K. W. Hill, M. G. Bell, R. Budny,
C. E. Bush1, D. R. Ernst, G. W. Hammett,
D. Mikkelsen, H. Park, A. T. Ramsey,
S. Sabbagh2, S. D. Scott, E. J. Synakowski,
G. Taylor, and M. C. Zarnstorff
Princeton Plasma Physics Laboratory, Princeton University,
Princeton, NJ 08543, USA
1 Oak Ridge National Laboratory, Oak Ridge, TN
2 Columbia University, New York, NY
Abstract. To study the applicability of artificially enhanced impurity
radiation for mitigation of the plasma-limiter interaction in reactor regimes,
krypton and xenon gases were injected into TFTR supershots and high-li
plasmas. At neutral beam injection (NBI) powers
PB 30MW, carbon
influxes (blooms) were suppressed, leading to improved energy confinement and
neutron production in both D and DT plasmas, and the highest DT fusion energy
production (7.6 MJ) in a TFTR pulse. Comparisons of the measured radiated
power profiles with predictions of the MIST impurity transport code have
guided studies of highly-radiative plasmas in ITER. The response of the
electron and ion temperatures to greatly increased radiative losses from the
electrons was used to study thermal transport mechanisms.
IAEA 2001