NSTX PFC Upgrade Plans College W&M R. Kaita for the NSTX Team - - PowerPoint PPT Presentation

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NSTX PFC Upgrade Plans College W&M R. Kaita for the NSTX Team - - PowerPoint PPT Presentation

Supported by NSTX PFC Upgrade Plans College W&M R. Kaita for the NSTX Team Colorado Sch Mines Culham Sci Ctr Columbia U U St. Andrews CompX Princeton Plasma Physics Laboratory York U General Atomics Chubu U INEL Fukui U Plasma


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SLIDE 1

NSTX PFC Upgrade Plans

  • R. Kaita for the NSTX Team

Princeton Plasma Physics Laboratory Plasma Facing Components Meeting UCLA August 6, 2010

College W&M Colorado Sch Mines Columbia U CompX General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Illinois U Maryland U Rochester U Washington U Wisconsin Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI KBSI KAIST POSTECH ASIPP ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep U Quebec

Supported by

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SLIDE 2
  • General comments on Liquid Lithium Divertor

(LLD) technical performance

  • Effects of high power density on LLD
  • Test facilities at PPPL
  • Design of improved lithium loading for LLD
  • Inner divertor upgrade with molybdenum tiles

Outline

  • 2 -
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SLIDE 3

NSTX operation with Liquid Lithium Divertor demonstrates basic soundness of design*

  • 3 -

Side view of LLD and divertor tiles

  • R. Ellis

Pivoting corner supports

  • No excessive heating or deleterious introduction of impurities from LLD during

high-power NSTX plasma operations > Validates design with thin, molybdenum-sprayed stainless steel liner on copper backing

  • No unanticipated LLD displacement due to thermal effects, eddy currents, or
  • ther potential sources of mechanical stress

> Edge mounting scheme functioning as designed *See paper SP3C-32 by R. Ellis et al. in 36th International Conference on Plasma Science and 23rd Symposium on Fusion Engineering

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SLIDE 4

Discoloration only observation on LLD after high power neutral beam injection plasmas

  • No apparent damage to LLD or “diagnostic” tiles

separating LLD quadrants observed with up to 4 MW of neutral beam injection

  • 4 -

Limits of LLD Location of

  • uter strike

point “Diagnostic” tile

  • F. Scotti
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SLIDE 5
  • Test chamber on diagnostic neutral beamline

– MSE-LIF neutral beam heat flux ~ 10 MW/m2 comparable to NSTX divertor – Thermocouples and IR camera measure surface and bulk temperatures

Results consistent with offline studies of thermal response of LLD sample

  • 5 -
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SLIDE 6
  • C128 chamber (pictured) has

heated proto-LLD sample for controlled testing – LITER 1C for deposition – differentially pumped RGA arm – camera for surface reflectivity measurements – QDM for LITER deposition and plate evaporation – various species glows possible (characterized by Langmuir probe) – Lithium Conductivity Diagnostic for surface quality and thickness measurements (possible installation in NSTX PMI probe)

LITER port Camera View RGA Glow feedthru Gas inlet LLD sample QDM

Offline facilities also available with lithium evaporation capability for NSTX PFC testing

  • 6 -
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SLIDE 7

More efficient LLD loading planned with liquid lithium fill system

  • Proposed concept adopts LITER Liquid Lithium Fill system (LIFTER)

technology being used to refill LITERS

  • Concept
  • 1 station per plate (one per 90°)
  • 3 components per fill station:
  • 1. External LIFTER-like unit
  • 2. Vertical pipe from port to toroidal distribution pipe near outer wall
  • 3. Moly or ATJ clad 316-SS pipe (spoke) from distribution pipe to plate
  • J. Timberlake

1 2 2 3

  • 7 -
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SLIDE 8

Concept for molybdenum plasma-facing surface for NSTX inboard divertor under analysis

  • H. Kugel
  • 8 -

Tee-Bar, screw & Belleville washer

Horizontal Inboard Divertor Vertical Inboard Divertor LLD-1

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SLIDE 9

*Work supported in part by US DOE Contracts DE-AC02-09CH11466, DE-AC04-94AL85000, DE-AC52-07NA27344, and DE-AC05-00OR22725

  • H. Kugel 1), T. Abrams 1), M. G. Bell 1), R. Bell 1), R. Ellis 1),
  • S. Gerhardt 1), T. Gray 2), M. Jaworski 1), J. Kallman 1),
  • A. L. Roquemore 1), H. Schneider 1), F. Scotti 1), C. H. Skinner 1),
  • V. Soukhanovskii 3), V. Surla 4), and J. Timberlake 1)

1) Princeton Plasma Physics Laboratory, Princeton, NJ 2) Oak Ridge National Laboratory, Oak Ridge, TN 3) Lawrence Livermore National Laboratory, Livermore, CA 4) University of Illinois at Urbana-Champaign, Champaign, IL

NSTX Team Contributors and Acknowledgements*

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