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Koide, Yoshihiko; Yoshida, Kiyoshi; Wanner, M.*; Barabaschi, P.*; Cucchiaro, A.*; Davis, S.*; Decool, P.*; Di Pietro, E.*; Disset, G.*; Genini, L.*; et al.
Nuclear Fusion, 55(8), p.086001_1 - 086001_7, 2015/08
Times Cited Count：31 Percentile：83.35(Physics, Fluids & Plasmas)The most distinctive feature of the superconducting magnet system for JT-60SA is the optimized coil structure in terms of the space utilization as well as the highly accurate coil manufacturing, thus meeting the requirements for the steady-state tokamak research: A conceptually new outer inter-coil structure separated from the casing is introduced to the toroidal field coils to realize their slender shape, allowing large-bore diagnostic ports for detailed plasma measurements. A method to minimize the manufacturing error of the equilibrium-field coils has been established, aiming at the precise plasma shape/position control. A compact butt-joint has been successfully developed for the Central Solenoid, which allows an optimized utilization of the limited space for the Central Solenoid to extend the duration of the plasma pulse.
Murakami, Haruyuki; Kizu, Kaname; Ichige, Toshikatsu; Furukawa, Masato; Natsume, Kyohei; Tsuchiya, Katsuhiko; Kamiya, Koji; Koide, Yoshihiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; et al.
IEEE Transactions on Applied Superconductivity, 25(3), p.4201305_1 - 4201305_5, 2015/06
Times Cited Count：6 Percentile：34.26(Engineering, Electrical & Electronic)JT-60U magnet system will be upgraded to the superconducting coils in the JT-60SA programme of the Broader Approach activities. Terminal joint of Central Solenoid (CS) is wrap type Nb
Sn-NbTi joint used for connecting CS (NbSn) and current feeder (NbTi). The terminal joints are placed at the top and the bottom of the CS systems. CS modules located at middle position of CS system need the lead extension from the modules to the terminal joint. The joint resistance measurement of terminal joint was performed in the test facility of National Institute for Fusion Science. The joint resistance was evaluated by the operating current and the voltage between both ends of the terminal joint part. Test results met the requirement of JT-60SA magnet system. The structural analysis of the lead extension and its support structure was conducted to confirm the support design. In this paper, the results of resistance test of joint and the structural analysis results of lead extension are reported.
Yoshida, Kiyoshi; Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Kamiya, Koji; Koide, Yoshihiko; Phillips, G.*; Zani, L.*; Wanner, M.*; Barabaschi, P.*; et al.
IEEE Transactions on Applied Superconductivity, 24(3), p.4200806_1 - 4200806_6, 2014/06
Times Cited Count：13 Percentile：56.48(Engineering, Electrical & Electronic)The upgrade of the JT-60U magnet system to the superconducting coils (JT-60SA) is progressing as a satellite facility for ITER by Japan and EU in the BA agreement. All components of magnet system are now under manufacturing in mass production. The first superconducting EF conductor was manufactured in 2010 in Japan. First superconducting coil EF4 was manufactured in 2012. Other EF5 and EF6 coils shall be manufactured by 2013 to install temporally on the cryostat base before the assembly of the plasma vacuum vessel. CS model coil is fabricated to qualify all manufacturing process of NbSn conductor. The first TF conductor was manufactured in 2012. The cryogenic requirements for JT-60SA are about 9 kW at 4.5K. Each coil is connected through an in-cryostat feeder to the current leads located outside the cryostat in the CTB. A total of 26 HTS current leads are installed in the CTB. The manufacturing of the magnet system is in progress to provide components to assembly the Tokamak machine.
Kamiya, Koji; Furukawa, Masato; Hatakenaka, Ryuta*; Miyakita, Takeshi*; Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Koide, Yoshihiko; Yoshida, Kiyoshi
AIP Conference Proceedings 1573, p.455 - 462, 2014/01
Times Cited Count：5 Percentile：90.59(Thermodynamics)The thermal shield of JT-60SA is kept at 80 K and will use the Multi Layered Insulator (MLI) to reduce radiation heat load to the superconducting coils at 4.4 K from the cryostat at 300 K. Due to plasma pulse operation, the MLI is affected by eddy current in toroidal direction. The MLI is designed to suppress the current by electrically insulating every 20 degree in the toroidal direction by covering the MLI with polyimide films. In this paper, two kinds of designs for insulated MLI are proposed focusing on a way to overlap MLI. A boil-off calorimeter method and temperature measurement has been performed to determine the thermal performance of MLI. The design of electrical insulated thermal anchor between the toroidal field (TF) coil and the thermal shield is also explained.
