On Dust Particle Dynamics in Tokamak Edge Plasma

Size: px
Start display at page:

Download "On Dust Particle Dynamics in Tokamak Edge Plasma"

Transcription

1 On Dust Particle Dynamics in Tokamak Edge Plasma Sergei Krasheninnikov University of California, San Diego, USA With contributions from Y. Tomita 1, R. D. Smirnov, and R. K. Janev 1 1 National Institute for Fusion Science, Toki, Gifu , Japan The Graduate University for Advanced Studies, Toki, Gifu , Japan December, 003, Kyoto, Japan

2 Outline I. Introduction II. Dust power and particle balance in tokamak III. Dust in magnetized sheath IV. Impact of surface roughness and dust flights V. Dust and core contamination VI. Conclusions

3 I. Introduction Significant amount of dust particles is observed in the chambers of fusion devices Winter PPCF 1998 But so far an impact of dust on the performance of current fusion devices is not clear

4 1) evidence of dust particles in fusion devices a) JIPPT-IIU (NIFS, Japan) [ K. Narihara, et al., Nuclear Fusion 37 (1997) 1177 ] _large scattering signal in Thomson scattering system _most cases: after discharge with disruption _ several cases : during discharges m : small solid particles such as flakes and microparticles _ ~ 100 ms after disruption FIG (a) (a) Raw scattering signals on on the the fift polychromator. X, X, Y and Z denote the the spec channels. Large scattering signals appeared ms. ms. Similar signals appeared on on channe 1, 1,,, 5 5 and and 7 7 at at different times. A plasm current Ip Ip is is shown for for reference.

5 [ J. Sharpe, A. Sagara, et al., J. Nucl. Mater (003) 455] C Au Ti Ti Ti Fe 10 µ m Carbon, steel, and titanium particles collected from LHD coil armor. The gold results from the coating of particles which is used to avoid charging effects on the non-conductive filter substrate.

6 Sharpe et al., J. Nucl. Mater 003 However, an existence of dust particles in burning plasma experiments poses a high threat: it can contain toxic and radioactive materials and retain tritium

7 We show that dust in fusion devices can be very mobile and during one shot dust particles can move through edge plasma on distances much larger that the scrape-of-layer (SOL) width and comparable to tokamak radii Our estimates indicate that it is plausible that transport of dust particles can be an important mechanism of impurity transport into core plasma

8 II. Dust power and particle balance in tokamak Can dust particle survive in fusion plasma? Consider power and mass balance of carbon dust particles accounting for BB radiation, evaporation, RES, and physical and chemical sputtering In order to simplify our estimates we will assume that electron and ion temperatures are close to Ti Te = T~10 ev and plasma density is about cm 3. Such parameters are rather typical for tokamak divertor plasma

9 10 1 heating power cooling power P, W/m n=10 14 cm -3 total n=10 13 cm -3 thermal evaporation n=10 1 cm -3 radiation T d, K

10 drd /dt, µm/s total rate thermal evaporation physical sputtering RES chemical sputtering T d, K

11 10 5 drd /dt, µm/s n=10 14 cm -3 n=10 13 cm -3 n=10 1 cm T d, K Yes, in fusion edge plasma dust particle of ~1 µm scale can live long enough to contribute to dust particle transport!

12 III. Dust in magnetized sheath Dust charge Z d is determined by the ambipolarity of plasma flux to dust particle e Z r d d =Λ T, where Λ ~3 The forces acting on dust particle M d V d dt d = F F E F ( ) = ezde, F = ς πr M nv V V, g = g, F Md fric F d i i p d 3 M = πrdεm B B 4πR sat tor R R,

13 Estimates show that electric and friction forces dominate in edge plasmas In fusion devices dust, probably, is formed at the wall surface Therefore, plasma environment near the wall (sheath) important for dust dynamics y y plasma flow F fric -ϕ (y) F E B α z x V diam λ d ρ i x λ d E ρ i y

