作者: J. N. Brooks , J. P. Allain , R. Bastasz , R. Doerner , T. Evans
DOI: 10.13182/FST05-A763
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摘要: The US Advanced Limiter-divertor Plasma-facing Systems (ALPS) program is developing the science of liquid metal surface divertors for near and long term tokamaks. These systems may help solve demanding heat removal, particle erosion issues fusion plasma/surface interactions. ALPS combines tokamak experiments, lab modeling. We are designing both static flowing lithium National Spherical Torus Experiment (NSTX) at Princeton. also studying tin, gallium, tin-lithium systems. Results to date extensive generally encouraging, e.g., showing: I) good performance with a Li limiter, 2) high D pumping in non-zero He/Li pumping, 3) well-characterized temperature-dependent composition sputter yield data, 4) predicted stable low-recycle improved-plasma NSTX-Li performance, 5) temperature capability Sn or Ga potential reduced ELM & disruption response concerns. In MHD area, analysis predicts NSTX dynamic being evaluated.