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1.
Post-mortem analysis of ITER CS helium inlets fatigue tested at cryogenic temperature / Aviles Santillana, I (CERN) ; Sgobba, S (CERN) ; Castillo Rivero, S (CERN) ; Libeyre, P (BIAM, St Paul lez Durance) ; Jong, C (BIAM, St Paul lez Durance) ; Everitt, D (Oak Ridge, U.S. ITER)
In the ITER Magnet System, ten thousand tonnes of superconducting Cable In Conduit Conductor (CICC) arecooled down by a forcedflow of supercritical helium, which is supplied from helium inlets. For the ITER CentralSolenoid (CS), consisting of six independent pancake wound modules, the He inlets consist of three overlappingholes covered by an oblong shaped boss, welded to the CS jacket through full penetration, multi-pass TungstenInert Gas (TIG) welding [...]
2019 - 5 p. - Published in : Fusion Eng. Des. 146 (2019) 642-646
2.
Assessment of Residual Stresses in ITER CS Helium Inlet Welds Fatigue Tested at Cryogenic Temperature / Sgobba, S (CERN) ; Aviles Santillana, I (CERN) ; Langeslag, S (CERN) ; Fernandez Pison, P (CERN ; Carlos III U., Madrid) ; Castillo Rivero, S (CERN ; Seville U.) ; Libeyre, P (Euratom, St. Paul Lez Durance) ; Jong, C (Euratom, St. Paul Lez Durance) ; Everitt, D (Oak Ridge, U.S. ITER) ; Freudenberg, K (Oak Ridge, U.S. ITER)
The ITER Central Solenoid (CS) consists of six independent wound modules. The cooling of the cable-in-conduit conductor is assured by a forced flow of supercritical He at 4.5 K supplied by He inlets located at the innermost radius of the coil. [...]
2019 - 6 p. - Published in : IOP Conf. Ser. Mater. Sci. Eng. 502 (2019) 012095
In : 27th International Cryogenic Engineering Conference - International Cryogenic Materials Conference 2018, Oxford, United Kingdom, 3 - 7 Sep 2018, pp.012095
3.
From manufacture to assembly of the ITER central solenoid / Libeyre, P (BIAM, St Paul lez Durance) ; Schild, T (BIAM, St Paul lez Durance) ; Bruton, A (BIAM, St Paul lez Durance) ; Cormany, C (BIAM, St Paul lez Durance) ; Dolgetta, N (BIAM, St Paul lez Durance) ; Gaxiola, E (BIAM, St Paul lez Durance) ; Jong, C (BIAM, St Paul lez Durance) ; Mitchell, N (BIAM, St Paul lez Durance) ; Evans, D (BIAM, St Paul lez Durance) ; Levesy, B (BIAM, St Paul lez Durance) et al.
The Central Solenoid (CS), a key component of the ITER Magnet system, using a 45 kA Nb 3 Sn conductor, includes six identical coils, called modules, to form a solenoid, enclosed inside a structure providing vertical pre-compression and mechanical support. Procurement of the components of the ITER CS is the responsibility of US ITER, the US Domestic Agency (USDA), while the assembly of these components will be carried out by the ITER Organization (IO). [...]
2019 - 4 p. - Published in : Fusion Eng. Des. 146 (2019) 437-440
4.
The Effect of Specific Manufacturing Characteristics on PF ITER Full-Size Joint Performance / Pison, Pilar Fernandez (Carlos III U., Madrid) ; Langeslag, Stefanie A E (CERN) ; Santillana, Ignacio Aviles (CERN) ; Dimitrijevic, Alexander (CERN) ; Sgobba, Stefano (CERN) ; Ilyin, Yury (BIAM, St Paul lez Durance) ; Simon, Fabrice (BIAM, St Paul lez Durance) ; Lim, Byung Su (BIAM, St Paul lez Durance)
The development of new generation superconducting magnets for fusion research, such as the ITER experiment, is largely based on coils wound from so-called “Cable-In-Conduit” Conductors (CICCs). CICCs consist of various types of stainless steel jackets, densely filled with compacted superconducting strands, which are cooled by supercritical helium. [...]
2019 - 6 p. - Published in : IEEE Trans. Appl. Supercond. 29 (2019) 4200706
5.
Development of HTS Current Leads for the ITER Project / Bauer, P. (BIAM, St Paul lez Durance) ; Ballarino, A (CERN) ; Devred, A (CERN) ; Ding, K (Hefei, Inst. Plasma Phys.) ; Dong, Y (Hefei, Inst. Plasma Phys.) ; Niu, E (Unlisted, CN) ; Du, Q (Hefei, Inst. Plasma Phys.) ; Gung, C Y (BIAM, St Paul lez Durance) ; Han, Q (Hefei, Inst. Plasma Phys.) ; Heller, R (KIT, Karlsruhe) et al.
