Electrical Insulation Testing for ITER Fusion Tokamak

被引：0

作者：

Gaxiola, E. ^{[1
]}

Evans, D. ^{[1
]}

Laquiere, J. ^{[1
]}

Laurenti, A. ^{[1
]}

Libeyre, P. ^{[1
]}

Lyraud, C. ^{[1
]}

Piccin, R. ^{[1
]}

Rinaudo, G. ^{[1
]}

Simon, F. ^{[1
]}

Vollmann, T. ^{[1
]}

Langeslag, S. ^{[2
]}

Sgobba, S. ^{[2
]}

Martovetsky, N. ^{[3
]}

Khumthong, K. ^{[4
]}

Norausky, N. ^{[4
]}

Smith, J. ^{[4
]}

Niu, E. ^{[5
]}

Wei, J. ^{[6
]}

Wu, H. ^{[6
]}

Yu, X. ^{[6
]}

机构：

[1] ITER Org IO, St Paul Les Durance, France

[2] European Nucl Res Ctr CERN, Geneva, Switzerland

[3] US ITER Project Off USIPO, Oak Ridge, TN USA

[4] GA, San Diego, CA USA

[5] China Int Nucl Fus Energy Program Execut Ctr CNDA, Beijing, Peoples R China

[6] Inst Plasma Phys ASIPP, Hefei, Anhui, Peoples R China

来源：

2017 IEEE ELECTRICAL INSULATION CONFERENCE (EIC) | 2017年

关键词：

magnets; insulation; partial discharge; supercon ductivity; tokamak; fusion;

D O I：

暂无

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

The uniqueness of the ITER fusion project drives purpose and scope here to fulfil (functional) Procurement Arrangement (PA) requirements for the Central Solenoid (CS) and Correction Coil (CC) magnets' electrical insulation [1-3]; as used and undertaken for covering high voltage testing operations of the magnet coil winding pack (WP) vacuum pressure insulation (VPI) beam qualification, followed in 2016 by start of magnets series production in the USA and China [1, 2]. Useful to be considered common state-of-the-art electrical power components testing practices [3, 4] are presented here as performed to verify that the integrity and insulation of the various components are within acceptable limits during different phases of the fabrication and to certify acceptance on delivery of the complete coils. Initial measurement plans were complemented into electrical tests with typical high voltage engineering implemented measures as a pre-requisite to successfully validate produced results. The above permitted the first quantitative validation of the obtained final production, including life time behavior.

引用

页码：408 / 411

页数：4

共 10 条

[1] [Anonymous], ITER D RSA9K8 DLZ CC
[2] [Anonymous], 60270 IEC
[3] [Anonymous], 2010, TECHN SPEC ANNEX B P
[4] [Anonymous], 2014, ITER D QQMAWT 303700, P1
[5] ASTM, D149 ASTM
[6] Gaxiola E. H. R., 1999, THESIS, P124
[7] Libeyre P., 2016, ASC 2016, P1
[8] Libeyre P., 2015, MT24, P1
[9] Electrical Insulation Systems for the ITER CS Modules
Reed, R. P.
Martovetsky, N. N.
[J]. ADVANCES IN CRYOGENIC ENGINEERING, VOL 60, 2014, 1574 : 354 - 361
[10] High-voltage testing of superconducting power apparatus
Schwenterly, SW
[J]. CRYOGENICS, 1998, 38 (11) : 1115 - 1122

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