14 Dust motion in y-direction can be described by effective potential rt Ud( y) = αςfnshtπrd y+ Λ d ϕ( y) e y min y U d (y) In case of small oscillations in the vicinity of y min, such oscillations can be described by the following equation d d y dt dy = Ω d( yd y min ) ν d V, dt Ω 1 d = M d d Ud, dy y= y min νv = ςfmn i shviπrd, Ω d ~ 10 s >> ν V ~ 1s

15 In both z- and x- directions friction forces continuously accelerate dust particle Due to this acceleration dust particle gains speed ~ cm / s in ~10 3 s Therefore, surface inhomogeneity (corner, step) can cause particle to fly V d dust particle V d dust particle wall wall

16 IV. Impact of surface roughness and dust flights Even less dramatic surface roughness can be a reason for dust particle flights h w λ w particle trajectory wall wall a) Small amplitude of surface wave h w << ρ i d y dt d ( ) = Ω y ymin ( x ), y ( x ) = y + h sin( k x ), min min w w

17 ( x) ( fric x ) d x F = fric x = F dt M M d d t, x res d d w fric ( Resonance occurs at t Ω M k F ) and it is meaningful resonance if Sres tresωd >> 1 For S res >>1 we can integrate the equations of motion and find 1 / π S y d( t) hw Sres sin res ( ) sin dt + π π Ω 4 4 For y () t > ρ h > ρ / S we expect large excursion of dust trajectory d i w i res

18 b) Large amplitude of surface wave h w >> ρ i In order to overcome the effect of centrifugal force and confine dust particle in effective potential well within sheath it is necessary to obey the inequality ( x) MV d d Ffric ( y) ( x) = < F F Rw R fric α fric, w where Rw 1/ hwkw is the effective wall curvature radius and is distance along the wall passed by the particle Particle cannot be confined anymore within the sheath after 1 α conf h k w w

19 Analyzing resonance conditions we find that for h w >> ρ i dust particle looses confinement within the sheath before reaching resonance conditions Once particle looses confinement within the sheath it starts to fly and bounce time to time the sheath article trajectory wall

20 We notice that the rejection of the particle by the wall can be due to both of the sheath electric field and wall structure itself Just to illustrate the process of particle flights, we consider the case where the wall surface is corrugated in x-direction according to the following expression i x yw( x) = ( 1) hw 1 i, for i λ w x i+ 1, (36) λ w

21 where i is the integer number, and h w and λ w are the effective magnitude and wave-length of the corrugation We will assume that λ β >> h >> ρ and introduce the angle w w i 4h / λ << 1, so that the inclination of the surface to x-coordinate w w w is ±β w We will assume that the energy of dust particle is large and after it penetrates through the sheath it experiences specula reflection by the wall.

22 Assume that initially dust particle in the sheath was about the minimum of potential well U d located in the sheath ( sh) Then it will be accelerated along the surface by the force F fric until it reaches breaking point of the surface at x than time the energy sh F fric =λ i w / and flies, gaining, by E1 ~ ( ) λ w. (37) With increasing particle energy its re-entry of the sheath occurs at a distance from original take off, which is much larger than λ w

23 Therefore we can assume that particle randomly hits positive and negative slop of the wall As a result, the pitch angle of the particles leaving the sheath µ dw dw x y V = sign( V ( ) ( ) ) dw xy Vdw (, ), (38) ( ( xy, ) ) ( xy, ) ( y = ( ) ) + ( dw ( x) ) (where Vdw Edw / Md Vdw V and where V dw the particle velocities taken at the moment when particle leaves the (...) are

24 wall) is randomly changed by β w <<1 and the evolution of µ dw can be described as a diffusive process We will consider only this evolution assuming that averaged value of pitch angle, 0< µ dw < 1 Notice that in this case particle scattering from the wall cannot flip the ( x) sign of V dw which, then, coincides with the direction of diamagnetic ion flow in the sheath, which accelerates dust particle Then µ dw can be found from diffusive equation

