Long Term Reduction of Divertor Carbon Sources in DIII-D

Size: px
Start display at page:

Download "Long Term Reduction of Divertor Carbon Sources in DIII-D"

Transcription

1 Long Term Reduction of Divertor Carbon Sources in DIII-D D.G Whyte, UCSD R. Doerner, W.P. West, R.L. Lee, N.H. Brooks, R.D. Isler, M.R. Wade, G.D. Porter APS-DPP, Seattle, Nov NATIONAL FUSION FACILITY #1

2 Abstract Submitted for the DPP99 Meeting of The American Physical Society Sorting Category: (Experimental) Long-term Reduction of Divertor Carbon Sources in DIII-D 1 D.G. WHYTE, R. DOERNER, University of California, San Diego, W.P. WEST, R.L. LEE, N.H. BROOKS, General Atomics, R.C. ISLER, M.R. WADE, Oak Ridge National Laboratory, G.D. PORTER, Lawrence Livermore National Laboratory The long-term evolution of carbon sputtering from the tokamaks graphite-covered lower divertor is studied using in-situ spectroscopy and ex-situ laboratory erosion yield measurements. The total effective yield and, hence, the impurity source amplitude has gradually decreased a factor > 4 since installation of the tiles in This reduction is likely caused by the 2-fold reduction in the chemical erosion yield of the graphite, the effect of > 3 applied boronizations. Despite this great success in wall conditioning, there has been no concomitant decrease in the core plasma carbon contamination during the same period. Two explanations are being explored: (1) the nature of parallel impurity transport decouples the wall source and content, and (2) the first wall is the principal source of carbon in the core. 1 Supported by U.S. DOE Grant DE-FG3-95ER and Contracts DE-AC3-99ER54463, DE-AC5-96OR22464, and W-745-ENG-48. X Prefer Oral Session Prefer Poster Session D.G. Whyte whyte@gav.gat.com University of California, San Diego Special instructions: DIII-D Poster Session 2, immediately following RJ Colchin Date printed: July 16, 1999 Electronic form version 1.4

3 Outline Background & Motivation History of chemical and total erosion yields in DIII-D lower divertor (1992- present). Effect of lower divertor carbon erosion yield on core plasma carbon contamination. Laboratory studies of DIII-D graphite tiles Summary & discussion. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #2

4 Background & Motivation Previous results suggest chemical erosion of carbon plays an important role in DIII-D Helium plasmas: reduced carbon radiation in core and divertor. UEDGE modeling: a distributed chemical carbon source (using University of Toronto Y chem ) provided radiation to induce detachment and match C spectroscopy. Previous results suggest that chemical erosion of carbon plays a minor role in DIII-D CD-band emission not observed in divertor (Y chem < 1-3 ). Divertor detachment, which eliminates physical sputtering, showed only carbon deposition in divertor (DiMES, PSI 98)..total yield reduced by x1. Current carbon-based tokamaks show divertor erosion and tritium retention will seriously limit operations of next-step DT devices. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #3

5 T ( C) Divertor detachment eliminates net carbon erosion in the entire lower divertor!...yet carbon density in core plasma remains constant? T e (ev) n e (m -3 ) i (m -2 s -1 ) q (MW m -2 ) 2 1 Attached vs. Detached Carbon Erosion Rate (cm / burn-year) Inner leg Outer leg erosion deposition private flux exposure 4 8 R strikepoint (cm) R OSP (cm) Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #4 D 2 Torr L /s I p MA P aux MW W th MW n e /n C 1 19 m -3 f C % /.16 4 ~ /

6 Brightness ( x 1 17 ph/s/m 2 /sr/å) Brightness ( x 1 17 ph/s/m 2 /sr/å) Atomic and molecular spectroscopy suggest chemical erosion plays a minor role in DIII-D divertor. C I 8335 Å detached plasma C II detached: OSP ( ) attached: outer leg attached: top of baffle CD band chord viewing DiMES 833 Wavelength (Å) 834 BD band chord viewing inner corner Wavelength (Å) D Ar II Atomic Carbon SXB ~ 3 Molecular Carbon (C x H y ) DXB ~ 1 Assumption Y chem Ions only 1-3 Ions=neutrals 1-4 Particle Flux (m-2 s-1) Detached DiMES exp t Inner Strikepoint Atomic carbon R chord at divertor floor (m) Outer Strikepoint 6 7 OSP exposure DiMES sample Carbon in molecules PF exposure Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #5

7 Based on carbon-based tokamaks standard operation, erosion will severely limit operation of D-T burning device. Pervasive in/out asymmetry. Outer divertor net erosion rate: > 1 cm / burn-year! T trapping in erosion caused layers: ~ 1 kg / m 2 / burn-year! Net change in tile thickness ( m) DAC ISP DIII-D net redeposition net erosion OSP Major Radius (m) <T surf > (K) DAC (f) (g) ASDEX Upgrade Inner Wall Heat shield Divertor plates ISP ICRH- Antenna OSP Distance along divertor plates (m) DAC 1 2 JET (MkI) Tile # R=2.3 m 334 ISP Be target OSP Tile number R=3.1 m Plasmafacing Only Entire top surface Carbon target Poloidal erosion / redeposition patterns from 3 tokamaks: > 1 year of operations. DAC: trapped D concentration Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #6 D.G. Whyte, et al. Nucl Fusion (1999).

