IRFM, Assoc EURATOM CEA Fus, CEA, F-13108 St Paul Les Durance, France
[8] Univ Padua, CRF, Consiglio Nazl Ric, Corso Stati Uniti 4, I-35127 Padua, Italy
[9] ITER Org, CS 90046, F-13067 St Paul Les Durance, France
[10] Univ Federico II, C So Umberto I,40, I-80138 Naples, Italy
[11] CNR, Ist Sci & Tecnol Plasmi, C So Stati Uniti 4, I-35127 Padua, Italy
关键词
JET; ITER; Plasma control; LOCKED MODES; DIII-D;
D O I
10.1016/j.fusengdes.2024.114694
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This work reports on error field identification and control studies carried out at JET and insights on the development of the empirical EF controller for ITER. The empirical EF controller has been included in the JET real-time central controller following the execution of the non-disruptive compass scan method (Paz-Soldan C. et al., Nuclear Fusion 62 (2022) 126007), which allowed the identification of the EF source and the currents for error field compensation. When testing the empirical EF controller, born locked n = 1 modes have been observed to spin-up and a lower density regime has been explored in the 1.8 MA plasma current, 2.1 T toroidal magnetic field scenario than otherwise achievable. These experimental results demonstrate the benefits of EF correction. In preparation of EF correction studies in ITER, the empirical EF controller for ITER has been developed and integrated in the plasma control system database.
引用
收藏
页数:7
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