25 d µ dw dt ~ D, (39) µ with the effective diffusion coefficient D µ ~ β t w coll, (40) and where t coll is the time between two consecutive collisions Taking into account that t coll is determined by reversing the sing of y- component of the velocity by friction force we find

26 t coll ~ ( ( xy, Edw M ) d µ αf sh fric 1 / dw. (41) Next we consider the particle energy gain sh Dust particle is exposed by accelerating force of diamagnetic flow F fric for the time, τ coll, when particle moves through the sheath with the thickness ~ ρ i Therefore, for µ dw > β, we have w

27 τ coll ~ ρ i ( ( xy, 1 / ) dw E M d µ dw, (4) and de ( xy, sh ( xy, / dw Ffricτ ( 1 coll Edw M ) d dt Assuming E ~ ( xy, dw t coll > E 1 from Eq. (38)-(4) we find. (43) E ( xy, dw sh sh t F ~ Ffricρ α i 8 β M ρ w fric d i 17 /, (44)

28 µ dw ~ αβ 3 w sh t F M ρ fric d i 1 / / 7. (45) Taking into account that our analysis is limited by µ dw <1, we find that our approximation works for t < t = µ 1 αβ 3 w M F ρ d i sh fric 1 /. (46) By the time t ~ t µ dust particle moves at the distance, L µ ~ ρi 4 αβ, (47) w

29 along the wall in x-direction and gains the energy ( xy, ( F Edw Md Vd x ) ( y) ~ ( ) ~ M ( d V ) fricρi d ~ ~ αβ µ β In order to satisfy inequality E restriction h w 1 4 < ( ) w i 1 ( xy, dw sh w sh wffric L > E 1 we find the following λ ρ /. (49) µ. (48) At t > t µ x-component of particle velocity can turn to be negative due to scattering off the wall

30 As a result particles can fly back toward their initial position and start to lose the energy In the case where wavy wall structure like (36) would be in z-direction then treatment of dust particle motion similar to that we performed gives us the following asymptotic dependences ( yz, ) ( sh) dw fric E F t M ~ ( ) 13 / ( yz, ) dw w Edw E1 µ ~ αβ ln d, (50) ( ) ( ), (51) where the notation is obvious

31 Notice that in this case energy of the particle increases t due to ion friction force caused by plasma flow along the magnetic field lines, which exist in entire recycling region

32 V. Dust and core contamination Such flights of dust particles can result in their motion toward core and contamination of core plasma with impurity Assuming that main material dust consist of is carbon we find that in each dust particle with r d 4 ~3 10 cm and ~ gcm / ρ d 3 there are N C ~10 13 carbon atoms

33 In order to maintain impurity fraction, ξ imp, in the core, the carbon influx through separatrix should be about Γ ( sep) ( sep) imp imp H ( sep Γ ) H is the flux of hydrogenic species though separatrix =ξ Γ, where For ξ imp ~10 and Γ H sep ( ) ~ s we find Γ imp ( sep) ~ s and it would take the flux, Γ d sep required impurity influx ( ) ~ s, of dust particle to establish

34 Assuming that dust particles penetrate into the core through an area ~ cm and dust particle speed is ~ 10 3 cm / s we find dust particle density at separatrix nd ~3 10 cm 3

35 Where this dust may come from? Assume that carbon dust is originated at the walls of main chamber due to plasma flux to the wall However, since carbon sputtering yield, Y C, is about a few percent, in order to maintain about one percent of core impurity fraction, supplied to the core as a dust, we should assume that roughly ~100% of sputtered carbon is transformed into dust and then flies to the core ( sep ) sep sep imp imp H ( ) C H ( ) Γ ~ ξ Γ ~ Y Γ It looks to be unlikely the case!

