Published August 2017 | Version v1
Journal article

The Divertor Tokamak Test facility proposal: Physical requirements and reference design

  • 1. Consorzio CREATE and DIETI – Università degli Studi di Napoli Federico II, Via Claudio 21, I-80125 Napoli (Italy)
  • 2. ENEA Unità Tecnica Fusione, C.R. Frascati, Via E. Fermi 45, 00044 Frascati, Roma (Italy)
  • 3. Istituto di Fisica del Plasma "Pietro Caldirola"- CNR, Via Cozzi 53, 20125 Milano (Italy)
  • 4. Consorzio CREATE and DIII, Università della Campania "Luigi Vanvitelli", Via Roma 29, 81031 Aversa (CE) (Italy)
  • 5. Consorzio RFX and DII, Università degli Studi di Padova, Via Gradenigo, 6/A, I-35131, Padova (Italy)

Description

Highlights: • The DTT (Divertor Test Tokamak facility) proposal is aimed at demonstrating a heat exhaust system capable of withstanding the large load of DEMO in case of inadequate radiated power fraction. • DTT has the flexibility to test a wide set of divertor concepts and techniques including alternative magnetic configurations and liquid metal targets. • The basic physical DTT parameters have been selected so as to have edge conditions as close as possible to DEMO in terms of dimensionless parameters within an upper bound of 500 M€ for the investment costs. - Abstract: The main goal of the Divertor Tokamak Test facility (DTT) is to explore alternative power exhaust solutions for DEMO. The principal objective is to mitigate the risk of a difficult extrapolation to fusion reactor of the conventional divertor based on detached conditions under test on ITER. The task includes several issues, as: (i) demonstrating a heat exhaust system capable of withstanding the large load of DEMO in case of inadequate radiated power fraction; (ii) closing the gaps in the exhaust area that cannot be addressed by present devices; (iii) demonstrating how the possible implemented solutions (e.g., advanced divertor configurations or liquid metals) can be integrated in a DEMO device. In view of these goals, the basic physical DTT parameters have been selected according to the following guidelines: (i) edge conditions as close as possible to DEMO in terms of dimensionless parameters; (ii) flexibility to test a wide set of divertor concepts and techniques; (iii) compatibility with bulk plasma performance; (iv) an upper bound of 500 M€ for the investment costs.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nme.2017.05.008

Additional details

Identifiers

DOI
10.1016/j.nme.2017.05.008;
PII
S2352179116300813;

Publishing Information

Journal Title
Nuclear Materials and Energy
Journal Volume
12
Journal Page Range
p. 1330-1335
ISSN
2352-1791

Conference

Title
22. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices
Acronym
PSI-22
Dates
30 May - 3 Jun 2016
Place
Rome (Italy)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50079865
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DIVERTORS; EQUIPMENT; EXHAUST SYSTEMS; ITER TOKAMAK; LIQUID METALS; PROPOSALS; TEST FACILITIES
Descriptors DEC
CLOSED PLASMA DEVICES; ELEMENTS; FLUIDS; LIQUIDS; METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
© 2017 The Authors. Published by Elsevier Ltd.
Collaborations
DTT project proposal contributors