JT 60SA European Home Team

Garching bei München, Germany

JT 60SA European Home Team

Garching bei München, Germany
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Polli G.M.,ENEA | Cucchiaro A.,ENEA | Cocilovo V.,ENEA | Corato V.,ENEA | And 6 more authors.
Fusion Engineering and Design | Year: 2017

ENEA, in the framework of Broader Approach program for the early realization of fusion with the construction of JT-60SA tokamak, is procuring 9 of the 18 TF coils of JT-60SA magnet system. Within 2016 five coils will be completed and delivered to the cold test facility in Saclay, France, for the final acceptance tests before their shipment to Naka site for the assembly. Manufacturing has been divided in two main production steps: winding pack (WP) manufacturing and integration into casing. All the nine WPs have been already completed on September 2015 and the final integration phase has started in 2015 for the first coil. The integration, in its turn, is composed of six sub-steps: insertion, welding, embedding impregnation, final machining of interface areas, He piping assembly and final acceptance tests. Each of these steps has been already accomplished and two coils have been delivered to Saclay and undergone the cryogenic acceptance tests. This paper provides an overview and intermediate assessment of the contract that ENEA signed with ASG Superconductors for this supply. © 2017 Elsevier B.V.


Lacroix B.,French Atomic Energy Commission | Portafaix C.,French Atomic Energy Commission | Duchateau J.L.,French Atomic Energy Commission | Hertout P.,French Atomic Energy Commission | And 4 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2012

In the framework of the JT-60SA project, a parametric study was performed on the He mass flow rate cooling the Toroidal Field (TF) system. This mass flow is a crucial design parameter, since a high value is favorable regarding the temperature margin criterion, but requires more circulation power thus generating one of the main cryogenic loads. The study was led with the Tacos/Texto tool, based on Ansys (thermal) and Gandalf (thermohydraulics) codes. The impact of the TF conductor mass flow was analyzed, regarding on the one hand the temperature margin criterion, and on the other hand cryogenic aspects such as the TF magnet heat loads smoothing and the impact on the overall cryogenic system loads. Concerning the temperature margin criterion, the analysis showed that the foreseen nominal value of 4 g/s per conductor is appropriate for the studied reference scenario, while proposing a lower mass flow value in case of less demanding operation conditions, notably without or with low neutron heating. In such conditions, a TF mass flow limitation could bring an appreciable reduction of cryogenic loads, but shouldn't involve significant benefit regarding heat load smoothing. © 2011 IEEE.


Duchateau J.L.,French Atomic Energy Commission | Turck B.,French Atomic Energy Commission | Lacroix B.,French Atomic Energy Commission | Schwarz M.,Karlsruhe Institute of Technology | And 2 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2012

Under fast magnetic field variations, ac losses are deposited in a Cable in Conduit Conductor (CICC). The corresponding power losses are transferred to helium thanks to the high wetted perimeter of the conductor. The critical energy of the CICC can be expected to be proportional to the high volumetric heat capacity of helium and to the temperature margin. To confirm the expectations, stability tests under a transversal pulsed magnetic field were performed in the Sultan test facility on a prototype JT-60SA conductor sample. The shape of the magnetic field variation as a function of time is a truncated sinusoid. The experimental results are not totally in agreement with expected behavior on two particular points: the deposited energy in the conductor as a function of the pulsed field amplitude, measured by calorimetry, deviates from the expected quadratic behavior for coupling losses. The deviation is also increasingly dependent on the transport current at a given Sultan background magnetic field, the critical energies at low temperature margins are reduced in comparison with expected values. An explanation based on the saturation of parts of the cable is proposed. © 2011 IEEE.