36 Another possibility, dust formation in the vicinity of divertor striking points, looks much more plausible! Indeed, due to strong plasma recycling in the divertor, plasma flux ( div) to divertor targets, Γ H, can easily be as high as s Then carbon influx into core Γ imp written as follows Γ ( sep) ~ ( sep) ( imp Y C dust flight ΓH div ) = η η s with dust can be where η dust is the fraction of sputtered carbon converted into dust, η flight is the flying fraction of dust, which flies to the core

37 With, for example, Y C ~3% of sputtering yield, it gives sputtered carbon flux in divertor to be ~ s 1 If only η dust ~3% of these carbon atoms will be transformed to dust and, then, only η flight ~10% of dust particles will be launched towards the core, the relevant ( sep) impurity influx Γ imp ~ s through the saparatrix will be established Γ ( sep) ( ) imp = ~ YC ηdustηflightγh div s 1 Major axis Core Divertor plate Dust flights

38 VI. Conclusions Due to acceleration by plasma flows, dust particles can have a very high speed (~ 10 3 cm / s and even higher) Interactions of dust particles with surface inhomogeneities (including micro-roughness as well as steps, corners, etc.) can cause dust particle flights toward tokamak core It is feasible that dust formation in and transport from divertor region play an important role in core plasma contamination

39 However, even then, dust particle density around separatrix is ~3 10 cm 3, which makes it difficult to diagnose

Characterization of heated dust particles using infrared and dynamic images in LHD

Characterization of heated dust particles using infrared and dynamic images in LHD 1 EX/P4-7 Characterization of heated dust particles using infrared and dynamic images in LHD N Ashikawa 1), Y. Tomita 1), S. Masuzaki 1), A. Sagara 1), G. Kawamura 1), K. Nishimura 1), N. Ohno ) and LHD

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

Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device

Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device M. SHOJI, T. WATANABE, S. MASUZAKI, H. YAMADA, A. KOMORI and LHD Experimental

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

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

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

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

1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.

1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5. 1. Motivation power exhaust in JT-60SA tokamak 2. Tool COREDIV code 3. Operational scenarios of JT-60SA 4. Results 5. Conclusions K. Gałązka Efficient power exhaust in JT-60SA by COREDIV Page 2 The Institute

More information

Design window analysis of LHD-type Heliotron DEMO reactors

Design window analysis of LHD-type Heliotron DEMO reactors Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya

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

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

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

Neoclassical transport

Neoclassical transport Neoclassical transport Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 28 th January 2013 Dr Ben Dudson Magnetic Confinement Fusion (1 of 19) Last time Toroidal devices

More information

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Akihiro SHIMIZU, Takeshi IDO, Masaki NISHIURA, Ryohei MAKINO 1), Masayuki YOKOYAMA, Hiromi TAKAHASHI, Hiroe IGAMI, Yasuo YOSHIMURA, Shin KUBO,

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

Modeling and analysis of surface roughness effects on sputtering, reflection and sputtered particle transport *

Modeling and analysis of surface roughness effects on sputtering, reflection and sputtered particle transport * 278 Journai of Nuclear Materials 176 & 177 (1990) 278-282 North-Holland Modeling and analysis of surface roughness effects on sputtering, reflection and sputtered particle transport * J.N. Brooks Argonne

More information

My view on the vapor shielding issues

My view on the vapor shielding issues My view on the vapor shielding issues Sergei Krasheninnikov University of California San Diego, USA Consultancy Meeting on Atomic Data for Vapour Shielding in Fusion Devices IAEA, Vienna, Austria, 19-20

More information

Molecular Dynamics Study of Plasma Surface Interactions for Mixed Materials

Molecular Dynamics Study of Plasma Surface Interactions for Mixed Materials J. Plasma Fusion Res. SERIES, Vol. 9 () Molecular Dynamics Study of Plasma Surface Interactions for Mixed Materials Kaoru OHYA, Naohide MOHARA, Kensuke INAI, Atsushi ITO, Hiroaki NAKAMURA, Yoshio UEDA

