Overview of engineering design, manufacturing and assembly of JT-60SA machine

Pietro, E. Di; Barabaschi, P.; Kamada, Y.; Ishida, S.

doi:10.1016/j.fusengdes.2013.11.015

Cited by 27 publications

(7 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The machine is fully superconductive [3], similarly to the largest tokamaks in operation (e.g. KSTAR [4] and EAST [5]), commissioned (JT-60SA [6]) and under construction (ITER [7], SPARC [8]) worldwide. Like in the JT-60SA design, the current to the superconducting (SC) magnets arrives from the power supply at room temperature through the busbar to the current leads, contained in the Cold Terminal Boxes (CTB).…”

Section: Introductionmentioning

confidence: 99%

Techno-Economic Optimization of the NbTi DTT Feeders

et al. 2023

View full text Add to dashboard Cite

The superconducting (SC) coils of the Divertor Tokamak Test (DTT) facility will be connected to the current leads by a set of SC feeders, currently designed as cable-in-conduit conductors wound using commercial NbTi strands to be cooled by Supercritical Helium at 4.5 K. The feeders are immersed in the magnetic field generated by the SC coil and plasma outside of magnet system, so that the maximum field on the most loaded feeder can reach 4 T at the full rated current (including the self-field effect). Here the performance of the feeder conductors is assessed during a plasma pulse, based on the DTT standard singlenull operating scenario, for the most loaded feeder of the Central Solenoid and of the Toroidal and Poloidal Field coils, computing the minimum temperature margin to current sharing throughout the plasma scenario. Several alternative cabling configurations are analyzed, designed to withstand the nominal current at the peak field with a different number of SC and stabilizer strands. A figure of merit is built parametrically based on the variation of the minimum temperature margin as a function of the material, manufacturing and operational costs of the different alternative feeder layouts. Based on such techno-economical characterization, the optimal (cheapest) design of the feeder cables is identified.INDEX TERMS DTT facility, Superconducting cables, Cable-in-conduit conductors, current leads, temperature margin, techno-economic analysis FIGURE 1. Layout of the SC feeders and cryolines for the DTT machine: CSCL: Central Solenoid Current Leads box; PFCL: Poloidal Field Current Leads box; and TFCL (bottom left) Toroidal Field Current Leads box.

show abstract

Section: Introductionmentioning

confidence: 99%

Techno-Economic Optimization of the NbTi DTT Feeders

et al. 2023

View full text Add to dashboard Cite

show abstract

“…The JT-60SA [1][2][3][4] project was initiated in June 2007 under the framework of the Broader Approach (BA) Agreement and Japanese National Fusion Programme for an early realization of fusion energy by conducting supportive and complementary work for the ITER project towards supporting the basis for DEMO. In 2009, after a complex start-up phase due to the necessity to carry out a re-baselining effort to fit in the original budget while aiming to retain the machine mission, performance, and experimental flexibility, the detailed design of the project could start immediately followed by the start of manufacturing of the long lead items.…”

Section: Introductionmentioning

confidence: 99%

Progress of the JT-60SA project

Barabaschi¹,

Kamada²,

Shirai³

2019

Nucl. Fusion

View full text Add to dashboard Cite

The JT-60SA project was initiated in June 2007 under the framework of the Broader Approach Agreement and Japanese National Fusion Programme for an early realization of fusion energy by conducting supportive and complementary work for the ITER project towards supporting the basis for DEMO. With the project now in an advanced implementation stage, the early defined approach for its implementation has proven to be successful and hence continues to be employed. This is underpinned by the very close collaboration between QST in Japan, F4E in Europe, and all other European stakeholders: the EU Voluntary Contributors and EUROfusion. As of September 2018, the closure of the torus has been accomplished. All TF coils have been manufactured, tested at full current and cryogenic temperature demonstrating a consistent temperature margin, and assembled. All manufacturing of equilibrium field coils was completed by the middle of August 2016. Three central solenoid (CS) modules were completed by March 2017 while manufacturing of the last CS module has recently been completed. The manufacture and delivery of all 26 high temperature superconductor current leads was completed in November 2017. All large power systems, including the switching network units and super conducting magnet power supplies, have also been manufactured, delivered and with few residual commissioning activities still ongoing in Naka. With the cryostat base already in place since 2013, the cryostat vessel body cylindrical section has been manufactured, preassembled, measured and delivered to Naka. The full scope of the cryoplant, manufacturing and commissioning, is now successfully completed. The final assembly phase has therefore started together with the gradual execution of integrated commissioning leading to the completion of the assembly in March 2020 and a first plasma in September 2020. The efficient start-up and scientific exploitation of JT-60SA by the large international team is a challenging enterprise, which will be similar to, and provide important input to, the ITER start-up phase. To optimize this phase, a broad set of coordinated activities have been carried out over recent years by a joint Japanese-EU JT-60SA research unit, fully integrated in the integrated project team and liaising with the broader Japanese and EU fusion physics community. The paper will provide an overview of the progress of the manufacturing and assembly of the JT-60SA machine towards first plasma, and progress in preparing for the next phases of JT-60SA following this milestone.

show abstract

“…JT-60SA (super advanced) is a superconducting tokamak under construction in the Naka Fusion Institute of the National Institutes for Quantum and Radiological Science and Technology (QST). The mission of the JT-60SA project [1][2][3][4] is to contribute to an early realization of fusion energy by addressing key physics and engineering issues for ITER [5] and demonstration fusion reactors (DEMO) [6,7] by utilizing JT-60SA. Figure 1 is a schematic view of the JT-60SA tokamak.…”

Section: Introductionmentioning

confidence: 99%

Recent progress of the JT-60SA project

Shirai

Barabaschi²,

Kamada

2017

Nucl. Fusion

View full text Add to dashboard Cite

The JT-60SA project has been implemented for the purpose of an early realization of fusion energy. With a powerful and versatile NBI and ECRF system, a flexible plasma-shaping capability, and various kinds of in-vessel coils to suppress MHD instabilities, JT-60SA plays an essential role in addressing the key physics and engineering issues of ITER and DEMO. It aims to achieve the long sustainment of high integrated performance plasmas under the high βN condition required in DEMO. The fabrication and installation of components and systems of JT-60SA procured by the EU and Japan are steadily progressing. The installation of toroidal field (TF) coils around the vacuum vessel started in December 2016. The commissioning of the cryogenic system and power supply system has been implemented in the Naka site, and JT-60SA will start operation in 2019. The JT-60SA research plan covers a wide area of issues in ITER and DEMO relevant operation regimes, and has been regularly updated on the basis of intensive discussion among European and Japanese researchers.

show abstract

Overview of engineering design, manufacturing and assembly of JT-60SA machine

Cited by 27 publications

References 7 publications

Techno-Economic Optimization of the NbTi DTT Feeders

Techno-Economic Optimization of the NbTi DTT Feeders

Progress of the JT-60SA project

Recent progress of the JT-60SA project

Contact Info

Product

Resources

About