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Shirai H.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2015

For the purpose of the early realization of fusion energy, construction of JT-60 Super Advanced (JT-60SA), a superconducting tokamak facility, is steadily proceeding in JAEA Naka Fusion Institute located in Naka city, Ibaraki prefecture, Japan, toward the first plasma in March 2019. This project is conducted under the Satellite Tokamak Programme of the Broader Approach Agreement and the Japanese national programme. It contributes to a wide range of fusion research and development, especially in conducting supportive researches for the ITER project to accomplish its technical targets, and conducting complementary researches to the ITER project necessary to design and construct a demonstration fusion power plant (DEMO). It also has an essential role to train domestic scientists and technicians, especially those in younger generation, who are expected to play leading roles in ITER and DEMO. JT-60SA, upgrade of JT-60U which used normal conducting coils, commands high-temperature and high-pressure deuterium plasmas in the breakeven condition for a long pulse duration (typically 100 s). It has powerful auxiliary heating and current drive tools using Neutral Beam Injection system and Electron Cyclotron Resonance Frequency system, several kinds of plasma stability control coils and flexible plasma shaping capability. JT-60SA is a powerful device for exploring and optimizing operation scenarios of ITER and DEMO. Major components of JT-60SA have been procured by EU and Japan; e.g. toroidal field coils, poloidal field coils, vacuum vessel (VV), thermal shields, power supply system, cryostat, cryogenic system and so forth. Some facilities previously used by JT-60U are reused with refurbishment and repair; e.g. central substation, motor generators, and so forth, to reduce overall construction cost. Performance of auxiliary heating and current drive facilities are also improved. Disassembly of JT-60U in the torus hall of Naka Fusion Institute was completed in October 2012. Assembly of JT-60SA started in January 2013. Cryostat base and three poloidal field coils were already installed in the tokamak hall, and seven 40-degree VV sectors as well as two 30-degree VV sectors put on the cryostat base are being welded on by one. Quench Protection Circuit, a power supply system fabricated by EU, was also delivered to Naka. On site assembly work has been set forward in a robust manner. In parallel with construction of JT-60SA, research plan of JT-60SA has been intensively discussed involving members of research communities in EU and Japan. In the eight principal research areas, research proposals from European and Japanese researchers have been elaborated and put together as "JT-60SA Research Plan", which is open to public and will be updated on a periodic basis in the future. Copyright © 2015 by JSME.


Kamada Y.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Ishida S.,JT 60SA Project Team
Nuclear Fusion | Year: 2013

The JT-60SA project implemented by Japan and Europe is progressing on schedule towards the first plasma in March 2019. After careful R&D, procurements of the major components have entered their manufacturing stages. In parallel, disassembly of JT-60U has been completed on time, and the JT-60SA tokamak assembly is expected to start in January 2013. The JT-60SA device, a highly shaped large superconducting tokamak with a variety of plasma control actuators, has been designed in order to contribute to ITER and to complement ITER in all the major areas of fusion plasma development necessary to decide DEMO reactor construction. Detailed assessments and prediction studies of the JT-60SA plasma regimes have confirmed these capabilities: using ITER- and DEMO-relevant plasma regimes, heating conditions, and its sufficiently long discharge duration, JT-60SA enables studies on magnetohydrodynamic stability at high beta, heat/particle/momentum transport, high-energy ion physics, pedestal physics including edge localized mode control, and divertor physics. By integrating these studies, the project provides 'simultaneous and steady-state sustainment of the key performance characteristics required for DEMO' with integrated control scenario development. © 2013 IAEA, Vienna.


Kamada Y.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Ishida S.,JT 60SA Project Team | Ide S.,Japan Atomic Energy Agency | And 11 more authors.
Nuclear Fusion | Year: 2011

The JT-60SA device has been designed as a highly shaped large superconducting tokamak with a variety of plasma actuators (heating, current drive, momentum input, stability control coils, resonant magnetic perturbation coils, W-shaped divertor, fuelling, pumping, etc) in order to satisfy the central research needs for ITER and DEMO. In the ITER- and DEMO-relevant plasma parameter regimes and with DEMO-equivalent plasma shapes, JT-60SA quantifies the operation limits, plasma responses and operational margins in terms of MHD stability, plasma transport and confinement, high-energy particle behaviour, pedestal structures, scrape-off layer and divertor characteristics. By integrating advanced studies in these research fields, the project proceeds 'simultaneous and steady-state sustainment of the key performances required for DEMO' with integrated control scenario development applicable to the highly self-regulating burning high-β high bootstrap current fraction plasmas. © 2011 IAEA, Vienna.


Ishida S.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency
Fusion Engineering and Design | Year: 2010

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. © 2010 Published by Elsevier B.V. All rights reserved.


Shirai H.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency
Fusion Engineering and Design | Year: 2015

Aiming at supporting the early realization of fusion energy, the JT-60SA Project has shown steady progress for several years toward the first plasma in 2019 under the dual frameworks: the Satellite Tokamak Programme of the Broader Approach Agreement between EU and Japan, and the Japanese national programme. JT-60SA is a superconducting tokamak designed to operate in break-even equivalent conditions for a long pulse duration (typically 100. s) with a maximum plasma current of 5.5. MA. A variety of plasma control capabilities enable JT-60SA to contribute directly to the ITER project and also to DEMO by addressing key engineering and physics issues for advanced plasma operation. Design and fabrication of JT-60SA components, shared by the EU and Japan, started in 2007. Assembly in the torus hall started in January 2013, and welding work of the vacuum vessel sectors (seven 40° sectors and two 30° sectors) is currently ongoing on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so on were or are being delivered to the 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 the JT-60SA Research Plan being developed jointly by European and Japanese fusion communities. © 2015 Elsevier B.V.