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 Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak

Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak Effect of Ion Orbit Loss on Rotation and the Radial Electric Field in the DIII-D Tokamak by T.M. Wilks 1 with W.M. Stacey 1 and T.E. Evans 2 1 Georgia Institute of Technology 2 General Atomics Presented

More information

Plasmoid Motion in Helical Plasmas

Plasmoid Motion in Helical Plasmas Plasmoid Motion in Helical Plasmas Ryuichi ISHIZAKI and Noriyoshi NAKAJIMA National Institute for Fusion Science, Toki 509-5292, Japan (Received 12 December 2009 / Accepted 18 May 2010) In order to explain

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

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

History of PARASOL! T. Takizuka! Graduate School of Engineering, Osaka University!! PARASOL was developed at Japan Atomic Energy Agency!

History of PARASOL! T. Takizuka! Graduate School of Engineering, Osaka University!! PARASOL was developed at Japan Atomic Energy Agency! History of PARASOL! T. Takizuka!!! Graduate School of Engineering, Osaka University!! PARASOL was developed at Japan Atomic Energy Agency! OSAKA UNIVERSITY! 20th NEXT Meeting, Kyoto Terrsa, Kyoto, 13-14

More information

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D by J.G. WATKINS, T.E. EVANS, I. JOSEPH, C.J. LASNIER, R.A. MOYER, D.L. RUDAKOV, O. SCHMITZ,

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

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

AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS

AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS AN UPDATE ON DIVERTOR HEAT LOAD ANALYSIS T.K. Mau, A. Grossman, A.R. Raffray UC-San Diego H. McGuinness RPI ARIES-CS Project Meeting June 4-5, 5 University of Wisconsin, Madison OUTLINE Divertor design

More information

Plasma and Fusion Research: Regular Articles Volume 10, (2015)

Plasma and Fusion Research: Regular Articles Volume 10, (2015) Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE

More information

Fusion Nuclear Science - Pathway Assessment

Fusion Nuclear Science - Pathway Assessment Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,

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

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI

More information

Particle Transport Measurements in the LHD Stochastic Magnetic Boundary Plasma using Mach Probes and Ion Sensitive Probe

Particle Transport Measurements in the LHD Stochastic Magnetic Boundary Plasma using Mach Probes and Ion Sensitive Probe Particle Transport Measurements in the LHD Stochastic Magnetic Boundary Plasma using Mach Probes and Ion Sensitive Probe N. Ezumi a*, K. Todoroki a, T. Kobayashi b, K. Sawada c, N. Ohno b, M. Kobayashi

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

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 J Fusion Energ (2010) 29:553 557 DOI 10.1007/s10894-010-9327-6 ORIGINAL RESEARCH Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1 H. Saitoh Z. Yoshida J. Morikawa Y. Yano T. Mizushima

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

The Spherical Tokamak as a Compact Fusion Reactor Concept

The Spherical Tokamak as a Compact Fusion Reactor Concept The Spherical Tokamak as a Compact Fusion Reactor Concept R. Kaita Princeton Plasma Physics Laboratory ENN Symposium on Compact Fusion Technologies April 19 20, 2018 *This work supported by US DOE Contract

More information

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD

Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD 21st IAEA Fusion Energy Conference Chengdu, China, 16-21 October, 2006 IAEA-CN-149/ Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD K. Saito et al. NIFS-851 Oct.