Yoshida, Kiyoshi; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Honda, Atsushi; Onishi, Yoshihiro; Furukawa, Masato; Asakawa, Shuji; Kuramochi, Masaya; Kurihara, Kenichi
Fusion Engineering and Design, 88(9-10), p.1499 - 1504, 2013/10
Times Cited Count：6 Percentile：44.02(Nuclear Science & Technology)The modifying of the JT-60U magnet system to the superconducting coils (JT-60SA) is progressing as a satellite facility for ITER by both parties of Japanese government and European commission (EU) in the Broader Approach agreement. The magnet system for JT-60SA consists of 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with 4 modules, and 6 Equilibrium Field (EF) coils. The manufacturing of the JT-60SA magnet system is in progress in EU and Japan. The JT-60SA superconducting magnet system generates an average heat load of 3.2 kW at 4 K to the cryoplant, from nuclear and thermal radiation, conduction and electromagnetic heating, and requires current supplies 20 kA for 4 CS modules and 6 EF coils, 25.7 kA to 18 TF coils. The helium flow to remove this heat, consisting of supercritical helium at pressures up to 0.5 MPa and temperature between 4.4-4.8 K, is distributed to the coils and structures through the valve box (VB) from the cryoline connecting to the auxiliary cold box located outside the torus hall. The feeders also contain the electrical supplies from the current lead transitions to room temperature to the coil. The feeder components consist of the in-cryostat feeders with flexible parts to allow coil operational displacements from the connection pipes out of the cryostat, including S-bend conductor to allow differential thermal contraction and the coil terminal boxes (CTBs) with HIS current leads. A measurement and control system is required to monitor and control these coils and feeders for safety and optimal operational availability. For each coil, both current and supercritical helium are supplied from external systems and are controlled from a central system as part of the regular operation with plasma pulses. Quench detection instruments for superconducting coils, feeders and HTS current leads are provided as a separate, stand alone system.
Shibanuma, Kiyoshi; Arai, Takashi; Hasegawa, Koichi; Hoshi, Ryo; Kamiya, Koji; Kawashima, Hisato; Kubo, Hirotaka; Masaki, Kei; Saeki, Hisashi; Sakurai, Shinji; et al.
Fusion Engineering and Design, 88(6-8), p.705 - 710, 2013/10
Times Cited Count：10 Percentile：61.16(Nuclear Science & Technology)Yoshida, Kiyoshi; Kizu, Kaname; Tsuchiya, Katsuhiko; Murakami, Haruyuki; Kamiya, Koji; Payrot, M.*; Zani, L.*; Wanner, M.*; Barabaschi, P.*; Heller, R.*; et al.
IEEE Transactions on Applied Superconductivity, 22(3), p.4200304_1 - 4200304_4, 2012/06
Times Cited Count：22 Percentile：70.54(Engineering, Electrical & Electronic)The JT-60SA is progressing as a "satellite" facility for ITER in the Broader Approach agreement. The fabrications of the conductor for CS and EF coils were started in 2008. The first superconducting conductor of EF4 coil was manufactured at March 2010. The manufacturing tools for EF coils are design and prepared from 2009. The double pancake using the superconductor has been started at 2011. The TF coil case encloses the winding pack and is the main structural component of the magnet system. The interface between TF case and CS and EF coil were designed. The conductor for TF coils fabrication has been started. The cryogenic system is equivalent to be about 9 kW refrigeration at 4.5 K. Each coil is electrically connected through the in-cryostat feeder and the coil terminal boxes. The 26 current leads using high temperature superconductor. The manufacturing of superconducting magnet for JT-60SA are started by solving its cost and technology.
Kamiya, Koji; Onishi, Yoshihiro; Ichige, Toshikatsu; Furukawa, Masato; Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Mizumaki, Shoichi*
Proceedings of 24th International Cryogenic Engineering Conference (ICEC 24) and International Cryogenic Materials Conference 2012 (ICMC 2012) (CD-ROM), p.587 - 590, 2012/05
The JT-60 plans to be upgraded to a full-superconducting tokamak referred as the JT-60 Super Advance (JT-60SA) as one of the JA-EU broader approach projects. In the JT-60SA, the superconducting magnets are surrounded by thermal shield cooled at 80 K, which is categorized into 3 groups; the vacuum vessel thermal shield (VVTS), the port thermal shield (PTS) and the cryostat thermal shield (CTS). In this study, seismic analysis was conducted for the thermal shield to confirm the soundness of the latest design, taking the dynamical analysis into account. Trial manufacturing of a 10 degree outer VVTS was also conducted. The outer VVTS was subsequently assembled with already existing inner VVTS to measure the total tolerance (manufacturing plus assembly). It was found that the total tolerance was 5.2 mm which is less than the target tolerance of 10 mm. Finally, concept and the current status of the JT-60SA cryodistribution design are reported.
