Upgrade of ADITYA Tokamak with Limiter Configuration to ADITYA Upgrade Tokamak with Divertor Configuration
Creators
- 1. Institute for Plasma Research (IPR), Bhat, Gandhinagar (India)
Description
Full text: It is a well-known fact that small and medium-sized tokamaks have enormously contributed in design and development of large size tokamaks such as ITER for building fusion reactors in terms of physics, engineering and diagnostics. Small and medium-sized tokamaks are very convenient to develop and test new ideas, technologies and materials, which, because of the risky nature, cannot be done in large machines without preliminary studies, such as disruption studies, runaway studies, etc. The worldwide effort on magnetic fusion is devoted to the present generations of large tokamaks like DIII-D, TCV, EAST, SST-1 etc., which are operational emphasizing on divertor and tungsten wall ITER-like operation. However, there are very few (2–3) small and medium-sized tokamaks operational around the world with divertor facility and technical capabilities to provide able support for operation and trouble shooting of these big tokamaks. Therefore, it has been planned to upgrade the existing ADITYA tokamak (R0 = 75 cm, a = 25 cm) successfully operated over two decades with more than 30,000 discharges into a state-of-art machine with divertor operation and very good plasma control to support the future Indian Fusion programme. The scientific objectives of ADITYA tokamak Upgrade include low loop voltage plasma start-up with strong pre-ionization having a good plasma control system. The upgrade is designed keeping in mind the experiments, disruption mitigation studies relevant to future fusion devices, runway mitigation studies, demonstration of Radio-frequency heating and current drive, etc. This upgraded ADITYA tokamak will be used for basic studies on plasma confinement and scaling to larger devices, development and testing of new diagnostics and so on. This machine will be easily accessible and will be very useful for generation of technical and scientific expertise for future fusion devices. The installation of ADITYA Upgrade tokamak is completed and plasma discharges will be initiated soon. In this paper, special features of the upgrade including various aspects of designing and fabrication of new components for ADITYA Upgrade tokamak along with preliminary results of plasma operations will be presented. (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. 717
- 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
- 50008585
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADITYA TOKAMAK; CONTROL SYSTEMS; DIVERTORS; DOUBLET-3 DEVICE; ITER TOKAMAK; PLASMA CONFINEMENT; RADIOWAVE RADIATION; TCV TOKAMAK; TUNGSTEN
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; ELECTROMAGNETIC RADIATION; ELEMENTS; METALS; RADIATIONS; REFRACTORY METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- IAEA-CN--234-0720