Fusion Science and Technology / Volume 26 / Number 3P2 / November 1994 / Pages 595-602
Divertor Experiment and Technology / Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 / dx.doi.org/10.13182/FST94-A40222
Articles are hosted by Taylor and Francis Online.
A better understanding of helium transport in the plasma core and edge in enhanced confinement regimes is now emerging from recent experimental studies on DIII-D. Overall, the results are encouraging with significant helium exhaust obtained in a diverted, ELMing H-mode plasma, with and transport studies indicating that DHe/χeff ∼ 1 in all plasma conditions studied to date. However, measurements in the core and pumping plenum show a significant dilution of helium as it flows from the plasma core to the pumping plenum. Such dilution could be the limiting factor in the overall removal rate of helium in a reactor system.