Conceptual design of the power supplies for DTT Neutral Beam Injector
Creators
- 1. Consorzio RFX, Corso Stati Uniti 4, 35127 Padova (Italy)
- 2. Department of Industrial Engineering (DII), Università di Padova, Via Gradenigo 6/A, 35131 Padova (Italy)
- 3. Consiglio Nazionale delle Ricerche, Istituto per la Scienza e Tecnologia dei Plasmi, Via R. Cozzi 53, 20125 Milano (Italy)
- 4. DTT S.c.a r.l., Via E. Fermi 45, 00044 Frascati (RM) (Italy)
- 5. ENEA, Centro Ricerche Frascati, Via E. Fermi 45, 00044 Frascati (RM) (Italy)
- 6. CREATE Consortium, Via Claudio 21, 80125 Napoli (Italy)
- 7. EniProgetti S.p.A., Via P. Stefanini 11, 00144 Roma (Italy)
Description
The Divertor Tokamak Test facility (DTT) is the new tokamak whose construction is starting in Frascati (Italy), with the main aim of testing different divertor magnetic configurations and technologies in view of DEMO. In the present design, the DTT heating mix includes one Negative Neutral Beam Injector (NBI), with a power injected in the plasma of 10 MW and a beam energy of 500 keV.
spara010>The NBI conceptual design is under development and includes solutions already adopted for ITER (RF-driven ion source, gas neutralizer, electrostatic Residual Ion Dump), but with some simplifications to reduce costs and complexity deemed feasible for DTT. In particular, the beam source is air-insulated and fed by the gas-insulated Transmission Line through gas-air bushings.
spara011>This paper presents the status of the conceptual design of the main power supplies of the DTT NBI. The main ratings are collected from physics requirements and NBI design. On this basis, the reference technical solutions are selected, considering the experience gained at the ITER Neutral Beam Test Facility in Padova (Italy), the specific design of the DTT NBI and the layout constraints of the DTT Site. For the Acceleration Grid Power Supply, besides the ITER-like design, an innovative approach based on the Modular Multilevel Converter technology, never adopted in this application, is considered; pros and cons of the two solutions are evaluated.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2021.112624Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2021.112624;
- PII
- S0920379621004002;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 169
- Journal Page Range
- vp.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004397
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Descriptors DEI
- CONFIGURATION; DESIGN; DIVERTORS; ELECTROSTATICS; HEATING; ION SOURCES; ITER TOKAMAK; KEV RANGE; PLASMA; POWER SUPPLIES; TEST FACILITIES; TESTING
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRONIC EQUIPMENT; ENERGY RANGE; EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2021 Elsevier B.V. All rights reserved.