The Divertor Tokamak Test facility proposal: Physical requirements and reference design
Creators
- 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.2017.05.008Additional 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