Zani L.,CEA Cadarache Center | Barabaschi P.,JT 60SA EU Home Team | Di Pietro E.,JT 60SA EU Home Team | Verrecchia M.,JT 60SA EU Home Team
IEEE Transactions on Applied Superconductivity | Year: 2015

In the framework of the JT-60 Super Advanced (JT-60SA) project, as part of its contribution to the Broader Approach Agreement, Europe provides the full toroidal field (TF) magnet system. For this purpose, Fusion for Energy (F4E) is procuring 27 km of TF conductor, which is of cable-in-conduit type, including 486 strands (2/3 NbTi and 1/3 copper) embedded into a rectangular stainless steel jacket. Since the start of procurement in 2010, the totality of strand has been manufactured, and more than half of the total conductor unit lengths have been accepted by F4E. In the course of this material fabrication, a large quality control (QC) program was established to consolidate the robustness of the quality diagnostic of both productions' follow-up. As for the TF strand production, a comprehensive campaign of critical properties evaluation was led to ensure that the TCS (temperature of current sharing) value in the operation condition is compliant with a 1-K temperature margin in the JT-60SA tokamak. From the large amount of data collected over the two-year production period, a statistic analysis is presented in the paper, together with the methodology that was used to build it. As for TF conductor production, the QC database provided hydraulic properties at low Re. In this framework, a covering QC campaign was led to crosscheck the acceptance data and, at the same time, quoting the reliability of acceptance data exploitation for predictive mass flow analyses in operation. An extra QC, including material analyses and quantitative energy-dispersive X-ray (EDX) analysis of both cable and jacket, was also performed. Highlights are mainly put to the scientific approach of the present topics investigated, but together, some considerations on the risk approach are also presented. © 2002-2011 IEEE.


Ishida S.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency
Journal of the Korean Physical Society | Year: 2014

The JT-60SA project has been implemented jointly by Europe and Japan since June 2007. After the disassembly of JT-60 from the torus hall had been completed in October 2012, the project achieved the major milestone of starting the tokamak’s assembly at the JAEA Naka site in January 2013 following the completion of the cryostat base in Europe and its transport to Japan. Procurement and assembly activities for components such as the superconducting magnet, cryogenic system, power supply, vacuum vessel, divertor and cryostat are progressing on track towards the start of operation in March 2019. In preparation for exploitation, the JT-60SA Research Plan was issued in December 2011, and the research integration activities are addressing JT-60SA data management, validation and analysis tools. This paper overviews the latest evolution of the project in terms of construction and exploitation for JT-60SA. © 2014, The Korean Physical Society.


Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency | Ishida S.,Japan Atomic Energy Agency
Fusion Engineering and Design | Year: 2011

The JT-60SA experiment is one of the three projects to be undertaken in Japan as part of the Broader Approach Agreement, conducted jointly by Europe and Japan, and complementing the construction of ITER in Europe. It is a fully superconducting tokamak capable of confining break-even equivalent deuterium plasmas with equilibria covering high plasma shaping with a low aspect ratio at a maximum plasma current of I p = 5.5 MA. In late 2007 the BA Parties, prompted by cost concerns, asked the JT-60SA Team to carry out a re-baselining effort with the purpose to fit in the original budget while aiming to retain the machine mission, performance, and experimental flexibility. Subsequently the Integrated Project Team has undertaken a machine re-optimization followed by engineering design activities aimed to reduce costs while maintaining the machine radius and plasma current. This effort led the Parties to the approval of the new design in late 2008 and hence final design and procurement activities have commenced. The paper will describe the process leading to the re-baselining, the resulting final design and technical solutions and the present status of procurement activities. © 2011 Published by Elsevier B.V.


Ishida S.,Japan Atomic Energy Agency | Barabaschi P.,JT 60SA EU Home Team | Kamada Y.,Japan Atomic Energy Agency
Nuclear Fusion | Year: 2011

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. © 2011 IAEA, Vienna.


Zani L.,CEA Cadarache Center | Barabaschi P.,JT 60SA EU Home Team | Di Pietro E.,JT 60SA EU Home Team | Verrecchia M.,JT 60SA EU Home Team
IEEE Transactions on Applied Superconductivity | Year: 2014

In the framework of the JT-60SA project, aiming at upgrading the present JT-60U tokamak, Europe, as part of its in-kind contribution within the Broader Approach agreement, will provide the toroidal field (TF) magnet system. For this purpose, Fusion for Energy is committed to procure about 29 km of TF conductor. The TF conductor is cable-in-conduit type and includes 486 strands (2/3 NbTi-1/3 copper) wrapped with a thin stainless steel foil and compacted into a rectangular stainless steel jacket. The procurement is split into two main contracts: one for TF strand manufacturing and the other for TF conductor cabling and jacketing. TF strand manufacture was completed while the TF conductor one is being finished. In the present paper, we draw an overview of both productions emphasizing on the quality control (QC) approaches and on aspects relevant to risk management of the JT-60SA tokamak operation. For the NbTi strand, the complete production overview is provided including extensive statistical considerations on NbTi strand critical performances (IC,T} \rm CS). For the TF conductor, the overview also deals with collected results from acceptance tests and peripheral tests led for consolidating the QC (hydraulic tests, nondestructive examination, full-size sample cold tests in SULTAN facility). © 2013 IEEE.

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