Procedure qualification and integration of the continuous external Rogowski diagnostics to the superconducting magnets of ITER tokamak

被引：0

作者：

Ma, Y. ^{[1
]}

Nakamoto, M. ^{[2
]}

Sakurai, T. ^{[2
]}

Kiyoshi, Y. ^{[1
,2
]}

Iguchi, M. ^{[2
]}

Hong, Y. ^{[2
]}

Bellesia, B. ^{[3
]}

Aprili, P. ^{[3
]}

Luongo, C. ^{[1
]}

Koczorowski, S. ^{[1
]}

Gomikawa, K. ^{[1
]}

Tronza, V. ^{[1
]}

Nishino, H. ^{[2
]}

Peluso, B. ^{[4
]}

Gros, G. ^{[4
]}

Pelcot, F. ^{[4
]}

Hattat, A. ^{[5
]}

Huguenot, S. ^{[5
]}

Bony, F. ^{[5
]}

Lama, J. ^{[6
]}

Fujiwara, E. ^{[7
]}

Okada, Y. ^{[8
]}

Yamane, M. ^{[8
]}

Baratta, A. ^{[9
]}

Battaglia, D. ^{[9
]}

Marteil, H. ^{[10
]}

Counsell, G. ^{[3
]}

Vayakis, G. ^{[1
]}

Walsh, M. ^{[1
]}

机构：

[1] ITER Org, Route Vinon Verdon,CS 90046, F-13067 St Paul Les Durance, France

[2] Natl Inst Quantum Sci & Technol QST, 4-9-1Anagawa,Inage Ku, Chiba, Chiba 2638555, Japan

[3] Fus Energy, C-Josep Pla 2,Torres Diagonal Litor, Barcelona, Spain

[4] CEA, IRFM, F-13108 St Paul Les Durance, France

[5] AXON Cable SAS, BP 1,Route Chalons Champagne, F-51210 Montmirail, France

[6] Sgenia Ind, Edificio II,C Chile 4, Las Rozas De Madrid 28230, Madrid, Spain

[7] Mitsubishi Heavy Ind MHI, 1-1Wadasaki Cho 1 Chome,Hyogo Ku, Kobe, Hyogo 6528585, Japan

[8] Mitsubishi Elect Corp MELCO, 2-7-3 Marunouchi, Tokyo, Tokyo 1008310, Japan

[9] Simic SpA, Via Vittorio Veneto, I-12072 Camerana, CN, Italy

[10] DAHER Technol, 7 Ave Union, F-94390 Orly, France

来源：

FUSION ENGINEERING AND DESIGN | 2023年 / 196卷

关键词：

ITER; Diagnostics integration; Rogowski coils; Hydrostatic pressure test; Helium leak test; Cryogenic test; Resin impregnation; Superconducting magnets; DESIGN;

D O I：

10.1016/j.fusengdes.2023.113984

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：

Continuous External Rogowski (CER) are the primary plasma current diagnostics for the ITER tokamak, as well as the only diagnostics built into the ITER Toroidal Field Coils (TF coils). The integration of CER diagnostics to the TF coils faced numerous technical challenges, such as: the integrated components have to withstand the maximum pressure foreseen during ITER TF coil resin impregnation (350 kPa), comply with the high vacuum requirements that the helium leak rate shall be <2.7 x 10(-9) Pa-m(3)/s, and survive at cryogenic temperature. The CER diagnostics integration campaign turned out to be a marked success, thanks to a comprehensive pre qualification program and well-coordinated collaborations among the participating parties. All four sets of CER diagnostics have so far been integrated to the respective TF coils. As a pioneering attempt of building plasma diagnostics into reactor-scale superconducting magnets, the potential implications of this venture to the diagnostics development for DEMO and future fusion reactors are discussed. The gained experiences and lessons learned from this venture are summarized at last.

引用

页数：14

共 19 条

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