The HTS current leads for the ITER project will be the largest ever operated, with unprecedented currents, up to 68 kA and voltages, up to 14 kV. According to the ITER agreement they will be provided in-kind by China. [...]
2020 - 8 p. - Published in : IOP Conf. Ser. Mater. Sci. Eng. 756 (2020) 012032 fulltext from publisher: PDF;
In : Conference on Cryogenic Engineering and on International Cryogenic Materials, Hartford, Connecticut, 21 - 25 Jul 2019, pp.012032
6.
Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes / Ding, Kaizhong (Hefei, Inst. Plasma Phys.) ; Zhou, Tingzhi (Hefei, Inst. Plasma Phys.) ; Ballarino, Amalia (CERN) ; Gung, Chenyu (Southampton U.) ; Lu, Kun (Hefei, Inst. Plasma Phys.) ; Song, Yuntao (Hefei, Inst. Plasma Phys.) ; Niu, Erwu (Beihang U.) ; Bauer, Pierre (BIAM, St Paul lez Durance) ; Devred, Arnaud (BIAM, St Paul lez Durance) ; Lee, Seungje (BIAM, St Paul lez Durance) et al.
High temperature superconducting current leads (HTS-CL) are designed to supply the current to the large superconducting ITER magnets for the operation with reduced heat load to the cryogenic system. The Toroidal field (TF) current leads are the largest with a current capacity of 68 kA each. [...]
2019 - 5 p. - Published in : IEEE Trans. Appl. Supercond. 29 (2019) 4802605 fulltext from publisher: HTML;
7.
Design Optimization and Assessment of Fabrication of ITER Central Solenoid Twin Box Joints / Santillana, Ignacio Aviles (CERN) ; Guinchard, Michael (CERN) ; Lourenço, Sandra Sophie (CERN) ; Motschmann, Fritz (CERN) ; Sacristan de Frutos, Oscar (CERN) ; Sgobba, Stefano (CERN) ; Bruton, Andrew (BIAM, St Paul lez Durance) ; Gaxiola, Enrique (BIAM, St Paul lez Durance) ; Libeyre, Paul (BIAM, St Paul lez Durance) ; Schild, Thierry (BIAM, St Paul lez Durance) et al.
The ITER Central Solenoid (CS) will be one of the world's largest and most powerful pulsed superconducting electromagnet ever built; at an approximate weight of 1300 tons and a total height of 18 m consisting of a stack of six electrically independent 4.1 m diameter modules. In order to electrically connect the CS with the feeder busbars, 12 twin box joints are used to assure an efficient high current transfer while avoiding excessive AC losses. [...]
2020 - 4 p. - Published in : IEEE Trans. Appl. Supercond. 30 (2020) 4202404
8.
Analysis of the Leakage Events in the Thermal Shield Cooling Pipes of the ITER Magnet System / Sgobba, Stefano (CERN) ; Santillana, Ignacio Aviles (CERN) ; Celuch, Michal (CERN) ; Crouvizier, Mickaël (CERN) ; Perez Fontenla, Ana Teresa (CERN) ; Castro, Enrique Rodriguez (CERN) ; Mitchell, Neil (Euratom, St. Paul Lez Durance) ; Koizumi, Norikiyo (Euratom, St. Paul Lez Durance) ; Pearce, Robert (Euratom, St. Paul Lez Durance) ; Worth, Liam (Euratom, St. Paul Lez Durance) et al.
The ITER Thermal Shields (TS) consist of actively cooled stainless steel panels. Their role is to minimise the radiation heat load from warm components, such as the Vacuum Vessel (VV) and the cryostat, hence contributing to insulating the magnet system operating at 4.5 K. [...]
2024 - 5 p. - Published in : IEEE Trans. Appl. Supercond. 34 (2024) 4203405
9.
Key impact of phase dynamics and diamagnetic drive on Reynolds stress in magnetic fusion plasmas / Sarazin, Y (BIAM, St Paul lez Durance) ; Dif-Pradalier, G (BIAM, St Paul lez Durance) ; Garbet, X (BIAM, St Paul lez Durance) ; Ghendrih, P (BIAM, St Paul lez Durance) ; Berger, A (BIAM, St Paul lez Durance) ; Gillot, C (BIAM, St Paul lez Durance) ; Grandgirard, V (BIAM, St Paul lez Durance) ; Obrejan, K (BIAM, St Paul lez Durance) ; Varennes, R (BIAM, St Paul lez Durance) ; Vermare, L (UPMC, Paris (main) ; U. Paris-Saclay ; U. Paris-Sud 11, Dept. Phys., Orsay) et al.
Reynolds stress is a key facet of turbulence self-organization. In the magnetized plasmas of controlled fusion devices, the zonal flows that are driven by the averaged Reynolds stress modify the confinement performance. [...]
2021 - 13 p. - Published in : Plasma Phys. Control. Fusion 63 (2021) 064007
10.
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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