8 History of carbon chemical erosion yields in the DIII-D lower divertor (1992- present). #7

9 Relative spectroscopy can be used to measure carbon erosion yields in situ Y Technique relies on S/XB (loss events per photon) and relative intensities: Fairly insensitive to T e and n e. Insensitive to photometric calibration. Chemical erosion yield Y chem D D B = B Total erosion yield total ΓC x = Γ ( Γ = C x D y Γ y +Γ D C CD D/ XB S / XB CD D γ D γ ) B B D CII S S / / XB XB CII D α, γ α, γ Intensity (a.u.) OSP exposure DiMES sample C CD band (Å) PF exposure D Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #8

10 S/XB and D/XB values are fairly constant for attached plasma (T e > 1 ev) conditions. 1 1 n e =3x1 13 n e =5x1 13 n e =1x1 14 ADAS Ionizations per photon for D Experiment (Attached plasmas) T e (ev) Derived values for D γ S/XB Atomic rate calculations. Experimental comparison to probes & DTS. Agreement / scatter to within a factor of 2. Assumes recycling ~ influx. D/XB is derived from controlled CD 4 injections: JET: D/XB ~4-5 for attached plasmas. PISCES: D/XB ~5-1 for T e > 1 ev. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #9

11 DIII-D tiles have accumulated ~2.5 µm of boronization layers & ~1 5 seconds (25, shots) of plasma exposure without significant alterations to lower divertor tiles. Accumulated boron deposition ( µm ) % 1% graphite coverage Existing tiles removed, cleaned & re-installed Exposure time (s) 1.2E+5 8.E+4 4.E+4.E+ 24 hours Jan-91 Jan-93 Jan-95 Jan-97 Jan Boronization shot number Single boronization = ~1 nm uniform B layer deposited Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #1

12 Graphite tiles are visibly altered by tokamak exposure. replacement tiles Plasma-exposed tile removed from DIII-D for PISCES exposure DiMES DIII-D Lower Divertor near DiMES (August 1998) Scratches from plasma arc Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #11

13 In , a single boronization would cause an immediate, but temporary, reduction in Y chem and Y total. Relative brightness to D γ BD CII CD #7677 #7667 Direct comparison before and after boronization. Y chem reduced ~x4 Y total reduced ~x2 BD band reduced, but not eliminated by plasma exposure Shots since boronization Averaged over lower divertor chords Substantial removal of 1 nm boron layer consistent with measured OSP net erosion rates ~ 2 nm/s Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #12

14 Comparison of nearly identical plasmas show that Y chem has decreased significantly in DIII-D since CD / Dγ ISP R (cm) OSP Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #13 Mar-93 Jan-99 Spectra normalized to D γ intensity & for different detector responses (intensified vs. non-intensified) #76952 #9842 I p (MA) n e (cm -3 ) 7.6x x1 13 P inj (MW) W dia (MJ) Intensity (a.u.) 1 #76952 #9842 CD band BD band (Å) D

15 A database of lower divertor CD band spectroscopy ( ) clearly shows a large reduction in Y chem. All chords, all plasma types CD / D γ Includes all discharges where spectrometer was tuned to 43 nm: LSN & DN Ohmic, L, ELMy H Attached & detached shot number Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #14

16 Average lower divertor Y chem for attached ELMy H-mode plasmas has gradually decreased a factor of 2 from ~2% to ~.1% since >1 shots post-boronization Yield measurement fairly reliable since for attached divertor T e > 1 ev: D/XB CD ~ 5 S/XB ~ 2 Dγ.1 Y chem Y chem ΓC x = Γ D D y B = B CD D/ XB S / XB D γ D CD γ Shot Scatter in yield probably indicative of uncertainty in T plate, Γ & S/XB. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #15

17 Observed yield reductions are not due to any systematic drift of plasma parameters used in spectroscopy database. Attached ELMy H-mode >1 shots post-boronization 1 14 n e (cm -3 ) P inj (W) I p (A) 1 6 Average values Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #16 Shot

18 Y chem reduction is even larger at ISP, consistent with plasma redeposition of both boron and carbon at the inner divertor leg reducing the yield. Attached ELMy H-mode >1 shots post-boronization CD / D γ Outer Strikepoint Inner strikepoint Absolute yield comparison not available because of poor plasma diagnosis at ISP Shot Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #17

19 Smaller subset of detached plasmas show a lower erosion yield than attached plasmas, consistent with lower incident energy at tiles..1.1 ELMy H-mode >1 shots post-boronization Attached Detached Yield comparison depends on changes due to recombining divertor plasma (T e < 2 ev): D/XB CD ~ 2 (PISCES) S/XB Dγ ~ 35 (Experiment).1.1 Y chem Shot DiMES Y chem ΓC x = Γ D D y B = B CD D/ XB S / XB CD D γ D γ Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #18

20 The average BD band in the lower divertor has not changed significantly with accumulative boronizations. 1 BD / D γ Attached ELMy H-mode >1 shots post-boronization Tiles cleaned Shot BD band is a measurement of boron chemical erosion yield B II measurements would better indicate relative boron content but rarely tuned to lines with spectrometer. Results could indicate substantial boron-carbide bond formation, which would be resistant to chemical erosion. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #19

21 Reduction of total lower divertor carbon sources & core plasma carbon contamination #2

22 Simultaneous with the reduction in Y chem of ~x1, the lower divertor Y total has decreased at least x4. Attached ELMy H-mode >1 shots post-boronization Maximum value in lower divertor Y total ( Γ = C x D y Γ +Γ D C ) B B D CII S / XB S / XB CII D α, γ α, γ CII / D α CII / D γ Shot Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #21

23 Comparison of nearly identical ELMy H-mode plasmas show that the total divertor carbon source has decreased significantly in DIII-D since 1993, without any subsequent change in core carbon concentration! Intensity (a.u.) 1 D ELMy H-mode Outer Strikepoint #781 (6-93) #945 (1-97) (Å) C II doublet Spectra normalized to D α intensity & for different detector responses (intensified vs. non-intensified) LSN #781 #945 plasmas I p (MA) n e (cm -3 ) 4.6x1 13 5x1 13 P inj (MW) W dia (MJ) R OSP (cm) CII / D α (OSP).23.2 f core, C (%) Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #22

24 1 The outer mid-plane carbon source has remained large and constant, in contrast to the significant decrease in lower divertor yield / sources. Attached ELMy H-mode >1 shots post-boronization OVI / D Lyβ CIII / D Lyβ Relative midplane XUV spectroscopy of impurity resonance lines: CIII (977 Å) OVI (13 Å) D Lyβ (125 Å) 1 Average carbon yield using S/XB technique and absolute calibration: Y midplane ~ 1-2% Shot Absolute CIII & CII intensities and S/XB technique indicate significant carbon influx from first wall (~2 A). Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #23

