Published May 3, 2018 | Version v1
Report

Upgrade of ADITYA Tokamak with Limiter Configuration to ADITYA Upgrade Tokamak with Divertor Configuration

  • 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)

Part of:
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material

Additional details

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