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Journal Articles

Progress of JT-60SA Project; EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

Shirai, Hiroshi; Barabaschi, P.*; Kamada, Yutaka; JT-60SA Team

Fusion Engineering and Design, 109-111(Part B), p.1701 - 1708, 2016/11

 Times Cited Count:17 Percentile:4.88(Nuclear Science & Technology)

The JT-60SA Project has shown steady progress toward the first plasma in 2019. JT-60SA is a superconducting tokamak designed to operate in the break-even conditions for a long pulse duration with a maximum plasma current of 5.5 MA. Design and fabrication of JT-60SA components shared by EU and Japan started in 2007. Assembly in the torus hall started in January 2013, and welding work of the vacuum vessel sectors is currently on going on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so forth were or are being delivered to Naka site for installation, assembly and commissioning. This paper gives technical progress on fabrication, installation and assembly of tokamak components and ancillary systems, as well as progress of JT-60SA Research Plan being developed jointly by EU and Japanese fusion communities.

Journal Articles

Present status of manufacturing and R&Ds for the JT-60SA tokamak

Higashijima, Satoru; Kamada, Yutaka; Barabaschi, P.*; Shirai, Hiroshi; JT-60SA Team

Fusion Science and Technology, 68(2), p.259 - 266, 2015/09

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Journal Articles

JT-60SA superconducting magnet system

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:23 Percentile:11.96(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.

Journal Articles

Present status and future prospects of the JT-60SA project

Ishida, Shinichi; Barabaschi, P.*; Kamada, Yutaka; JT-60SA Team

Journal of the Korean Physical Society, 65(8), p.1221 - 1226, 2014/10

 Times Cited Count:0 Percentile:100(Physics, Multidisciplinary)

Journal Articles

Mass production of superconducting magnet components for JT-60SA

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:34.53(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 Nb$$_{3}$$Sn 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.

Journal Articles

Progress of ITER and JT-60SA magnet development in Japan

Koizumi, Norikiyo; Nunoya, Yoshihiko; Yoshida, Kiyoshi; Barabaschi, P.*

Physics Procedia, 58, p.232 - 235, 2014/00

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Assembly study for JT-60SA tokamak

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:8 Percentile:36.72(Nuclear Science & Technology)

Journal Articles

Progress of the JT-60SA project

Kamada, Yutaka; Barabaschi, P.*; Ishida, Shinichi; JT-60SA Team; JT-60SA Research Plan Contributors

Nuclear Fusion, 53(10), p.104010_1 - 104010_17, 2013/10

 Times Cited Count:57 Percentile:2.9(Physics, Fluids & Plasmas)

Journal Articles

The Manufacturing of the superconducting magnet system for the JT-60SA

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:21 Percentile:24.6(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.

Journal Articles

Overview of the JT-60SA project

Ishida, Shinichi; Barabaschi, P.*; Kamada, Yutaka; JT-60SA Team

Nuclear Fusion, 51(9), p.094018_1 - 094018_12, 2011/09

 Times Cited Count:51 Percentile:6.94(Physics, Fluids & Plasmas)

This paper overviews the achievements and plans of the JT-60SA project which has been implemented jointly by Europe and Japan since 2007, covering the objectives, performance, schedule, design and procurement activities and on-site preparations. Re-baselining of the project was completed in late 2008. All of the scientific missions are preserved with the newly designed machine to meet the cost objectives. The construction of the JT-60SA has begun with procurement activities for components of the toroidal field magnet, poloidal field magnet, vacuum vessel, in-vessel components, cryostat, power supplies in parallel with dismantling the JT-60 facilities, at the end of which the first plasma is foreseen in 2016. For exploitation, development of the JT-60SA research plan has been started jointly between Japan and Europe.

Journal Articles

Plasma regimes and research goals of JT-60SA towards ITER and DEMO

Kamada, Yutaka; Barabaschi, P.*; Ishida, Shinichi; Ide, Shunsuke; Lackner, K.*; Fujita, Takaaki; Bolzonella, T.*; Suzuki, Takahiro; Matsunaga, Go; Yoshida, Maiko; et al.

Nuclear Fusion, 51(7), p.073011_1 - 073011_11, 2011/07

 Times Cited Count:53 Percentile:6.65(Physics, Fluids & Plasmas)

Journal Articles

Status and prospect of the JT-60SA project

Ishida, Shinichi; Barabaschi, P.*; Kamada, Yutaka; JT-60SA Team

Fusion Engineering and Design, 85(10-12), p.2070 - 2079, 2010/12

 Times Cited Count:52 Percentile:2.88(Nuclear Science & Technology)

The mission of the JT-60SA project is to contribute to the early realization of fusion energy by supporting the exploitation of ITER and research towards DEMO by addressing key physics issues associated with these machines. The JT-60SA will be capable of confining break-even equivalent class high-temperature deuterium plasmas at a plasma current I$$_{p}$$ of 5.5 MA and a major radius of 3 m lasting for a duration longer than the timescales characteristic of plasma processes, pursue full non-inductive steady-state operation with high plasma beta close to and exceeding no-wall ideal stability limits, and establish ITER-relevant high density plasma regimes well above the H-mode power threshold. Re-baselining of the project was completed in late 2008 which has been worked on since late 2007, where all the scientific missions are preserved with the newly designed machine to meet the cost objectives. The JT-60SA project made a large step forward towards its construction, which now foresees the first plasma in 2016. Construction of JT-60SA begins at Naka in Japan with launching the procurement of PF magnet, vacuum vessel and in-vessel components by Japan. In this year, the procurement of TF magnet, cryostat and power supply will be launched by Europe.