25 Despite the significant decrease in lower divertor yield / source, the core carbon fraction has not decreased. Attached ELMy H-mode >1 shots post-boronization Core carbon fraction (%) 8 7 Detached ELMy H-mode 6 Attached ELMy H-mode 5 Average shot number Based on r/a =.72 carbon concentration from visible CER. Consistent with larger f carbon database compiled by M. Wade & day-to-day experience. Some shots unavailable. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #24

26 Fractional radiated power, which is typically dominated by carbon, has not significantly decreased either. Attached ELMy H-mode >1 shots post-boronization Lower divertor Core (LSN only) Agrees qualitatively with CER core carbon spectroscopy results Shot Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #25

27 Summary: DIII-D Y chem Study Old DIII-D results for Y chem are in agreement with other tokamaks... JET: Y chem = 2 % T surf =45K ASDEX-U: Y chem = 1-2 % T surf =35K DIII-D ( ) Y chem ~ 2 % T surf ~4 K But present chemical and total yields are greatly reduced DIII-D (1999): Y chem ~.1% T surf ~4K DIII-D tile: Y chem = % T surf =6K (PISCES) Boronizations are the most likely cause for the Y chem reduction 3+ boronizations have applied ~2.5 microns of boron. No major tile changes or clean-ups in lower divertor in over six years both JET and ASDEX have refit lower divertor several times. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #26

28 Summary on Y total & Carbon sources Reduced Y chem (and other effects?) have significantly reduced the measured total carbon outflux from the lower divertor. Chemical erosion is now a minor player in lower divertor erosion with Y chem ~.1% << Y phys ~1-5%. No simultaneous decrease in core carbon fraction is found. Two explanations are possible: 1. Carbon ion SOL transport always adjusts to equilibrate thermal gradient vs. diffusive forces, making the source amplitude unimportant (preliminary UEDGE results show this effect). 2. The divertor is the not the principal source of carbon in the core plasma (e.g. All Be divertor in JET had carbon as main core impurity). Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #27

29 Laboratory studies of DIII-D graphite tiles effect of boronization on chemical erosion yield. #28

30 Plan: Use PISCES at UCSD to directly assess Y chem of DIII-D divertor tiles Two DIII-D lower divertor tiles removed (Summer 98) SEM and profilimetry revealed a >micron-depth low-z deposition layer at the inner divertor. ~8 discharges since last boronization. Visual inspection shows a metallic-like surface substantially different than virgin ATJ graphite. Section of tile exposed in PISCES-B linear plasma device Steady-state exposure with similar Γ and T e to DIII-D divertor. 3 ev incident energy fixed by target bias minimal Y phys. In-situ surface analysis station. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #29

31 PISCES-B Experimental Configuration Surface Analysis System Sample Manipulator Target C, W, Be Plasma Source PISCES-B Linear Plasma Device Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #3

32 Y chem Measurements on PISCES Weight loss of sample net yield -> gross yield correction from modeling. CD band spectroscopy Calibrated visible spectrometer. Benchmarked with CD 4 puffing through target. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #31

33 Calibrated CD 4 injection through PISCES target & High resolution spectroscopy provide detailed information about hydrocarbon transport & Y chem Sample Face Spectrometer Slit Image Axis for Spatially Resolved Emission, I(z) CD radical band (43 nm) axial profile Background Level CD 4 injection Axial Position (cm) Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #32

34 Summary of PISCES & UTIAS erosion tests on DIII-D tiles DIII-D CD-band molecular excitation rates measured Apparent Y chem < 1-3 in DIII-D. Energy dependence: Y chem Ε (.5 1) Surface composition 5% boron initially on surface. Y chem reduced x4 compared to virgin porous graphite. < 1 minutes of plasma exposure removed most of the carbon from the surface! Flux dependence?: apparently not needed to explain low Y chem. Preliminary result from UTIAS indicates portion of DIII-D redep film is resistant to O 2 chemical removal Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #33

35 D/XB CD 43 nm PISCES-B D/XB experiment PISCES-A This experiment 2e12 cm -3 3e12 cm Te (ev) D/XB Measurements (Molecules / Photon ratio) D/XB~1 is a maximum. Reproduces previous result. Implication: DIII-D CD-band spectroscopy used D/XB=1...but T e < 5 ev in PDD. Revised upper limit from CD-band spectroscopy: Y chem < 3-4x1-4 Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #34

36 WBC Erosion Code Has Been Thoroughly Benchmarked Against PISCES Data. 1 e-folding distance for CD (cm) 1 CD penetration vs. density, with T e ~ 4 ev 4.5 ev 4 ev 3.5 ev 1.E+11 1.E+12 1.E+13 electron density near target (cm -3 ) PISCES-B WBC prediction 3.5 ev 3.5 ev D/XB D/XB vs. density, with T e ~ 4 ev WBC /w Bethe- Born PISCES-B 4.5 ev 4 ev 3.5 ev 3.5 ev 3.5 ev 1.E+11 1.E+12 1.E+13 electron density (cm-3) WBC sub-gyro Monte-Carlo model (J. Brooks, ANL) includes full dissociative reactions for CD 4. Model matches both CD penetration and photon efficiency. Strongly non-linear penetration vs. n e Very large n e dependence on D/XB for approx. constant T e. Questions constant D/XB used in tokamak experiments during density scan Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #35

37 7.E-3 Chemical erosion yield 6.E-3 5.E-3 4.E-3 3.E-3 2.E-3 1.E-3 T < 15 C Power law fit y = 1.E-3xE.4 Energy dependence on Y chem Y chem E -.4 Γ= 1 23 s -1 m -2 T e ~ 4 ev.e Bias Voltage (V) Different energy dependence on chemical erosion yield from one experiment to another. PISCES data is more reliable in the sense that bias voltage is directly controlled...and all other exposure conditions are constant. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #36 Chemical Erosion Yield (CH/ion) K YsurfD A Up PISCES JET Average Energy (ev)

