Overview of the Divertor Tokamak Test Facility project.

Martin P. per il DTT Team

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The Divertor Tokamak Test Facility (DTT) is a new tokamak whose construction has recently been approved by the Italian government. DTT will be a high field superconducting toroidal device (6 T) carrying plasma current up to 6 MA in pulses with length up to 100s, with an up-down symmetrical D-shape defined by major radius R=2.15 m, minor radius a=0.7 m and average triangularity 0.3. The main role of DTT is to contribute to the development of a reliable solution for the power and particle exhaust in a reactor, a challenge commonly recognised as one of the major issues in the road map towards the realisation of a nuclear fusion power plant. Following the project approval, since June 2017 the design review of DTT has started. This paper will present the device by summarizing its main physics goals and the present status of the design. After an extensive activity, which involved Italian labs and scientists from other European labs, the DTT preliminary design report was released in June 2015. In the first semester of 2017 the Italian government identified the funding strategy of the experiment and authorized its start up. The DTT experiment may provide important elements for finding solutions to the plasma exhaust problem delivering information in operational ranges or configurations that are not accessible for the present devices or JT-60SA. To fulfill its goals, the DTT will perform experiments aiming at: (a) demonstrating the possibility to operate with a heat exhaust system capable of withstanding DEMO relevant thermal loads and in integrated scenarios, i.e. maintaining adequate core performance and edge and bulk parameters as close as possible to ITER and DEMO; (b) exploring innovative solutions like advanced divertor configurations and use of liquid metals that can be integrated in a DEMO device, taking into account the constraints on plasma bulk performances, poloidal field coil system, materials, space for the blanket and neutron shielding.

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