DTT: An Integrated Bulk and Edge Plasma Experiment to Tackle the Power Exhaust Problem in View of DEMO
Creators
- 1. Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile (ENEA), Rome (Italy)
Description
Full text: A DTT experiment should be capable of: 1) demonstrating a safe and robust power handling solution that can be extrapolated to DEMO; 2) achieving the previous goal without degrading the plasma core and pedestal performances, in a plasma regime as close as possible to a reactor one; and, 3) demonstrating the possibility to achieve points 1) and 2) by integrating as much as possible all the physics and technological aspects. The challenging task of integrating these three targets has been tackled by combining the approach of considering the divertor as a separated regions, as well as integrating the main adimensional physics aspects of the divertor and of the plasma bulk. A cost constraint of 500 M€ has been included among the scaling parameters. The integration of these aspects leads to a machine with R ≤ 2.3 m. A reasonable minimum size with R > 1.8 m has been evaluated by. evaluating the necessity of varying the local divertor magnetic topology; considering the radiation load on the first wall; considering the necessity of long discharge to study the technical aspects of the divertor materials. An intermediate size of R > 2.15 m has been selected, with a = 0.70 m, Ip = 6.0 MA, Bt = 6 T, and elongation k ≈ 1.76. The heating power will be PADD = 45 MW. The selected mix of heating is. ≈15–25 MW ECRH at 170 GHz; ≈15– 25 MW ICRH at 60–90 MHz; ≈5–15 MW NBI at 300 keV. The main expected performances are an average density e> = 1.7 x 1020/m3, an average temperature = 6.2 keV, PSEP/R = 15 MW/m and a parallel flow q ‖ ∼PSEPB/R = 125. DTT will be equipped with a set of external poloidal coils able to guarantee a large set of different divertor magnetic configurations. The presence of a set of small internal coils will allow to locally modifying the magnetic configuration, so as to produce a very large set of quite different topologies. The possibility to use a liquid metal divertor has been included in the design. A double null standard X-point divertor scenario will be possible. All the external coils are designed by using superconductor technology, allowing discharges lasting around 100 s. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 729
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50012629
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; DIVERTORS; ECR HEATING; FIRST WALL; ICR HEATING; LIQUID METALS; PLASMA; SUPERCONDUCTORS
- Descriptors DEC
- ELEMENTS; FLUIDS; HEATING; HIGH-FREQUENCY HEATING; LIQUIDS; METALS; PLASMA HEATING; THERMONUCLEAR REACTOR WALLS
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- IAEA-CN--234-0226