38 1% 9% 8% 7% 6% 5% 4% Oxygen Nitrogen Carbon Boron Auger surface analysis of DIII-D tile surface pre and post exposure on PISCES-B 3% 2% 1% % Preexposure Postexposure 2.5 Virgin graphite Exposure conditions: E = 3 ev Γ= 1 23 s -1 m -2 T e ~ 5 ev n e ~ 1.5x1 13 cm -3 CD band intensity (a.u.) Y chem =2.8x1-3 DIII-D tile with boron Y chem =1.1x Axial distance from target (cm) Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #37

39 Discussion Chemical erosion in the lower divertor is NOT the source of carbon in detached plasmas. Yet substantial atomic carbon radiation / flux is measured despite T e < 5 ev, i.e. no physical sputtering? Net erosion is eliminated everywhere in lower divertor! Strong indications that boronizations have substantially reduced the chemical and total effective yields of carbon in the DIII-D tokamak. In-situ and laboratory experiments show Y chem reduced ~4-1x compared to virgin graphite. No need to invoke flux dependence as method of reduced Y chem Future work Test more tile samples (PISCES and UofT) Remove more complete poloidal set of tiles during next vent? Incorporate Y chem into DiMES / WBC modeling & mixed material modelling Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #38

40 Discussion (continued). These results are very encouraging for the use of carbon in the learning phase of any next-step, high duty-cycle DT device. Graphite is very forgiving of disruptions, ELMs, etc. Detached plasmas necessary for power handling Y phys = But large Y chem for graphite produces significant erosion / redeposition and Tritium retention. Based on the DIII-D results, ~24 hours of plasma exposure, including frequent boronizations, should condition graphite divertor tiles to obtain order of magnitude reduction in Y chem. Reduction of divertor carbon sources, APS, Nov. 1999, D. Whyte #39

Physics of the detached radiative divertor regime in DIII-D

Physics of the detached radiative divertor regime in DIII-D Plasma Phys. Control. Fusion 41 (1999) A345 A355. Printed in the UK PII: S741-3335(99)97299-8 Physics of the detached radiative divertor regime in DIII-D M E Fenstermacher, J Boedo, R C Isler, A W Leonard,

More information

UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance

UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance UEDGE Modeling of the Effect of Changes in the Private Flux Wall in DIII-D on Divertor Performance N.S. Wolf, G.D. Porter, M.E. Rensink, T.D. Rognlien Lawrence Livermore National Lab, And the DIII-D team

More information

Scaling of divertor heat flux profile widths in DIII-D

Scaling of divertor heat flux profile widths in DIII-D 1 Scaling of divertor heat flux profile widths in DIII-D C.J. Lasnier 1, M.A. Makowski 1, J.A. Boedo 2, N.H. Brooks 3, D.N. Hill 1, A.W. Leonard 3, and J.G. Watkins 4 e-mail:lasnier@llnl.gov 1 Lawrence

More information

THE ADVANCED TOKAMAK DIVERTOR

THE ADVANCED TOKAMAK DIVERTOR I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and

More information

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK by M. GROTH, G.D. PORTER, J.A. BOEDO, N.H. BROOKS, R.C. ISLER, W.P. WEST, B.D. BRAY, M.E. FENSTERMACHER, R.J. GROEBNER,

More information

Simulation of Plasma Flow in the DIII-D Tokamak

Simulation of Plasma Flow in the DIII-D Tokamak UCRL-JC-129497 Preprint Simulation of Plasma Flow in the DIII-D Tokamak G.D Porter, T D. Rognlien, N. Wolf, J Boedo, R.C Isler This paper was prepared for submittal to 1998 International Congress on Plasma

More information

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D 20 th IAEA Fusion Energy Conference Vilamoura, Portugal, 1 to 6 November 2004 IAEA-CN-116/EX/P5-19 IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT

More information

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices!

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices! Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

Scaling of divertor heat flux profile widths in DIII-D

Scaling of divertor heat flux profile widths in DIII-D LLNL-PROC-432803 Scaling of divertor heat flux profile widths in DIII-D C. J. Lasnier, M. A Makowski, J. A. Boedo, S. L. Allen, N. H. Brooks, D. N. Hill, A. W. Leonard, J. G. Watkins, W. P. West May 20,

More information

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U EX/D-3 Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-6U N. Asakura ), H. Takenaga ), S. Sakurai ), G.D. Porter ), T.D. Rognlien ), M.E. Rensink ), O. Naito ), K. Shimizu

More information

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT by M.J. SCHAFFER, J.A. BOEDO, N.H. BROOKS, R.C. ISLER, and R.A. MOYER AUGUST 1998 DISCLAIMER This report was prepared as an account of work

More information

ITER A/M/PMI Data Requirements and Management Strategy

ITER A/M/PMI Data Requirements and Management Strategy ITER A/M/PMI Data Requirements and Management Strategy Steven Lisgo, R. Barnsley, D. Campbell, A. Kukushkin, M. Hosokawa, R. A. Pitts, M. Shimada, J. Snipes, A. Winter ITER Organisation with contributions

More information

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,

More information

Effect of the Surface Temperature on Net Carbon Deposition and Deuterium Co-deposition in the DIII-D Divertor

Effect of the Surface Temperature on Net Carbon Deposition and Deuterium Co-deposition in the DIII-D Divertor Effect of the Surface Temperature on Net Carbon Deposition and Deuterium Co-deposition in the DIII-D Divertor Presented by Dmitry Rudakov (UCSD) for the DiMES Team and Collaborators Presented at the 47th

More information

Scaling of divertor plasma effectiveness for reducing target-plate heat flux

Scaling of divertor plasma effectiveness for reducing target-plate heat flux Scaling of divertor plasma effectiveness for reducing target-plate heat flux T.D. Rognlien, I. Joseph, G.D. Porter, M.E. Rensink, M.V. Umansky, LLNL S.I. Krasheninnikov & A.Yu. Pigarov, UCSD; M. Groth,

More information

Detached Divertor Operation in DIII-D Helium Plasmas

Detached Divertor Operation in DIII-D Helium Plasmas UCRL-JC-130766 Preprint Detached Divertor Operation in DIII-D Helium Plasmas D.N. Hill, M.E. Fenstermacher, C.J. Lasnier, A.W. Leonard, M.R. Wade, W.P. West, and R.D. Wood This paper was prepared for submittal