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

3D analysis of impurity transport and radiation for ITER limiter start-up configurations

3D analysis of impurity transport and radiation for ITER limiter start-up configurations 3D analysis of impurity transport and radiation for ITER limiter start-up configurations P2-74 X. Zha a*, F. Sardei a, Y. Feng a, M. Kobayashi b, A. Loarte c, G. Federici c a Max-Planck-Institut für Plasmaphysik,

More information

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Physics of fusion power. Lecture 14: Anomalous transport / ITER Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities

More information

Electron temperature barriers in the RFX-mod experiment

Electron temperature barriers in the RFX-mod experiment Electron temperature barriers in the RFX-mod experiment A. Scaggion Consorzio RFX, Padova, Italy Tuesday 5 th October 2010 ADVANCED PHYSICS LESSONS 27/09/2010 07/10/2010 IPP GARCHING JOINT EUROPEAN RESEARCH

More information

Parallel transport and profile of boundary plasma with a low recycling wall

Parallel transport and profile of boundary plasma with a low recycling wall 1 TH/P4-16 Parallel transport and profile of boundary plasma with a low recycling wall Xian-Zhu Tang 1 and Zehua Guo 1 1 Theoretical Division, Los Alamos National Laboratory, Los Alamos, NM 87545, U.S.A.

More information

Elastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials. Abstract

Elastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials. Abstract Elastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials Naoyoshi Kubota, Kentaro Ochiai, Keitaro Kondo 2 and Takeo Nishitani. :Japan Atomic Energy Research Institute,

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

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU Edge and Internal Transport Barrier Formations in CHS S. Okamura, T. Minami, T. Akiyama, T. Oishi, A. Fujisawa, K. Ida, H. Iguchi, M. Isobe, S. Kado, K. Nagaoka, K. Nakamura, S. Nishimura, K. Matsuoka,

More information

Modelling of plasma edge turbulence with neutrals

Modelling of plasma edge turbulence with neutrals Modelling of plasma edge turbulence with neutrals Ben Dudson 1 1 York Plasma Institute, Department of Physics, University of York, Heslington, York YO1 5DD, UK 7 th IAEA TM on Plasma Instabilities 4-6

More information

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields

Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields Overview of edge modeling efforts for advanced divertor configurations in NSTX-U with magnetic perturbation fields H. Frerichs, O. Schmitz, I. Waters, G. P. Canal, T. E. Evans, Y. Feng and V. Soukhanovskii

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

Hydrogen and Helium Edge-Plasmas

Hydrogen and Helium Edge-Plasmas Hydrogen and Helium Edge-Plasmas Comparison of high and low recycling T.D. Rognlien and M.E. Rensink Lawrence Livermore National Lab Presented at the ALPS/APEX Meeting Argonne National Lab May 8-12, 2

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

Effect of rotational transform and magnetic shear on confinement of stellarators

Effect of rotational transform and magnetic shear on confinement of stellarators Effect of rotational transform and magnetic shear on confinement of stellarators E. Ascasíbar(1), D. López-Bruna(1), F. Castejón(1), V.I. Vargas(1), V. Tribaldos(1), H. Maassberg(2), C.D. Beidler(2) R.

More information

Reduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface )

Reduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface ) Reduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface ) Tsuguhiro WATANABE National Institute for Fusion Science, Toki 509-59, Japan (Received 6 December 011 / Accepted 1 June 01) A new winding

More information

Metal Deposition. Filament Evaporation E-beam Evaporation Sputter Deposition

Metal Deposition. Filament Evaporation E-beam Evaporation Sputter Deposition Metal Deposition Filament Evaporation E-beam Evaporation Sputter Deposition 1 Filament evaporation metals are raised to their melting point by resistive heating under vacuum metal pellets are placed on

More information

Conceptual design of an energy recovering divertor

Conceptual design of an energy recovering divertor Conceptual design of an energy recovering divertor Derek Baver Lodestar Research Corporation Conceptual design of an energy recovering divertor, D. A. Baver, Lodestar Research Corporation. Managing divertor

More information

Plasma-Wall Interaction: A Multi-Scale Problem

Plasma-Wall Interaction: A Multi-Scale Problem Plasma-Wall Interaction: A Multi-Scale Problem R. Schneider 1 Max-Planck-Institut für Plasmaphysik, EURATOM Association, Teilinstitut Greifswald, Wendelsteinstr.1, D-17491 Greifswald, Germany Abstract

