NSTX PFC Upgrade Plans

Transcription

1 Supported by NSTX PFC Upgrade Plans 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 R. Kaita for the NSTX Team Princeton Plasma Physics Laboratory Plasma Facing Components Meeting UCLA August 6, 2010 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

2 Outline 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 - 2 -

3 NSTX operation with Liquid Lithium Divertor demonstrates basic soundness of design* Side view of LLD and divertor tiles 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 other potential sources of mechanical stress > Edge mounting scheme functioning as designed *See paper SP3C-32 by R. Ellis et al. in 36 th International Conference on Plasma Science and 23 rd Symposium on Fusion Engineering R. Ellis - 3 -

4 Discoloration only observation on LLD after high power neutral beam injection plasmas Location of outer strike point Limits of LLD Diagnostic tile No apparent damage to LLD or diagnostic tiles separating LLD quadrants observed with up to 4 MW of neutral beam injection F. Scotti - 4 -

5 Results consistent with offline studies of thermal response of LLD sample Test chamber on diagnostic neutral beamline MSE-LIF neutral beam heat flux ~ 10 MW/m 2 comparable to NSTX divertor Thermocouples and IR camera measure surface and bulk temperatures - 5 -

6 Offline facilities also available with lithium evaporation capability for NSTX PFC testing 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 LLD sample QDM Glow feedthru Gas inlet - 6 -

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 -7-

8 Concept for molybdenum plasma-facing surface for NSTX inboard divertor under analysis Horizontal Inboard Divertor Vertical Inboard Divertor LLD-1 Tee-Bar, screw & Belleville washer H. Kugel -8-

9 NSTX Team Contributors and Acknowledgements* 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 *Work supported in part by US DOE Contracts DE-AC02-09CH11466, DE-AC04-94AL85000, DE-AC52-07NA27344, and DE-AC05-00OR