Return To: Session OV6/ITER - ITER
Prev Page: (OV6/1) Key Engineering Features of the ITER-FEAT Magnet
Next Page: (ITER/3) Divertor Design and its Integration into the

(ITER/1) ITER-FEAT Operation

Y. Shimomura¹⁾, R. Aymar²⁾, V. Chuyanov²⁾, M. Huget¹⁾, H. Matsumoto²⁾, T. Mizoguchi¹⁾, Y. Murakami¹⁾, A. Polevoi¹⁾, M. Shimada¹⁾ and the ITER Joint Central Team and Home Teams
 
¹⁾ ITER Joint Central Team, Naka Joint Work Site, Naka-machi, Ibaraki-ken, Japan
²⁾ ITER Joint Central Team, Garching Joint Work Site, Garching, Germany

Abstract.  ITER is planned to be the first fusion experimental reactor in the world operating for research in physics and engineering. The first 10 years' operation will be devoted primarily to physics issues at low neutron fluence and the following 10 years' operation to engineering testing at higher fluence. ITER can accommodate various plasma configurations and plasma operation modes such as inductive high Q modes, long pulse hybrid modes, non-inductive steady-state modes, with large ranges of plasma current, density, beta and fusion power, and with various heating and current drive methods. This flexibility will provide an advantage for coping with uncertainties in the physics database, in studying burning plasmas, in introducing advanced features and in optimizing the plasma performance for the different programme objectives. Remote sites will be able to participate in the ITER experiment. This concept will provide an advantage not only in operating ITER for 24 hours per day but also in involving the world-wide fusion communities and in promoting scientific competition among the Parties.

Read the full paper in PDF format.