Murakami, Haruyuki; Kizu, Kaname; Ichige, Toshikatsu; Kamiya, Koji; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Hamaguchi, Shinji*; Takahata, Kazuya*; Yanagi, Nagato*; et al.
Proceedings of 24th International Cryogenic Engineering Conference (ICEC 24) and International Cryogenic Materials Conference 2012 (ICMC 2012) (CD-ROM), p.575 - 578, 2012/05
The JT-60U magnet system will be upgraded to the superconducting coils (JT-60SA) in the Broader Approach (BA) project. The JT-60SA magnet system has 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with 4 modules and 6 Equilibrium Field (EF) coils. The CS conductors are designed with NbSn cable in conduit (CIC) conductor because the magnetic field of CS is up to 8.9 T. The short CS conductor was manufactured and processed into the performance verification test sample. The Tcs test results indicate that the initial Tcs of the CS conductor is about 2 K higher than the minimum requirement of the conductor design. In addition the Tcs after the repetition excitation is more important issues for the CS conductor because the CS conductor is made of NbSn strand. The Tcs changes with the repetition excitation and the influence of the warm up and cool down process on the Tcs were measured. The test results show that there is no degradation while the repetition excitation tests. The AC loss test of the CS conductor was also performed for precise estimation of the conductor heat loads. The Tcs margin analysis of the CS conductor was conducted based on the latest conductor heat loads. The analysis results show that the CS conductor has enough Tcs margin during the JT-60SA operation. These results show that the design and the manufacturing process of the CS conductor satisfy its requirements. Thus CS conductors for the CS1 module have been manufactured on the mass production process. In this paper, the Tcs test, the repetition excitation test, the AC loss test and the Tcs margin analysis of the CS conductor are described.
Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Kamiya, Koji; Takahashi, Yoshikazu; Yoshida, Kiyoshi
Fusion Engineering and Design, 87(1), p.23 - 29, 2012/01
Times Cited Count：10 Percentile：60.35(Nuclear Science & Technology)The JT-60 is planned to be modified to a full-superconducting tokamak. The maximum temperature of the magnet during its quench might reach the temperature of higher than several hundreds Kelvin that will damage the magnet itself. The high precision quench detection system, therefore, is important in the protection system. The disk-shaped pickup coils are inserted in the CS module for quench detection. Thus we improved the analysis model to evaluate the applicability of the disk-shaped pickup coils to quench detection system during the fast plasma event, such as disruption, by introducing the passive coil series such as vacuum vessel and stabilizer. The analysis results show that the disk-shaped pickup coil is applicable whenever the standard operation and fast plasma event. Additionally, the pickup coil design method is also modified to reduce the total cost of protection system. In this paper, the improved analysis method, modified design method and those results are described.
Kamiya, Koji; Ichige, Toshikatsu; Honda, Atsushi; Yoshida, Kiyoshi
Proceedings of International Cryogenic Engineering Conference 23 (ICEC-23) and International Cryogenic Materials Conference 2010 (ICMC 2010), p.797 - 802, 2011/07
The JT-60 is planned to be upgraded to a full-superconducting tokamak referred as the JT-60 Super Advance (JT-60SA) as one of the JA-EU Broader Approach projects. In the JT-60SA, the superconducting magnets are to be surrounded with the thermal shield to reduce the radiation heat from the plasma vacuum vessel and from the ambient temperature. This study describes the design concept and current status of the JT-60SA thermal shield followed by thermal analysis focusing on the vacuum vessel side thermal shield (VVTS). Subsequently, the structural analysis in the plasma operation mode and at assembly was conducted. Finally, the trial model of the 10 degree VVTS and its manufacturing tolerance are presented.
Kamiya, Koji; Murakami, Haruyuki; Kizu, Kaname; Ichige, Toshikatsu; Yoshida, Kiyoshi
Teion Kogaku, 46(1), p.10 - 17, 2011/01
JT-60SA project replaces the JT-60U tokamak with a full superconducting tokamak. The helium refrigerator cools the superconducting coils by circulating 4.4 K, 0.6 MPa supercritical helium in the circulation loop at certain mass flow rate. Since the cooling power of the helium refrigerator is determined by the heat load of the superconducting coils, estimation of the heat generation and required mass flow rate to acquire sufficient temperature margin is of crucial importance. In this paper, optimizing the mass flow rate in the superconducting coils was attempted to satisfy 1 K temperature margin. Then, it is shown that the consequent maximum pressure drop in the circulation loop is 81 kPa to result in minimizing the heat load of the supercritical helium circulation pump.
Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Obana, Tetsuhiro*; Takahata, Kazuya*; Peyrot, M.*; Barabaschi, P.*
Physica C, 470(20), p.1727 - 1733, 2010/11
Times Cited Count：26 Percentile：69.32(Physics, Applied)The upgrade of JT-60U magnet system to superconducting coils (JT-60SA) is carried out by both parties of Japanese government and European commission (EU) in the framework of the Broader Approach (BA) agreement. The magnet system for JT-60SA consists of 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with four modules, six Equilibrium Field (EF) coils. The TF coil case encloses the winding pack and is the main structural component of the magnet system. The CS consists of four independent winding pack modules, which is support from the bottom of the TF coils. The six EF coils are attached to the TF coil cases through supports with flexible plates allowing radial displacements. The construction of CS and EF coils was started in 2008 in Japan. The construction of TF coils was started in 2009 in EU. This paper introduces the design of JT-60SA superconducting magnet and the design and experimental activities in Japan.
Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Peyrot, M.*; Barabaschi, P.*
Journal of Plasma and Fusion Research SERIES, Vol.9, p.214 - 219, 2010/08
The upgrade of JT-60U magnet system to superconducting coils (JT-60SA) is carried out by both parties of Japan and European commission (EU) in the framework of the Broader Approach agreement. The magnet system for JT-60SA consists of 18 Toroidal Field (TF) coils, a Central Solenoid (CS) with four modules, six Equilibrium Field (EF) coils. The TF coil case encloses the winding pack and is the main structural component of the magnet system. The CS consists of four independent winding pack modules, which is support from the bottom of the TF coils. The six EF coils are attached to the TF coil cases through supports with flexible plates. The feeder system is connected from each coil to the helium refrigerator and power supply. High temperature superconducting current leads are installed in the coil terminal box. The construction of CS and EF coils was started in 2008 in Japan.
Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji
no journal, ,
The upgrade of JT-60U magnet system to superconducting coils (JT-60SA) is carried out by both parties of Japan and EU in the framework of the Broader Approach agreement. In Japan, trail fabrication of superconducting conductors for the central solenoid (CS) and equilibrium field (EF) coils are progressed in short length (30m). The side of jackets is fixed by short length conductor sample. Detailed design of CS and EF coils are competed. the contract for CS and EF coil fabrication are started to design the manufacturing tools and to select an insulation material. The detailed design for thermal shield and helium distribution is progressed in Japan. In EU, the detailed design of the TF coils is competed. The assembly process to the tokamak is under studied to define geometric interface. The detailed design of the helium refrigerator and the high temperature current leads are progressed in EU.
Kamiya, Koji; Takenouchi, Tadashi; Ichige, Toshikatsu; Yoshida, Kiyoshi
no journal, ,
JT-60SA, which is planned to use superconducting magnets for plasma confinment, will use a thermal shield cooled at 80K as a radiation shield for 4K magnets. Therefore, the shape of the thermal shield strongly depends on the shape of the superconducting magnets. The specification and the shape of the toroidal field coil has been fixed this year, and 110 mm clearance between plasma vacuum vessel and the magnets has been acquired. In the present publication, the thermal shield has been designed in the 110 mm clearance and the thermal analysis has been conducted for a part of it.
Komeda, Masao*; Kamiya, Koji; Honda, Atsushi; Takenouchi, Tadashi; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Kamiya, Koji; Ichige, Toshikatsu; Yoshida, Kiyoshi
no journal, ,
JT-60SA, which plans to replace all coils for the plasma confinement with superconductor, needs to enclose the superconducting coils with the thermal shield in order to reduce the radiation heat load from the ambient temperature. The thermal shield on the plasma vacuum vessel side (VVTS) requires the manufacturing and assembly torelance with high accuracy due to the narrow space between the toroidal field coil and the VVTS. Therefore, it is important to determine the manufacturing torelance from the trial manufacturing for the VVTS design. In this talk, the results including the VVTS manufacturing torelance determined from the trial manufacturing are presented.
Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji; Kashiwa, Yoshitoshi; Honda, Atsushi; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Komeda, Masao*; Kamiya, Koji; Honda, Atsushi; Takenouchi, Tadashi*; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
