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Pong I.,ITER Organization | Jewell M.C.,ITER Organization | Jewell M.C.,University of Wisconsin - Eau Claire | Bordini B.,CERN | And 12 more authors.
IEEE Transactions on Applied Superconductivity

The ITER machine will require approximately 250 tons of NbTi strands and 500 tons of Nb3Sn strands. NbTi will be used in the Poloidal Field (PF) coils, Correction Coils (CC) and feeder busbars, whereas Nb3Sn will be used in the Central Solenoid (CS) and Toroidal Field (TF) coils. The large amount of superconducting strands needed requires worldwide procurement, involving suppliers from six of the seven ITER Domestic Agencies (DAs). To ensure reliable test results, it is necessary to benchmark the test facilities at each supplier and at each DA reference laboratory for physical and superconducting properties measurement, as well as sample preparation techniques. Following previous benchmarking efforts related to ITER procurement in the mid-1990s and to supplier and DA laboratory qualification performed on bronze Nb3Sn route strands in 2009, we report here the latest rounds on internal tin and NbTi strands. Ten participants from five DAs (China, EU, South Korea, Russia, and the U.S.) together with CERN (the ITER Organisations reference laboratory) took part in the benchmarking of internal Nb3Sn tin strands, and six participants from China and Russia, plus CERN, participated in the benchmarking of NbTi strands. © 2012 IEEE. Source

Fang C.,ASIPP | Song Y.,ASIPP | Wu W.,ASIPP | Wei J.,ASIPP | And 6 more authors.
Journal of Fusion Energy

ITER correction coil (CC) cases have characteristics of small cross section, large dimensions, and complex structure. The cases are made of heavy thick (20 mm), high strength and high toughness austenitic stainless steel 316LN. The multi-pass laser welding with hot wire technology is used for the case closure welding, due to its low heat input and deformation. In order to evaluate the reliability of this welding technology, 20 mm welding samples with the same groove structure and welding depth as the cases were welded. High purity argon was used as the shielding gas to prevent oxidation because of the narrowness and depth of the weld. In this paper investigation of, microstructure characteristics and mechanical properties of welded joints using optimized welding parameters are presented. The results show that the base metal, fusion metal, and heat affected zone (HAZ) are all have fully austenitic microstructure, and that the grain size of fusion metal was finer than that of the base metal. The welding resulted in an increase of hardness in the fusion metal and HAZ. It was confirmed that the tensile strength of fusion metal was higher than that of base metal and the impact toughness value is higher than industry standard requirement. Thus, this welding process was determined to be reliable for manufacture of the ITER CC cases manufacture. © 2014, Springer Science+Business Media New York. Source

Libeyre P.,ITER Organization | Li H.,ITER China | Reiersen W.,Oak Ridge National Laboratory | Dolgetta N.,ITER Organization | And 19 more authors.
Fusion Engineering and Design

The manufacturing line of the ITER Correction Coils (CC) at ASIPP in Hefei (China) was completed in 2013 and the manufacturing line of the ITER Central Solenoid (CS) modules is under installation at General Atomic premises in Poway (USA). In both cases, before starting production of the first coils, qualification of the manufacturing procedures is achieved by the construction of a set of mock-ups and prototypes to demonstrate that design requirements defined by the ITER Organization are effectively met. For each qualification item, the corresponding mock-ups are presented with the tests to be performed and the related acceptance criteria. The first qualification results are discussed. © 2015. Source

Libeyre P.,ITER Organization | Cormany C.,ITER Organization | Dolgetta N.,ITER Organization | Mitchell N.,ITER Organization | And 11 more authors.
Fusion Engineering and Design

The ITER correction coils (CC) include three sets of six coils each, distributed symmetrically around the tokamak and inserted between the toroidal field (TF) and the poloidal field (PF) coils. Each pair of coils located on opposite sides with respect to the plasma is series connected with polarity such to produce asymmetric fields. These superconducting coils use a cable-in-conduit conductor, insulated, wound into multiple pancakes and inserted inside an austenitic stainless steel case. The requirements and the main features of the design are presented and the selected options reviewed in terms of their criticality in achieving the specified tolerances. The requested qualification trials are identified and reports the results obtained so far. © 2013 Elsevier B.V. Source

Liu F.,CAS Hefei Institutes of Physical Science | Liu H.,CAS Hefei Institutes of Physical Science | Liu S.,ITER China | Liu B.,CAS Hefei Institutes of Physical Science | And 2 more authors.
Journal of Physics: Conference Series

China is in charge of most of Poloidal Field (PF) conductors production for the International Thermonuclear Experimental Reactor (ITER). The execution for PF conductors shall be in three main phases. According to ITER Procurement Arrangement (PA), the Domestic Agency (DA) shall be required to verify the room and low temperature acceptance tests carried out by the strand suppliers. As the reference laboratory of Chinese DA (CNDA), the superconducting strands test laboratory of Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) was undertaking the task of strands verification for ITER conductors. The verification test includes: diameter, Nickel plating thickness, copper-to-non-copper volume ratio, twist pitch direction and length, standard critical current (IC) and resistive transition index (n), residual resistance ration (RRR), and hysteresis loss. 48 NbTi strands with 7 billets were supplied for the PF Cable-In-Conduit Conductor (CICC) process qualification. In total, 54 samples were measured. The verification level for PF CICC process qualification was 100%. The test method, facility and results of each item are described in detail in this publication. © Published under licence by IOP Publishing Ltd. Source

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