More information

Helium effects on Tungsten surface morphology and Deuterium retention

Helium effects on Tungsten surface morphology and Deuterium retention 1 Helium effects on Tungsten surface morphology and Deuterium retention Y. Ueda, H.Y. Peng, H. T. Lee (Osaka University) N. Ohno, S. Kajita (Nagoya University) N. Yoshida (Kyushu University) R. Doerner

More information

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas M.E. Fenstermacher, T.H. Osborne, T.W. Petrie, C.J. Lasnier, A.W. Leonard, J.G. Watkins, 3 T.N. Carlstrom,

More information

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U 1 EX/P4-25 Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-6U T. Nakano, H. Kubo, N. Asakura, K. Shimizu and S. Higashijima Japan Atomic Energy Agency, Naka,

More information

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES

IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES IMPURITY ANALYSIS AND MODELING OF DIII-D RADIATIVE MANTLE DISCHARGES J. Mandrekas, W.M. Stacey Georgia Institute of Technology M. Murakami, M.R. Wade ORNL G. L. Jackson General Atomics Presented at the

More information

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D GA A24724 FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D by D.L. RUDAKOV, J.A. BOEDO, R.A. MOYER, N.H. BROOKS, R.P. DOERNER, T.E. EVANS, M.E. FENSTERMACHER, M. GROTH, E.M. HOLLMANN, S. KRASHENINNIKOV,

More information

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor J.N. Brooks, J.P. Allain Purdue University PFC Meeting MIT, July 8-10, 2009 CMOD Mo tile divertor erosion/redeposition

More information

ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS

ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS GA A2342 ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS by P.C. STANGEBY, J.G. WATKINS, G.D. PORTER, J.D. ELDER, S. LISGO, D. REITER, W.P. WEST, and D.G. WHYTE JULY 2 DISCLAIMER This report

More information

Angular Distribution Measurements of Sputtered Particles at UCSD

Angular Distribution Measurements of Sputtered Particles at UCSD Angular Distribution Measurements of Sputtered Particles at UCSD Presented by Russ Doerner for Jonathan Yu, Edier Oyarzabal and Daisuke Nishijima QMS measurements in unmagnetized plasma Moly Carbon clusters

More information

3D-DIVIMP(HC) CODE MODELING OF DIII-D DiMES POROUS PLUG INJECTOR EXPERIMENTS

3D-DIVIMP(HC) CODE MODELING OF DIII-D DiMES POROUS PLUG INJECTOR EXPERIMENTS GA A26737 3D-DIVIMP(HC) CODE MODELING OF DIII-D DiMES POROUS PLUG INJECTOR EXPERIMENTS by Y. MU, J.D. ELDER, P.C. STANGEBY, and A.G. McLEAN JULY 2010 DISCLAIMER This report was prepared as an account of

More information

Development of an experimental profile database for the scrape-off layer

Development of an experimental profile database for the scrape-off layer Development of an experimental profile database for the scrape-off layer M. Groth, 1 G.D. Porter, 1 W.M. Meyer, 1 A.W. Leonard, 2 T.H. Osborne, 2 D.P. Coster, 3 A. Kallenbach, 3 M. Wischmeier 3 N.H. Brooks,

More information

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer N. Smick, B. LaBombard MIT Plasma Science and Fusion Center PSI-19 San Diego, CA May 25, 2010 Boundary flows

More information

Divertor Heat Flux Reduction and Detachment in NSTX

Divertor Heat Flux Reduction and Detachment in NSTX 1 EX/P4-28 Divertor Heat Flux Reduction and Detachment in NSTX V. A. Soukhanovskii 1), R. Maingi 2), R. Raman 3), R. E. Bell 4), C. Bush 2), R. Kaita 4), H. W. Kugel 4), C. J. Lasnier 1), B. P. LeBlanc

More information

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D GA A25445 TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D by J.G. WATKINS, T.E. EVANS, C.J. LASNIER, R.A. MOYER, and D.L. RUDAKOV JUNE 2006 QTYUIOP DISCLAIMER This report was prepared

More information

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation 1 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation Y. Nakashima1), Y. Higashizono1), H. Kawano1), H. Takenaga2), N. Asakura2), N. Oyama2),

More information

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX 1 Dependences of the ertor and plane heat flux widths in NSTX T.K. Gray1,2), R. Maingi 2), A.G. McLean 2), V.A. Soukhanovskii 3) and J-W. Ahn 2) 1) Oak Ridge Institute for Science and Education (ORISE),

More information

MIGRATION OF ARTIFICIALLY INTRODUCED MICRON-SIZE CARBON DUST IN THE DIII D DIVERTOR

MIGRATION OF ARTIFICIALLY INTRODUCED MICRON-SIZE CARBON DUST IN THE DIII D DIVERTOR GA A25451 MIGRATION OF ARTIFICIALLY INTRODUCED MICRON-SIZE CARBON DUST IN THE DIII D DIVERTOR by D.L. RUDAKOV, W.P. WEST, C.P.C. WONG, N.H. BROOKS, T.E. EVANS, M.E. FENSTERMACHER, M. GROTH, S.I. KRASHENINNIKOV,

More information

Fusion Development Facility (FDF) Divertor Plans and Research Options

Fusion Development Facility (FDF) Divertor Plans and Research Options Fusion Development Facility (FDF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, M. Wade, V. Chan, R. Stambaugh (General Atomics) J. Canik (Oak Ridge National Laboratory) P. Stangeby

More information

Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance

Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance Alberto Loarte European Fusion Development Agreement Close Support Unit - Garching

More information

NSTX Plasma-Material Interface (PMI) Probe and supporting experiments

NSTX Plasma-Material Interface (PMI) Probe and supporting experiments NSTX Plasma-Material Interface (PMI) Probe and supporting experiments J.P. Allain 1,2, C.N. Taylor 1, B. Heim 1,3 PPPL Collaborators: C.H. Skinner, H.W. Kugel, R. Kaita, A.L. Roquemore 1 Purdue University,

