GAS-TARGET AND DETACHED PLASMA REGIMES FOR THE ITER DIVERTOR

A number of solutions to the problem of the ITER divertor power loadin g have been proposed. The most promising ones are those characterized by an ionization front which is detached from the divertor plate. The space between such a front and the plate is filled with a cold, T-e < 1 eV, and (relatively) low density plasma, n(e) < 10(14) cm(-3). A reg ular high recycling regime and a detached (gas target) regime have bee n simulated with the PLANET code at a high scrape-off power of 220 MW. It is found that, in the detached case, over 90% of this power can be converted into radiation and that the gas target is well confined, bu t the midplane density is rather high, n(e) congruent to 1 X 10(14) cm (-3).