Zani L.,JT 60SA European Home Team | Barabaschi P.,JT 60SA European Home Team | Bruzzone P.,Paul Scherrer Institute | Ciazynski D.,CEA Cadarache Center | And 6 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

In the framework of the JT-60SA project, included inside the Broader Approach agreement, EU is expected to provide to JA the totality of the toroidal field (TF) magnet system. It consists in 18 coils, evenly shared for in-kind procurement between France and Italy while the TF conductor providing is under the responsibility of Fusion for Energy. The conductor is a rectangular-shaped, NbTi-based, cable-in-conduit (CICC) and will be wound in double-pancake inside the TF casing. In the paper, the experimental approach of conductor design validation process and the associated analyses of conductor samples test campaign in the SULTAN facility are shown. A design and manufacture action on full-size SULTAN-type short samples for the TF conductor have been launched in 2007 to allow an early gathering of relevant information enabling to proceed onto the conductor design qualification process. A serie of two pre-prototypes was realized, based on a former conductor design which even if slightly different from the most up-to-date layout, includes all its important relevant features: square-shaped section, superconducting strands segregation with copper, no subwrapping. The samples are designed to allow comparative studies on shape influence (two types of sections) and on joint influence (presence or not of a bottom joint), and to provide a consolidated baseline for making decisions on conductor final design. A descriptive part of the samples manufacturing activity is included. The samples TFCS1 and TFJS1 were then characterized in the SULTAN facility (Villigen, CH) respectively in 2008 and 2009, experiencing DC tests, AC tests, mechanical cycling, and stability tests. The corresponding results and the associated analyses are shown and statements regarding the contribution of the present results to the assessment of the actual JT-60SA TF conductor design are also drawn. © 2006 IEEE.


Tsuchiya K.,Japan Atomic Energy Agency | Kizu K.,Japan Atomic Energy Agency | Murakami H.,Japan Atomic Energy Agency | Asakawa S.,Japan Atomic Energy Agency | And 3 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

PA (procurement arrangement) for poloidal field (PF) coil system, which consists of the central solenoid (CS) and the equilibrium field (EF) coils, was agreed between Japan and EU. During this activity, design of PF coils system was continued to be modified. For CS, material for the jacket of this conductor was changed into stainless steel (316LN) to make providing easier. In the modified material, maximum stress at the jacket was kept within the allowable limit. Accompanying this modification, the amount of pre-compress had to be re-estimated. Therefore, it was clarified that designs of pre-compression and tie plates need not to be major modification. For EF coils, positions and the number of turns were modified since the progress of the research for the plasma operations required in JT-60SA. Due to this optimization, total amount of superconducting material was reduced. The detail designs of PF coils were also performed to reduce the materials of supports and to evaluate the mechanical strength considering the various events. Thickness of clamp plate of the EF coil which received relatively small electromagnetic force was able to be reduced. Regarding the design of support legs with flexible plate, deformation of toroidal field (TF) coil was considered that should be included the evaluation of stress at this parts because this parts are directly attached on the TF coil case. Therefore, the revised designs of supports with sufficient mechanical strength were obtained for EF1 and EF4. © 2006 IEEE.


Muzzi L.,ENEA | Corato V.,ENEA | De Marzi G.,ENEA | Di Zenobio A.,ENEA | And 8 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

In the framework of the JT-60SA design activities, EU home team has defined a reference layout for the Toroidal Field conductor: it is a slightly rectangular Cable-In-Conduit NbTi conductor, operating at 25.7 kA with a peak field of 5.65 T. ENEA has assigned LUVATA Fornaci di Barga the task to produce the strands and to perform cabling, whereas jacketing and compaction have been carried out in its own labs. The sample, successfully tested at the CRPP SULTAN facility, has been assembled in such a way as to avoid the bottom joint between the two legs, thus using a single conductor length (about 7 m). An ad-hoc developed solution to restrain the U-bent conductor section (where jacket is not present), consisting in a stainless steel He-leak tight box with an inner structure designed in order to completely block the cable, has been also developed and manufactured by ENEA, where the sample has been also assembled. Instrumentation installation and final assembly of the sample have been performed by the SULTAN team. The main aspects of the sample manufacturing and characterization are here presented and discussed. © 2006 IEEE.


