1.
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Microstructure and Mechanical Properties of the Enclosure Welding Joint for ITER Correction Coils Cases
/ Xin, Jijun (Hefei, Inst. Plasma Phys.) ; Fang, Chao (Hefei, Inst. Plasma Phys.) ; Yang, Wuxiong (Beijing U. of Tech.) ; Huang, Chuanjun (Beijing, Tech. Inst. Phys. Chem.) ; Dai, Wenhua (Hefei, Inst. Plasma Phys.) ; Wei, Jing (Hefei, Inst. Plasma Phys.) ; Song, Yuntao (Hefei, Inst. Plasma Phys.) ; Li, Laifeng (Beijing, Tech. Inst. Phys. Chem.) ; Fabrice, Simon (Euratom, St. Paul Lez Durance) ; Paul, Libeyre (Euratom, St. Paul Lez Durance) et al.
To resist the alternating electromagnetic loads, the International Thermonuclear Experimental Reactor (ITER) correction coils are protected by a 20-mm-thick 316LN austenitic stainless steel case. According to the strict tolerance requirement of the case manufacture, laser welding was applied to enclosure welding of the cases with a 20-kW high-power laser for root pass and Tungsten Inert Gas welding was applied for filler and cover passes. [...]
2020 - 8 p.
- Published in : IEEE Trans. Appl. Supercond. 30 (2020) 8401208
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2.
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Microstructure and Mechanical Properties of ITER Correction Coil Case Material
/ Xin, Jijun (Hefei, Inst. Plasma Phys.) ; Fang, Chao (Hefei, Inst. Plasma Phys.) ; Song, Yuntao (Hefei, Inst. Plasma Phys.) ; Wei, Jing (Hefei, Inst. Plasma Phys.) ; Huang, Chuanjun (Beijing, Tech. Inst. Phys. Chem.) ; Libeyre, Paul (Euratom, St. Paul Lez Durance) ; Simon, Fabrice (Euratom, St. Paul Lez Durance) ; Sgobba, Stefano (CERN)
The modified 316LN austenitic stainless steel was selected as ITER correction coils case material to provide structural reinforcement to the winding pack. Considering the case structure, high-assembling accuracy and other strict requirements, 316LN in special extruded form has been developed. [...]
2017 - 7 p.
- Published in : IEEE Trans. Appl. Supercond. 27 (2017) 4201707
- Published in : IEEE Trans. Appl. Supercond. 30 (2019) 9700101
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3.
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Qualification of the Manufacturing Procedures of the ITER Correction Coils
/ Libeyre, P (Euratom, St. Paul Lez Durance) ; Cormany, C (Euratom, St. Paul Lez Durance) ; Dolgetta, N (Euratom, St. Paul Lez Durance) ; Gaxiola, E (Euratom, St. Paul Lez Durance) ; Ilyin, Y (Euratom, St. Paul Lez Durance) ; Mitchell, N (Euratom, St. Paul Lez Durance) ; Simon, F (Euratom, St. Paul Lez Durance) ; Evans, D (Euratom, St. Paul Lez Durance) ; Sgobba, S (CERN) ; Langeslag, S A E (CERN) et al.
The system of correction coils (CC) is a component of the ITER magnet system, required to correct toroidal asymmetries and reduce error magnetic fields detrimental for physical processes in the plasma. It includes 18 coils, inserted in between toroidal field coils and poloidal field coils and split into 3 sets of 6 coils each: bottom correction coils (BCC), side correction coils (SCC), and top correction coils (TCC). [...]
2017 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 27 (2017) 4201405
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4.
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The ITER In-Vessel Coils – design finalization and challenges
/ Vostner, Alexander (Euratom, St. Paul Lez Durance) ; Bontemps, Vincent (Euratom, St. Paul Lez Durance) ; Encheva, Anna (Euratom, St. Paul Lez Durance) ; Jin, Huan (Hefei, Inst. Plasma Phys.) ; Laquiere, Julien (Euratom, St. Paul Lez Durance) ; Macioce, Davide (Euratom, St. Paul Lez Durance) ; Mariani, Nicola (Euratom, St. Paul Lez Durance) ; Mcintosh, Simon (Euratom, St. Paul Lez Durance) ; Peng, Xuebing (Euratom, St. Paul Lez Durance) ; Singh, Shuvay (CERN) et al.
ITER In-Vessel Coils (IVCs), resistive magnets to be installed in close proximity to ITER plasma to compensate fast perturbations of the plasma itself, have undergone a comprehensive revision of their requirements and operational loads, leading to design modifications and R&D; activities. An update of the plasma operating scenarios has been done and the maximum currents during transient plasma events have been assessed considering actual operating currents and the surrounding vacuum vessel support structure leading to more representative load cases. [...]
2019 - 6 p.
- Published in : Fusion Eng. Des. 146 (2019) 1490-1495
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5.
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Electrical insulation testing for ITER fusion tokamak
/ Gaxiola, E (Euratom, St. Paul Lez Durance) ; Evans, D (Euratom, St. Paul Lez Durance) ; Laquiere, J (Euratom, St. Paul Lez Durance) ; Laurenti, A (Euratom, St. Paul Lez Durance) ; Libeyre, P (Euratom, St. Paul Lez Durance) ; Lyraud, C (Euratom, St. Paul Lez Durance) ; Piccin, R (Euratom, St. Paul Lez Durance) ; Rinaudo, G (Euratom, St. Paul Lez Durance) ; Simon, F (Euratom, St. Paul Lez Durance) ; Vollmann, T (Euratom, St. Paul Lez Durance) et al.
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. [...]
2017 - 4 p.
- Published in : 10.1109/EIC.2017.8004670
In : 35th IEEE Electrical Insulation Conference, Baltimore, MD, USA, 11 - 14 Jun 2017, pp.408-411
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6.