More information

N.H. BROOKS, R.C. ISLER,

N.H. BROOKS, R.C. ISLER, GA A25427 MEASUREMENT OF C I KINETIC TEMPERATURE IN METHANE PUFFING EXPERIMENTS ON DIII-D AND IMPLICATIONS FOR SPECTROSCOPICALLY DISTINGUISHING CARBON SPUTTERING MECHANISMS by N.H. BROOKS, R.C. ISLER,

More information

Carbon Deposition and Deuterium Inventory in ASDEX Upgrade

Carbon Deposition and Deuterium Inventory in ASDEX Upgrade 1 IAEA-CN-116 / EX / 5-24 Carbon Deposition and Deuterium Inventory in ASDEX Upgrade M. Mayer 1, V. Rohde 1, J. Likonen 2, E. Vainonen-Ahlgren 2, J. Chen 1, X. Gong 1, K. Krieger 1, ASDEX Upgrade Team

More information

Simulation of Double-Null Divertor Plasmas with the UEDGE Code

Simulation of Double-Null Divertor Plasmas with the UEDGE Code Preprint UCRL-JC-134341 Simulation of Double-Null Divertor Plasmas with the UEDGE Code M. E. Rensink, S. L. Allen, G. 0. Porter, T. 0. Rognlien This article was submitted to 7th International Workshop

More information

Application of atomic data to quantitative analysis of tungsten spectra on EAST tokamak

Application of atomic data to quantitative analysis of tungsten spectra on EAST tokamak Technical Meeting on Uncertainty Assessment and Benchmark Experiments for Atomic and Molecular Data for Fusion Applications, 19-21 December 2016, Vienna, Austria Application of atomic data to quantitative

More information

EFDA European Fusion Development Agreement - Close Support Unit - Garching

EFDA European Fusion Development Agreement - Close Support Unit - Garching Multi-machine Modelling of Divertor Geometry Effects Alberto Loarte EFDA CSU -Garching Acknowledgements: K. Borrass, D. Coster, J. Gafert, C. Maggi, R. Monk, L. Horton, R.Schneider (IPP), A.Kukushkin (ITER),

More information

THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST

THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST GA A25482 13 C-TRACER EXPERIMENTS IN DIII-D PRELIMINARY IN THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST by P.C. STANGEBY, S.L. ALLEN, N. BEKRIS, N.H. BROOKS,

More information

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas DIVIMP simulation of W transport in the SOL of JET H-mode plasmas A. Järvinen a, C. Giroud b, M. Groth a, K. Krieger c, D. Moulton d, S. Wiesen e, S. Brezinsek e and JET- EFDA contributors¹ JET-EFDA, Culham

More information

Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe

Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe Flow Measurements in the DIII-D Divertor Flow Measurements in the Divertor Region of DIII-D and Plasma Characterization using a Reciprocating Probe J. Boedo, R. Lehmer, R. Moyer, J. Watkins, D. Hill, T.

More information

GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING MEASUREMENTS IN DIII D

GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING MEASUREMENTS IN DIII D GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING by J.G. WATKINS, P.C. STANGEBY, J.A. BOEDO, T.N. CARLSTROM, C.J. LASNIER, R.A. MOYER, D.L. RUDAKOV, D.G. WHYTE JULY 2000 DISCLAIMER This report

More information

1 EX/P4-8. Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device

1 EX/P4-8. Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device 1 EX/P4-8 Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device T. Hino 1,2), T. Hirata 1), N. Ashikawa 2), S. Masuzaki 2), Y. Yamauchi

More information

Plasma shielding during ITER disruptions

Plasma shielding during ITER disruptions Plasma shielding during ITER disruptions Sergey Pestchanyi and Richard Pitts 1 Integrated tokamak code TOKES is a workshop with various tools objects Radiation bremsstrahlung recombination s line s cyclotron

More information

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.

Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment. Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment E. Kolemen a, S.L. Allen b, B.D. Bray c, M.E. Fenstermacher b, D.A. Humphreys c, A.W. Hyatt c, C.J. Lasnier b,

More information

Thomas Schwarz-Selinger. Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes

Thomas Schwarz-Selinger. Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes Max-Planck-Institut für Plasmaphysik Thomas Schwarz-Selinger Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes personal research interests / latest work

More information

Critical Gaps between Tokamak Physics and Nuclear Science. Clement P.C. Wong General Atomics

Critical Gaps between Tokamak Physics and Nuclear Science. Clement P.C. Wong General Atomics Critical Gaps between Tokamak Physics and Nuclear Science (Step 1: Identifying critical gaps) (Step 2: Options to fill the critical gaps initiated) (Step 3: Success not yet) Clement P.C. Wong General Atomics

More information

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS GA A25488 PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS by D.A. HUMPHREYS, D.G. WHYTE, M. BAKHTIARI, R.D. DERANIAN, E.M. HOLLMANN, A.W. HYATT, T.C. JERNIGAN, A.G.

More information

Sputtering yield measurements during low energy xenon plasma bombardment

Sputtering yield measurements during low energy xenon plasma bombardment JOURNAL OF APPLIED PHYSICS VOLUME 93, NUMBER 9 1 MAY 2003 Sputtering yield measurements during low energy xenon plasma bombardment R. P. Doerner a) Center for Energy Research University of California at

More information

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D GA A443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D by R.J. GROEBNER, T.N. CARLSTROM, K.H. BURRELL, S. CODA, E.J. DOYLE, P. GOHIL, K.W. KIM, Q. PENG, R. MAINGI, R.A. MOYER, C.L. RETTIG, T.L. RHODES,

More information

Hydrocarbon transport in the MkIIa divertor of JET

Hydrocarbon transport in the MkIIa divertor of JET INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 45 (23) 39 319 PLASMA PHYSICS AND CONTROLLED FUSION PII: S741-3335(3)37188-X Hydrocarbon transport in the MkIIa divertor of JET A Kirschner

More information

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Modelling of JT-60U Detached Divertor Plasma using SONIC code J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Modelling of JT-60U Detached Divertor Plasma using SONIC code Kazuo HOSHINO, Katsuhiro SHIMIZU, Tomonori TAKIZUKA, Nobuyuki ASAKURA and Tomohide NAKANO Japan

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.

