ITER China

Beijing, China

ITER China

Beijing, China

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Fang C.,ASIPP | Song Y.,ASIPP | Wu W.,ASIPP | Wei J.,ASIPP | And 6 more authors.
Journal of Fusion Energy | Year: 2014

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.


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 | Year: 2012

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.


Lu K.,CAS Hefei Institutes of Physical Science | Song Y.,CAS Hefei Institutes of Physical Science | Shen G.,CAS Hefei Institutes of Physical Science | Cheng Y.,CAS Hefei Institutes of Physical Science | And 13 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2014

The Procurement of Feeder system in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) for The International Thermonuclear Experimental Reactor (ITER) Tokamak device has been carrying out after the signature of Procurement Arrangement in October 2011. The relevant main tasks in 2012 and 2013 are the qualification of some key subcomponents, including high temperature superconducting current leads (HTS-CL), superconducting joints, 80-K thermal shield (TS), vacuum barrier, in-cryostat feeder, cold mass support, etc. The production of manufacturing drawings, preparation of manufacturing plan, manufacture and qualification of tooling, and qualification of subcomponents are all involved in this phase. This paper describes the progress made by ASIPP and some subcontractors for the feeder's qualification work. © 2015 IEEE.


Wei J.,CAS Hefei Institutes of Physical Science | Wu W.,CAS Hefei Institutes of Physical Science | Han S.,CAS Hefei Institutes of Physical Science | Yu X.,CAS Hefei Institutes of Physical Science | And 12 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2014

The ITER Correction Coils (CC) include three sets of six coils each, distributed symmetrically around the tokamak to correct error fields. Each pair of coils, located on opposite sides of the tokamak, is series connected with polarity to produce asymmetric fields. The manufacturing of these superconducting coils is undergoing qualification of the main fabrication processes: winding into multiple pancakes, welding helium inlet/outlet on the conductor jacket, turn and ground insulation, vacuum pressure impregnation, inserting into an austenitic stainless steel case, enclosure welding, and assembling the terminal service box. It has been proceeding by an intense phase of R&D, trials tests, and final adjustment of the tooling. This paper mainly describes the progress in ASIPP for the CC manufacturing process before and on qualification phase and the status of corresponding equipment which are ordered or designed for each process. Some test results for the key component and procedure are also presented. © 2013 IEEE.


Fang C.,ASIPP | Fang C.,Lappeenranta University of Technology | Song Y.,ASIPP | Wei J.,ASIPP | And 7 more authors.
Fusion Engineering and Design | Year: 2015

The ITER correction coil (CC) case reinforces the winding packs against the electromagnetic loads, minimizes stresses and deformations to the winding pack. The cases are made of high strength and high toughness austenitic stainless steel (316LN) hot rolled heavy plate and have a thickness of 20. mm. Considering the small cross-section and large dimensions of the case, deformation of the case when welding becomes a challenge in the case manufacturing. Therefore, laser welding was developed as the main welding technology for manufacturing. In this paper, multi-pass laser welding technology is used, the laser weldability of a 20. mm thick 316LN austenitic stainless steel plate is studied and the microstructure of the welded joint is analyzed. The welding experiment used an YLS-6000 fiber laser (IPG) and weld filler of 316LMn to match the base metal was used. The result shows that the welded joint has no obvious surface and internal defects based on the optimized welding parameters. The weld joint have a fine austenite microstructure and display columnar dendrites and cellular grains with strong directional characteristics. No apparent heat affected zone is observed and approximately 2. μm an austenite microstructure of the fusion line is clearly presented. © 2015 Elsevier B.V.


Lu K.,CAS Hefei Institutes of Physical Science | Wen X.,CAS Hefei Institutes of Physical Science | Liu C.,CAS Hefei Institutes of Physical Science | Song Y.,CAS Hefei Institutes of Physical Science | And 3 more authors.
Fusion Engineering and Design | Year: 2016

The Magnet Feeder system in the International Thermonuclear Experimental Reactor (ITER) deploys electrical currents and supercritical helium to the superconducting magnets and the magnet diagnostic signals to the operators. In the current design, the feeders located in the upper L3 level of the Tokamak gallery penetrate the Tokamak coolant water system vault, the biological shield and the cryostat. As a secondary confinement to contain the activated coolant water in the vault in the case of water pipe burst accident, a water barrier is welded between the penetration in the water pipe chase outer wall and the mid-plane of the vacuum jacket of the Feeder Coil Terminal Box (CTB). A thin-wall stainless steel diaphragm with an omega shape profile is welded around the CTB as the water barrier to endure 2. bar hydraulic pressure. In addition, the barrier is designed as a flexible compensator to withstand a maximum of 15. mm of axial displacement of the CTB in case of helium leak accident without failure. This paper presents the detail configuration, the manufacturing and assembly processes of the water barrier. Test results of the prototype water barrier under simulated accident conditions are also reported. Successful qualification of the design and manufacturing process of the water barrier lays a good foundation for the series production of this subsystem. © 2016 Elsevier B.V.


Libeyre P.,ITER Organization | Cormany C.,ITER Organization | Dolgetta N.,ITER Organization | Mitchell N.,ITER Organization | And 11 more authors.
Fusion Engineering and Design | Year: 2013

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.


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 | Year: 2014

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.


Niu E.,ITER China | Shen G.,CAS Hefei Institutes of Physical Science | Wang Z.,CAS Hefei Institutes of Physical Science | Ding K.,CAS Hefei Institutes of Physical Science
2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 | Year: 2013

The dry box (DB) is the transition section from the superconducting cables to the conventional ones; it houses the warm end of the high temperature superconducting current lead (HTS-CL) and the water-cooled cables, as well as the joint between them. The main function of the DB can be divided into two types, the thermal function provides a dry environment for the HTS-CL to prevent condensation on the warm end of the lead, which comes from the excess helium gas cooling power of the lead; on the other hand, the mechanical function supports the heavy joint and the water-cooled cables, which should be easy to connect and remove, meanwhile the strengthen should be enough. Therefore, the chamber is filled with hot dry air with positive pressure to the atmosphere outside, the natural and forced convection, as well as the electrical heater and thermal insulation layer are discussed. This paper describes these efforts. © 2013 IEEE.


Niu E.,ITER China | Wang Z.,Chinese Academy of Sciences | Shen G.,Chinese Academy of Sciences | Zhang S.,Chinese Academy of Sciences
2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 | Year: 2013

The TF Feeder delivers electricity and coolant to the superconducting TF coil, the superconducting busbar and supercritical helium pipe are all work at 4K. Without proper thermal insulation designs, the heat load from room environment will make it impossible to keep the busbar and the coil superconducting, thus numerous and accurate thermal analyses are performed to verify the design. It is vacuum inside the Feeder chambers, and the heat load mainly comes from the support conduction and the thermal radiation; 80K thermal shield, thermal intercept and low thermal conductivity support material are employed to minimize the heat load. Since the Feeder is a huge structure over 10m in length, it costs time for it to be cooled down, there must be a delay compared to the active cooled TF coils. Therefore, the cool down time is also researched in this paper. © 2013 IEEE.

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