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Design of the HTS Current Leads for ITER
/ Ballarino, A (CERN) ; Bauer, P (Euratom, St. Paul Lez Durance) ; Bi, Y (Hefei, Inst. Plasma Phys.) ; Devred, A (Euratom, St. Paul Lez Durance) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Foussat, A (Euratom, St. Paul Lez Durance) ; Mitchell, N (Euratom, St. Paul Lez Durance) ; Shen, G (Hefei, Inst. Plasma Phys.) ; Song, Y (Hefei, Inst. Plasma Phys.) ; Taylor, T (CERN) et al.
Following the design, fabrication and test of a series of trial leads, designs of the three types of current leads required for ITER have been developed, and targeted trials of specific features are in progress on the way to fabrication and testing of prototype units. These leads are of the hybrid type with a cold section based on the use of high temperature superconductor (HTS) and a resistive section cooled by forced flow of helium gas, optimized for operation at 68 kA, 55 kA and 10 kA. [...]
CERN-ATS-2012-047.-
Geneva : CERN, 2012 - 5 p.
- Published in : IEEE Trans. Appl. Supercond. 22 (2012) 4800304
Fulltext: PDF;
In : 22nd International Conference on Magnet Technology, Marseille, France, 12 - 16 Sep 2011
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7.
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Qualification of structural stainless steel products for the ITER correction coil cases
/ Sgobba, Stefano (CERN) ; Dalin, Jean-Michel (CERN) ; Langeslag, Stefanie Agnes Elisabeth (CERN) ; Aviles Santillana, Ignacio (CERN ; Carlos III U., Madrid) ; Libeyre, Paul (Euratom, St. Paul Lez Durance) ; Simon, Fabrice (Euratom, St. Paul Lez Durance) ; Wei, Jing (Hefei, Inst. Plasma Phys.) ; Chai, Zhiyong (Taiyuan Iron & Steel (group) Co., Ltd. (TISCO), Taiyuan) ; Li, Laifeng (Beijing, Tech. Inst. Phys. Chem.)
The ITER Correction Coils (CCs) consist of three sets of six coils, Bottom (BCC), Side (SCC) and Top Correction Coils (TCC), respectively. The CCs rely on 10 kA NbTi cable-in-conduit conductor. [...]
2017 - 5 p.
- Published in : Fusion Eng. Des. 124 (2017) 980-984
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8.
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Fatigue performance evaluation for ITER IVC conductor component materials
/ Jin, H (Hefei, Inst. Plasma Phys. ; Euratom, St. Paul Lez Durance) ; Vostner, A (Euratom, St. Paul Lez Durance) ; Wu, Y (Hefei, Inst. Plasma Phys.) ; Macioce, D (Euratom, St. Paul Lez Durance) ; Sgobba, S (CERN) ; Huang, C (Beijing, Tech. Inst. Phys. Chem.) ; Romero Rodriguez, C (CERN ; Carlos III U., Madrid) ; Fernandez Pison, P (CERN ; Carlos III U., Madrid) ; Elisabeth Langeslag, S A (CERN) ; Aviles Santillana, I (CERN ; Carlos III U., Madrid) et al.
The ITER IVCs are made of stainless steel mineral-insulated conductors composed by an OFE copper conductor and a SS316LN jacket. The baseline design requires the coils to endure all ITER machine life time. [...]
2017 - 9 p.
- Published in : Vacuum 145 (2017) 86-94
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9.
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Qualification of Fin-Type Heat Exchangers for the ITER Current Leads
/ Ballarino, A (CERN) ; Bauer, P (Euratom, St. Paul Lez Durance) ; Bordini, B (CERN) ; Devred, A (Euratom, St. Paul Lez Durance) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Niu, E ; Sitko, M (CERN) ; Taylor, T ; Yang, Y (Southampton U.) ; Zhou, T (Hefei, Inst. Plasma Phys.)
The ITER current leads will transfer large currents of up to 68 kA into the biggest superconducting magnets ever built. Following the development of prototypes and targeted trials of specific manufacturing processes through mock-ups, the ASIPP (Chinese Institute of Plasma Physics) is preparing for the series fabrication. [...]
2015
- Published in : IOP Conf. Ser. Mater. Sci. Eng. 101 (2015) 012119
IOP Open Access article: PDF;
In : Advances in Cryogenic Engineering: Cryogenic Engineering Conference, Tucson, AZ, USA, 28 Jun - 2 Jul 2015, pp.012119
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10.
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Characterization of low temperature high voltage axial insulator breaks for the ITER cryogenic supply line
/ Fernandez Pison, P (CERN ; Carlos III U., Madrid) ; Sgobba, S (CERN) ; Santillana, I Aviles (CERN ; Carlos III U., Madrid) ; Langeslag, S A E (CERN) ; Su, M (Euratom, St. Paul Lez Durance) ; Piccin, R (Euratom, St. Paul Lez Durance) ; Journeaux, J Y (Euratom, St. Paul Lez Durance) ; Laurenti, A (Euratom, St. Paul Lez Durance) ; Pan, W (Hefei, Inst. Plasma Phys.)
Cable-in-conduit conductors of the ITER magnet system are directly cooled by supercritical helium. Insulation breaks are required in the liquid helium feed pipes to isolate the high voltage system of the magnet windings from the electrically grounded helium coolant supply line. [...]
2017 - 8 p.
- Published in : IOP Conf. Ser. Mater. Sci. Eng. 279 (2017) 012007
Fulltext: PDF; External link: Fulltext
In : 2017 Cryogenic Engineering Conference and International Cryogenic Materials Conference, Madison, WI, USA, 9 - 13 Jul 2017, pp.012007
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