More information

Divertor Requirements and Performance in ITER

Divertor Requirements and Performance in ITER Divertor Requirements and Performance in ITER M. Sugihara ITER International Team 1 th International Toki Conference Dec. 11-14, 001 Contents Overview of requirement and prediction for divertor performance

More information

RADIATIVE DIVERTOR AND SOL EXPERIMENTS IN OPEN AND BAFFLED DIVERTORS ON DIIIÐD *

RADIATIVE DIVERTOR AND SOL EXPERIMENTS IN OPEN AND BAFFLED DIVERTORS ON DIIIÐD * RADIATIVE DIVERTOR AND SOL EXPERIMENTS IN OPEN AND BAFFLED DIVERTORS ON DIIIÐD * S.L. ALLEN, N.H. BROOKS, R. BASTASZ, à J. BOEDO, Æ J.N. BROOKS, J.W. CUTHBERTSON, Æ T.E. EVANS, M.E. FENSTERMACHER, D.N.

More information

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Bolometry H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy) Revised May 28, 2002 1. Radiated power Time and space resolved measurements of the total plasma radiation can be done by means

More information

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes S. Gangadhara,. Laombard M.I.T. Plasma Science and Fusion Center, 175 Albany St., Cambridge, MA 2139 USA Abstract Accurate

More information

Experimental results and modelling of ASDEX Upgrade partial detachment

Experimental results and modelling of ASDEX Upgrade partial detachment Experimental results and modelling of ASDEX Upgrade partial detachment M. Wischmeier 1 With thanks to X. Bonnin 2, P. Börner 3, A. Chankin 1, D. P. Coster 1, M. Groth 4, A. Kallenbach 1, V. Kotov 3, H.

More information

Experimental test of the neoclassical theory of poloidal rotation

Experimental test of the neoclassical theory of poloidal rotation Experimental test of the neoclassical theory of poloidal rotation Presented by Wayne Solomon with contributions from K.H. Burrell, R. Andre, L.R. Baylor, R. Budny, P. Gohil, R.J. Groebner, C.T. Holcomb,

More information

ELMs and Constraints on the H-Mode Pedestal:

ELMs and Constraints on the H-Mode Pedestal: ELMs and Constraints on the H-Mode Pedestal: A Model Based on Peeling-Ballooning Modes P.B. Snyder, 1 H.R. Wilson, 2 J.R. Ferron, 1 L.L. Lao, 1 A.W. Leonard, 1 D. Mossessian, 3 M. Murakami, 4 T.H. Osborne,

More information

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options A.M. Garofalo, T. Petrie, J. Smith, V. Chan, R. Stambaugh (General Atomics) J. Canik, A. Sontag, M. Cole (Oak Ridge National Laboratory)

More information

Chemical Erosion and Critical Issues for ITER

Chemical Erosion and Critical Issues for ITER Chemical Erosion and Critical Issues for ITER J. Roth Max-Planck-Institut für Plasmaphysik, Garching Chemical Erosion Studies Erosion yields: Dependence on temperature, energy and flux Emitted hydrocarbons

More information

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection M. Porkolab, P. C. Ennever, S. G. Baek, E. M. Edlund, J. Hughes, J. E.

More information

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod PFC/JA-94-15 Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod J.A. Goetz, B. Lipschultz, M.A. Graf, C. Kurz, R. Nachtrieb, J.A. Snipes, J.L. Terry Plasma

More information

In-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust

In-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust FT/P1-19 In-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust T. Hino 1), H. Yoshida 1), M. Akiba 2), S. Suzuki 2), Y. Hirohata 1) and Y. Yamauchi 1) 1) Laboratory of Plasma

More information

EU Plasma-Wall Interactions Task Force

EU Plasma-Wall Interactions Task Force Recent results on material migration and fuel retention in JET V. Philipps and JET TFE co-workers* Overview on present results on erosion, deposition and fuel retention in last JET campaign (2001-2004,C5-C15)

More information

GA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES

GA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES GA A311 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES by C.C. PETTY, M.R. WADE, J.E. KINSEY, R.J. GROEBNER, T.C. LUCE, and G.M. STAEBLER AUGUST 1999 This report

More information

ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS

ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS A. LOARTE, R.D. MONK, J.R. MARTÍN-SOLÍSa,D.J.CAMPBELL, A.V. CHANKIN b, S. CLEMENT, S.J. DAVIES, J. EHRENBERG, S.K. ERENTS c,h.y.guo, P.J. HARBOUR,

More information

PSI meeting, Aachen Germany, May 2012

PSI meeting, Aachen Germany, May 2012 Constraining the divertor heat width in ITER D.G. Whyte 1, B. LaBombard 1, J.W. Hughes 1, B. Lipschultz 1, J. Terry 1, D. Brunner 1, P.C. Stangeby 2, D. Elder 2, A.W. Leonard 3, J. Watkins 4 1 MIT Plasma

More information

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Non-solenoidal startup using point-source DC helicity injectors

More information

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas D. Reiter Institut für Plasmaphysik, FZ-Jülich, Trilateral Euregio Cluster Atomic and Molecular Data for Fusion Energy

More information

Estimating the plasma flow in a recombining plasma from

Estimating the plasma flow in a recombining plasma from Paper P3-38 Estimating the plasma flow in a recombining plasma from the H α emission U. Wenzel a, M. Goto b a Max-Planck-Institut für Plasmaphysik (IPP) b National Institute for Fusion Science, Toki 509-5292,

More information

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France Exhaust scenarios Alberto Loarte Plasma Operation Directorate ITER Organization Route de Vinon sur Verdon, 13067 St Paul lez Durance, France Acknowledgements: Members of ITER Organization (especially R.