Journal Articles

Development of JT-60SA superconducting magnet system

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:18 Percentile:34.77(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.

Journal Articles

Progress of JT-60SA project towards an integrated research for ITER and DEMO

Kamada, Yutaka; Ishida, Shinichi; Barabaschi, P.*; JT-60SA Team

Journal of Plasma and Fusion Research SERIES, Vol.9, p.641 - 649, 2010/08

Journal Articles

Design and construction of JT-60SA superconducting magnet system

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.

Journal Articles

Basic concept of JT-60SA tokamak assembly

Shibanuma, Kiyoshi; Arai, Takashi; Kawashima, Hisato; Hoshino, Katsumichi; Hoshi, Ryo; Kobayashi, Kaoru; Sawai, Hiroaki; Masaki, Kei; Sakurai, Shinji; Shibama, Yusuke; et al.

Journal of Plasma and Fusion Research SERIES, Vol.9, p.276 - 281, 2010/08

The JT-60 SA project is a combined project of JA-EU satellite tokamak program under the Broader Approach (BA) agreement and JA domestic program. Major components of JT-60SA for assembly are vacuum vessel (VV), superconducting coils (TF coils, EF coils and CS coil), in-vessel components such as divertor, thermal shield and cryostat. An assembly frame (with the dedicated cranes), which is located around the tokamak, is adopted to carry out effectively the assembly of tokamak components in the tokamak hall, independently of the facility cranes in the building. The assembly frame also provides assembly tools and jigs with jacks to support temporarily the components as well as to adjust the components at right positions. In this paper, the assembly scenario and scequence of the major components such as VV and TFC and the concept of the assembly frame including special jigs and fixtures are discussed.

Journal Articles

Status of JT-60SA tokamak under the EU-JA broader approach agreement

Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

 Times Cited Count:15 Percentile:25.73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ITER nuclear components, preparing for the construction and R&D results

Ioki, Kimihiro*; Akiba, Masato; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Ezato, Koichiro; Federici, G.*; et al.

Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08

 Times Cited Count:13 Percentile:32.37(Materials Science, Multidisciplinary)

The preparation of the procurement specifications is being progressed for key components. Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive tests (NDT). R&D activities are being carried out on vacuum vessel UT inspection with waves launched at an angle of 20 or 30 degree, on flow distribution tests of a two-channel model, on fabrication and testing of FW mockups and panels, on the blanket flexible support as a complete system including the housing, on the blanket co-axial pipe connection with guard vacuum for leak detection, and on divertor vertical target prototypes. The results give confidence in the validity of the design and identify possibilities of attractive alternate fabrication methods.

Journal Articles

Design improvements and R&D achievements for vacuum vessel and in-vessel components towards ITER construction

Ioki, Kimihiro*; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Gervash, A.*; Ibbott, C.*; Jones, L.*; et al.

Nuclear Fusion, 43(4), p.268 - 273, 2003/04

 Times Cited Count:19 Percentile:45.01(Physics, Fluids & Plasmas)

Although the basic concept of the vacuum vessel (VV) and in-vessel components of the ITER design has stayed the same, there have been several detailed design improvements resulting from efforts to raise reliability, to improve maintainability and to save money. One of the most important achievements in the VV R&D has been demonstration of the necessary fabrication and assembly tolerances. Recently the deformation due to cutting of the port extension was measured and it was shown that the deformation is small and acceptable. Further development of advanced methods of cutting, welding and NDT on a thick plate have been continued in order to refine manufacturing and improve cost and technical performance. With regard to the related FW/blanket and divertor designs, the R&D has resulted in the development of suitable technologies. Prototypes of the FW panel, the blanket shield block and the divertor components have been successfully fabricated.

Journal Articles

Prediction of performance in ITER-FEAT

Matsumoto, Hiroshi; Barabaschi, P.*; Murakami, Yoshiki*

Fusion Technology, 40(1), p.37 - 51, 2001/07

Recently, technical objectives of ITER were redefined aiming at the cost reduction of about 50% from the 1998 ITER design. Machine parameters which would satisfy the revised technical requirements under the engineering constraints were specified using a system code. The performance of these machines were studied and compared. As a result of these studies, final machine parameters were determined with revised conservative physics assumptions. This machine is referred as ITER-FEAT. It was shown that ITER-FEAT would achieve Q=10 in inductive operation with reasonable and conservative assumptions. Also, with an efficient current drive system and modest confinement improvement, possibility of Q=5 non-inductive operations in a steady state was shown.

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