5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

I5.3 Design and definition of a Divertor Tokamak Test facility

9 Sep 2016, 09:50
40m
Forum Hall 2nd floor (Prague Congress Centre)

Forum Hall 2nd floor

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 3

Speaker

R. Albanese (on behalf of the EUROfusion WPDTT2 team & the DTT report contributors)

Description

One of the main challenges in the European roadmap toward the realisation of fusion energy with a demonstration plant DEMO [1] is to develop a heat and power exhaust system able to withstand the large loads expected in the divertor. In parallel with the programme to optimise the operation with a conventional divertor based on detached conditions to be tested on ITER, efforts are being devoted to the definition and the design of a "Divertor Tokamak Test facility" (DTT). Aim of DTT is to assess the set of possible alternative solutions including advanced magnetic configurations and liquid metal divertors. DTT should operate integrating the most relevant physics and technology issues, with significant power loads, flexible divertors, plasma edge and bulk conditions approaching as much as possible those planned for DEMO, at least in terms of dimensionless quantities. The machine parameters are selected so as to have a balance between these requirements and the need to realize the new experiment accomplishing the DEMO timescale within a reasonable budget: major radius R=2.15 m, aspect ratio R/a =3.1, toroidal field BT=6 T, plasma current Ip=6 MA, additional power PTot=45 MW. The machine will have the possibility to test several different magnetic divertor topologies (including single null, double null, snowflake, X-divertor) in reactor relevant regimes. Different plasma facing materials will be tested (tungsten, liquid metals) up to a power flow of the order of 20 MW/m22. The main target of this experiment is the realization of an integrated solution (bulk and edge plasma) for the power exhaust in view of DEMO. According to the European roadmap, the DTT experiment should start its operation in 2022. To be coherent with this plan, the realization of the device will cover a time of around 7 years, starting from the first tender (during 2016) up to full commissioning and the first plasma (during 2022). The operations should then cover a period of more than 20 years, up to the initial phases of the DEMO realization. This talk presents the DTT proposal worked out by an International European Team of experts [2]. It demonstrates the possibility to set up a facility able to bridge the power handling gaps between the present day devices, ITER and DEMO within the European fusion development roadmap, which plays a crucial role for the development of one of the most promising technologies for an alternative, safe and sustainable energy source. [1]  F. Romanelli et al., Fusion Electricity - A roadmap to the realisation of fusion energy, EFDA, November 2012, ISBN 978-3-00-040720-8 [2]  A. Pizzuto (Ed.), DTT - Divertor Tokamak Test facility - Project Proposal, ENEA, July 2015, ISBN: 978-88-8286-318-0, http://fsn-fusphy.frascati.enea.it/DTT/downloads/Report/DTT_ProjectProposal_July2015.pdf

Co-author

R. Albanese (on behalf of the EUROfusion WPDTT2 team & the DTT report contributors, Consorzio CREATE & DIETI - Univ. Napoli Federico II, via Claudio 21, I-80125 Napoli, Italy)

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