More information

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General

More information

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract This work was performed under the auspices of the U.S. Department of Energy by under contract DE-AC52-7NA27344. Lawrence Livermore National Security, LLC The ITER tokamak Tungsten (W) is attractive as

More information

Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles

Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles Y. Hirohata 1), T. Tanabe 2), Y. Oya 3), K. Shibahara 4), M. Oyaidzu 5), T. Arai 6), K. Masaki 6), Y. Gotoh 6), K. Okuno

More information

Abstract Submitted for the DPP99 Meeting of The American Physical Society

Abstract Submitted for the DPP99 Meeting of The American Physical Society Abstract Submitted for the DPP99 Meeting of The American Physical Society Sorting Category: 5.1.1.2(Experimental) Calibration of a Three Path Thomson System at DIII- D 1 B.D. BRAY, C.L. HSIEH, T.N. CARLSTROM,

More information

Predicting the Rotation Profile in ITER

Predicting the Rotation Profile in ITER Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton

More information

Effect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma

Effect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma THE HARRIS SCIENCE REVIEW OF DOSHISHA UNIVERSITY, VOL. 56, No. 1 April 2015 Effect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma

More information

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod Alcator C-Mod Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod B. LaBombard, R.L. Boivin, M. Greenwald, J. Hughes, B. Lipschultz, D. Mossessian, C.S.

More information

Neutral particle behavior in divertor simulator MAP-II

Neutral particle behavior in divertor simulator MAP-II cpp header will be provided by the publisher Neutral particle behavior in divertor simulator MAP-II H. Matsuura 1, S. Kado 2, and Y. Kuwahara 3 1 Graduate School of Engineering, Osaka Prefecture University,

More information

Non-Solenoidal Plasma Startup in

Non-Solenoidal Plasma Startup in Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique

More information

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges

Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges by J.R. Ferron with T.C. Luce, P.A. Politzer, R. Jayakumar, * and M.R. Wade *Lawrence Livermore

More information

Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell

Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell Plasma-neutrals transport modeling of the ORNL plasma-materials test stand target cell J.M. Canik, L.W. Owen, Y.K.M. Peng, J. Rapp, R.H. Goulding Oak Ridge National Laboratory ORNL is developing a helicon-based

More information

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code Contrib. Plasma Phys. 56, No. 6-8, 772 777 (2016) / DOI 10.1002/ctpp.201610008 Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code K. Gała zka 1, I. Ivanova-Stanik 1, M. Bernert 2, A. Czarnecka

More information

Ion Temperature Measurements in the

Ion Temperature Measurements in the Ion Temperature Measurements in the PEGASUS Toroidal Experiment M.G. Burke, M.W. Bongard, R.J. Fonck, D.J. Schlossberg, A.J. Redd 52 nd Annual APS-DPP University of Wisconsin-Madison Chicago, IL November

More information

Dust Studies in Fusion Devices

Dust Studies in Fusion Devices Dust Studies in Fusion Devices D.L. Rudakov Presented at the PFC Meeting Boston MA July 7-10, 2009 10 µm Including contributions from A. Litnovsky, N. Asakura, N. Ashikawa, G. DeTemmerman, S. Ratynskaia

More information

Comparison of plasma breakdown with a carbon and ITER-like wall

Comparison of plasma breakdown with a carbon and ITER-like wall Comparison of plasma breakdown with a carbon and ITER-like wall P.C. de Vries, A.C.C. Sips, H.T. Kim, P.J. Lomas, F. Maviglia, R. Albanese, I. Coffey, E. Joffrin, M. Lehnen, A. Manzanares, M. O Mulane,

More information

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles 1 EXD/P3-01 Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles J-W. Ahn 1, J.M. Canik 1, R. Maingi 1, T.K. Gray 1, J.D. Lore 1, A.G. McLean 1, J.-K. Park 2, A.L.

More information

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography EFDA JET CP(02)01/03 T Eich, A Herrmann, P Andrew and A Loarte Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography . Power Deposition Measurements

More information

ABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D

ABSTRACT, POSTER LP1 12 THURSDAY 11/7/2001, APS DPP CONFERENCE, LONG BEACH. Recent Results from the Quiescent Double Barrier Regime on DIII-D ABSTRACT, POSTER LP1 1 THURSDAY 11/7/1, APS DPP CONFERENCE, LONG BEACH Recent Results from the Quiescent Double Barrier Regime on DIII-D E.J. Doyle, K.H. Burrell, T. Casper, J.C. DeBoo, A. Garofalo, P.

More information

Modelling of Carbon Erosion and Deposition in the Divertor of JET

Modelling of Carbon Erosion and Deposition in the Divertor of JET EFDA JET CP(01)02-64 A. Kirschner, V. Philipps, P. Wienhold, W. Fundamenski, G. Matthews, P. Coad, M. Stamp, D. Coster, D. Elder, P. Stangeby and JET EFDA Contributors Modelling of Carbon Erosion and Deposition

More information

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK by M.A. MAKOWSKI, A.W. LEONARD, J.D. ELDER, C.J. LASNIER, J. NICHOLS, T.H. OSBORNE, P.C. STANGEBY and J.G. WATKINS OCTOBER 2012 DISCLAIMER

More information

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Observation of Neo-Classical Ion Pinch in the Electric Tokamak* 1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,

More information

Advances in the Physics Basis of the Hybrid Scenario on DIII-D

Advances in the Physics Basis of the Hybrid Scenario on DIII-D Advances in the Physics Basis of the Hybrid Scenario on DIII-D C.C. Petty 1), W.P. West 1), J.C. DeBoo 1), E.J. Doyle 2), T.E. Evans 1), M.E. Fenstermacher 3), M. Groth 3), J.R. Ferron 1), G.R. McKee 4),

More information

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET Journal of Nuclear Materials 363 365 (2007) 989 993 www.elsevier.com/locate/jnucmat Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET T. Eich a, *, A.

More information

Tungsten: An option for divertor and main chamber PFCs in future fusion devices

Tungsten: An option for divertor and main chamber PFCs in future fusion devices ASDEX Upgrade Tungsten: An option for divertor and main chamber PFCs in future fusion devices R. Neu, R. Dux, A. Kallenbach, C.F. Maggi, T. Pütterich, M. Balden, T. Eich, J.C. Fuchs, O. Gruber, A. Herrmann,

More information