Overview of the ALPS Program

Journal Article · Fri Apr 15 00:00:00 EDT 2005 · Fusion Science and Technology

OSTI ID:20849942

Brooks, J N ^[1]; Allain, J P ^[1]; Bastasz, R ^[2]; Doerner, R ^[3]; Evans, T ^[4]; Hassanein, A ^[1]; Kaita, R ^[5]; Luckhardt, S ^[3]; Maingi, R ^[6]; Majeski, R ^[5]; Morley, N B ^[7]; Narula, M ^[7]; Rognlien, T ^[8]; Ruzic, D ^[9]; Stubbers, R ^[9]; Ulrickson, M ^[2]; Wong, C P.C. ^[4]; Whyte, D ^[3]; Ying, A ^[7]

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1. Argonne National Laboratory (United States)
2. Sandia National Laboratories (United States)
3. University of California San Diego (United States)
4. General Atomics (United States)
5. Princeton Plasma Physics Laboratory (United States)
6. Oak Ridge National Laboratory (United States)
7. University of California Los Angeles (United States)
8. Lawrence Livermore National Laboratory (United States)
9. University of Illinois Urbana Champaign (United States)

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 the demanding heat removal, particle removal, and erosion issues of fusion plasma/surface interactions. ALPS combines tokamak experiments, lab experiments, and modeling. We are designing both static and flowing liquid lithium divertors for the National Spherical Torus Experiment (NSTX) at Princeton. We are also studying tin, gallium, and tin-lithium systems. Results to date are extensive and generally encouraging, e.g., showing: 1) good tokamak performance with a liquid Li limiter, 2) high D pumping in Li and non-zero He/Li pumping, 3) well-characterized temperature-dependent liquid metal surface composition and sputter yield data, 4) predicted stable low-recycle improved-plasma NSTX-Li performance, 5) high temperature capability Sn or Ga potential with reduced ELM and disruption response concerns. In the MHD area, analysis predicts good NSTX static Li performance, with dynamic systems being evaluated.

• OSTI ID: 20849942
• Journal Information: Fusion Science and Technology, Vol. 47, Issue 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
COMPUTERIZED SIMULATION
DIVERTORS
EDGE LOCALIZED MODES
EROSION
FIRST WALL
GALLIUM
LIMITERS
LIQUID METALS
LITHIUM
MAGNETOHYDRODYNAMICS
NSTX DEVICE
PERFORMANCE
PLASMA
PLASMA SIMULATION
PUMPING
REMOVAL
SURFACES
TEMPERATURE DEPENDENCE
TIN