Portafaix C.,French Atomic Energy Commission | Barabaschi P.,JT 60SA European Home Team | Gauthier F.,French Atomic Energy Commission | Hertout P.,French Atomic Energy Commission | And 5 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2010

In the framework of the EU participation to JT-60SA project, a pseudo-3D thermo hydraulic tool was developed in order to address reliably the choice between multiple design options on the TF coils design. © 2006 IEEE.


Cucchiaro A.,ENEA | Polli G.M.,ENEA | Cocilovo V.,ENEA | Drago G.,ASG Superconductors | And 5 more authors.
Fusion Engineering and Design | Year: 2013

In the framework of the Broader Approach Agreement for the construction of the JT-60SA tokamak, ENEA is in charge to provide 9 of the 18 Toroidal Field (TF) coils. The 9 coils are being manufactured by ASG superconductors in Genoa under the supervision of ENEA in collaboration with the JT-60SA European home team. Prior the manufacturing, a preparatory activity has been carried out aimed at designing, constructing and setting-up the relevant components to be realized. In order to get confidence of some special manufacturing process, several qualification activities have been performed. In this paper an overview of the principal milestones reached during the preparatory phase and a description of the qualification activities with relevant test results are presented. © 2013 Elsevier B.V.


Nunio F.,French Atomic Energy Commission | Davis S.,JT 60SA European Home Team | Decool P.,French Atomic Energy Commission | Disset G.,French Atomic Energy Commission | And 5 more authors.
IEEE Transactions on Applied Superconductivity | Year: 2014

The 18 toroidal field coils of the JT-60SA are mechanically linked by the so called 'Outer Intercoil Structure' (OIS). Each OIS is bolted to its neighbors by five splice plates: this presents the double advantage of facilitating the assembly of the structure as well as ensuring an efficient electrical insulation by the insertion of an epoxy-glass sheet between the clamping stainless-steel parts. Since strong electromagnetic loads are carried by these OIS, the bolting requires a high preload to provide a significant contact pressure and thus prevent the slippage of the splice plates. We identified some critical issues that are associated with this bolted joint: the sliding behavior at the cryogenic temperature, the risk of creep of the epoxy-glass spacers during the long period of the assembly phase, and the high stress levels developed in the bolting. In this paper, we present the results of the qualification tests for several components of the fastening parts of the OIS. Two mockups of the connection were tested at room temperature and at 4 K to measure the sliding coefficient between the stainless steel and the glass-epoxy faying surfaces. The loss of preload in the bolts due to the hydraulic tightening process has also been measured on different scaled mockups. The effectiveness of the titanium washers used to compensate the loss of preload due to the difference in the thermal shrinkage between the steel and the glass-epoxy components has also been validated. Finally, the creep behavior of the insulation has been investigated by testing the glass-epoxy samples on a specially designed testing device. © 2002-2011 IEEE.


Zani L.,JT 60SA European Home Team | Barabaschi P.,JT 60SA European Home Team | Peyrot M.,JT 60SA European Home Team
IEEE Transactions on Applied Superconductivity | Year: 2012

Included in the Broader Approach (BA) treaty, the JT-60SA project foresees to upgrade the existing JT-60U tokamak by substituting superconducting magnets to the present resistive magnets system. For this, a bilateral EU-JA procurement agreement drives EU, represented by Fusion for Energy (F4E) entity, to procure in-kind the totality of the 18 JT-60SA Toroidal Field (TF) Coils. Being almost the totality of the in-kind procurement of F4E for JT-60SA, the TF conductor manufacture monitoring is directly held by F4E, finalized by a delivery of components to collaborative EU institutes (CEA and ENEA) for its transformation into TF coils [1]. The organization of TF conductor procurement lies on two contract placed in December 2010 by F4E to industrial operators for strand manufacture on one side and cablingjacketing transformation on the other side. After a general overview the present paper describes the different steps reached up to the present state of fabrication achievement. The status of the ongoing manufacture and the foreseen next steps targeted in the near future will also be mentioned. © 2011 IEEE.

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