Special Session (Nuclear Fusion):

Title:            Indian Fusion Programme and Contribution for ITER Project
Authors:       Aparajita Mukherji
Abstract:     Indian national programme to develop magnetically confined plasma experiments initiated in late 80’s. A mandate was given to Institute for Plasma Research (IPR) for development of 1st indigenous Indian Tokamak ADITYA1, which was successfully commissioned in 1989. Since then it is producing various scientific database and operating regularly for conducting experiments. The Institute has taken the next major step to construct Steady State Superconducting Tokamak (SST-1) for generating database for steady state plasma operation, particularly in the areas of plasma-wall interaction during long pulse operation and to develop fusion relevant technologies2,3. SST-1 is a medium size Tokamak, having toroidal magnetic field 3 T, plasma current 220 kA and major & minor radius 1.1 m and 0.2 m respectively. After successful achievement of first plasma in June 2013, SST-1 is now aiming for achieving various experimental parameters regime4,5. In parallel technology development programme in some of the key areas of fusion, like, divertor & first-wall, fusion reactor materials development & characterization, R&D of fusion blanket6,7, remote handling, neutronics etc. have been initiated. Development of auxiliary technologies for fusion, like, radio frequency, neutral beam, magnets and plant systems have also started as the next step in our national programme. Theoretical research activities in IPR are dedicated in fusion related modelling and simulation work. To accelerate the Indian fusion programme, IPR has joined international fusion project ITER as a full partner in Dec 2005, along with other ITER partners European Union, Japan, the People’s Republic of China, the Republic of Korea (South), the Russian Federation and USA. The aim of ITER is to demonstrate fusion could be used to generate electrical power, and to gain the necessary data to design and operate the first electricity-producing plant. In ITER, the main focus will be to study the plasmas in conditions similar to those expected in an electricity-generating fusion power plant. It will generate 500 MW of fusion power for extended periods of time, ten times more than the energy input needed to keep the plasma at the right temperature. It will therefore be the first fusion experiment to produce net power. It will also test a number of key technologies, including the heating, control, diagnostic and remote maintenance that will be needed for a real fusion power station. As ‘inkind’ contribution for ITER project, India shall be supplying total 9 work packages. For smooth execution of Indian responsibility, ITER-India, within the IPR, has been created in 2007 as a nodal agency for ITER project. The 9 work packages are (1) Cryostat & Vacuum Vessel Pressure Suppression System, (2) In-wall Shielding, (3) ICRH RF power sources, (4) ECRH RF power sources, (5) Diagnostic Neutral Beam, (6) Diagnostics with Upper Port Plug, (7) Power Supply Systems, (8) Cryodistribution and Cryolines and (9) Component Cooling Water System, Chilled Water System and the Heat Rejection System. These packages can be broadly divided in different categories, like, heavy engineering, precision machining, R&D oriented, technology driven and interface & integration driven. The most important features of this project are first-of-its-kind, large scale and complexity. Each package needs special attention to address from design criteria to construction phase. So far significant progress has been achieved for most of the packages8-16. All these activities are aiming for development of our own fusion reactor in future. In this presentation, various experimental results and technology development programme will be discussed.
Keywords:   Tokamak, ITER, Divertor, Blanket, Fusion Power, Radio Frequency, Neutral Beam
Pages:         010-011

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