Conveners
Wed-Mo-Po3.01 - Fusion V: DDT and DEMO
- Neil Mitchell (ITER Organization)
- Simonetta Turtu' (ENEA)
The DDT (Divertor Tokamak Test) machine is under construction at the Frascati research center of ENEA and is aimed to investigate the possible divertor solutions for the management of power and particles exhaust for the EU-DEMO tokamak. Its Poloidal Field coil system is constituted by 6 magnets, identical in pairs as the machine is foreseen to be fully symmetric to allow for plasma...
The Divertor Tokamak Test facility (DTT) is an experimental tokamak machine to be built in Frascati, Italy, at the ENEA research centre. During its development, the DTT has gone through several important design updates. Developing a rigorous finite element methodology to evaluate the performance of all its components has thus been a critical part of the verification phase of each new design...
In the EU DEMO fusion reactor, currently in its pre-conceptual design phase, the long plasma pulse duration and the large thermal loads represent a challenge for the power exhaust, so that a new, robust design of the divertor is needed. For this reason, several DEMO-relevant divertor solutions will be tested in the Divertor Tokamak Test (DTT) facility that will be built in Italy. It will be a...
In the context of the European Fusion Roadmap, the Divertor Tokamak Test (DTT) experimental reactor is intended to investigate alternative divertor configurations in view of the EU-DEMO power exhaust handling necessities, and it is to be built at the Frascati ENEA research centre in Italy. The six poloidal field coils of the tokamak are responsible for the plasma shape and equilibrium, and...
The “Divertor Tokamak Test” facility, DTT, is a project of an experimental tokamak reactor developed in Italy, in the framework of the European Fusion Roadmap.
This work presents the magnetic and the structural assessment of the performance of the DTT central solenoid.
The CS is the core magnet of the poloidal system and generates the magnetic flux needed to induce the plasma current....
In the framework of EU design activities for dimensioning the future fusion DEMOnstration reactor (DEMO), extensive analyses were conducted in EUROfusion context, aiming at ultimately defining the design of the DEMO magnets system. In this objective CEA proposes design for all cryomagnetic systems: Toroidal Field (TF) coils, Central Solenoid (CS) and Poloidal Field (PF) coils.
In the last...
The design of DEMO PF coils is proposed and analysed based on the requirements defined by the EUROfusion 2019 DEMO baseline. Two types of forced flow cable-in-conduit conductors are used: NbTi with high void fraction and Nb3Sn with a dedicated cooling channel. The design addresses the dimensioning of the winding pack, the electromagnetic field calculations, stress analysis and thermal...
The Swiss Plasma Center (SPC) has developed a layout of Toroidal Field (TF) coil for EUROfusion DEMO tokamak, basing on a reference baseline of 2015. Each TF coil winding pack is wound with graded Nb3Sn conductors and consists of 12 single layers, connected in series by means of inter-layer joints.
The design of inter-layer joints takes into account the react-and-wind (R&W) manufacturing...
State-of-the-art high field solenoids make use of hybrid designs exploiting the superior high field performance of High Temperature Superconductors (HTS) in the innermost region. The benefits of a hybrid Central Solenoid in a pulsed tokamak like DEMO can be two-fold: either to reduce its outer radius (which would result in a reduced overall size and cost of the tokamak), or to increase the...