More information

ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters

ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters CT/P-7 ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters A. S. Kukushkin ), H. D. Pacher ), G. W. Pacher 3), G. Janeschitz ), D. Coster 5), A. Loarte 6), D. Reiter 7) ) ITER IT, Boltzmannstr.,

More information

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer Alcator C-Mod Particle Transport in the Alcator C-Mod Scrape-off Layer B. LaBombard, R.L. Boivin, B. Carreras, M. Greenwald, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L. Terry, S.J. Zweben,

More information

GA A23066 ENHANCEMENT OF RUNAWAY AVALANCHE BY LOWER HYBRID WAVES

GA A23066 ENHANCEMENT OF RUNAWAY AVALANCHE BY LOWER HYBRID WAVES GA A23066 ENHANCEMENT OF RUNAWAY AVALANCHE BY LOWER HYBRID WAVES by V.S. CHAN, P.B. PARKS, S.C. CHIU, and R.W. HARVEY MARCH 1999 This report was prepared as an account of work sponsored by an agency of

More information

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of

More information

Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak

Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak 1 EX/P3-21 Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak L.H Yao 1), B.B. Feng 1), C.Y. Chen 1), Z.B. Shi 1), B.S. Yuan 1), W,W. Xiao 1), Y. Zhou

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

Deuterium experiment project on LHD and impact of plasma ion species on confinement

Deuterium experiment project on LHD and impact of plasma ion species on confinement Deuterium experiment project on LHD and impact of plasma ion species on confinement M. Osakabe a, Y.Yokoyama a, K.Nagaoka a, H.Takahashi a, R.Seki a, S.Murakami b, M.Yoshinuma a, K.Tanaka a, K.Ida a, K.Nagasaki

More information

Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact

Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact Peter Stangeby 4 September 2003 1. Fig. 1 shows an example of a suitable magnetic configuration for application

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

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany DEPTH PROFILE REONSTRUTION FROM RUTHERFORD BAKSATTERING DATA U. V. TOUSSAINT, K. KRIEGER, R. FISHER, V. DOSE Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D-8574 Garching, Germany

More information

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva CRPP - EPFL SPS Annual Meeting 2014 02.07.2014 CRPP The tokamak

More information

arxiv:cond-mat/ v1 [cond-mat.soft] 24 Apr 2006

arxiv:cond-mat/ v1 [cond-mat.soft] 24 Apr 2006 J. Plasma Physics (2005), vol. *, part *, pp. 1 4. c 2005 Cambridge University Press DOI: 10.1017/S0000000000000000 Printed in the United Kingdom 1 arxiv:cond-mat/0604543v1 [cond-mat.soft] 24 Apr 2006

More information

Assessment of Liquid Metal as the Divertor Surface of a Fusion Power Plant

Assessment of Liquid Metal as the Divertor Surface of a Fusion Power Plant University of California, San Diego UCSD-ENG-079 Assessment of Liquid Metal as the Divertor Surface of a Fusion Power Plant Xiaobing Zhou a,b and Mark S. Tillack a a University of California, San Diego

More information

Imposed Dynamo Current Drive

Imposed Dynamo Current Drive Imposed Dynamo Current Drive by T. R. Jarboe, C. Akcay, C. J. Hansen, A. C. Hossack, G. J. Marklin, K. Morgan, B. A. Nelson, D. A. Sutherland, B. S. Victor University of Washington, Seattle, WA 98195,

More information

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas 1 Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas N. Hayashi 1), T. Takizuka 1), N. Aiba 1), N. Oyama 1), T. Ozeki 1), S. Wiesen 2), V. Parail 3) 1) Japan Atomic Energy Agency,

More information

TH/P4-9. T. Takizuka 1), K. Shimizu 1), N. Hayashi 1), M. Hosokawa 2), M. Yagi 3)

TH/P4-9. T. Takizuka 1), K. Shimizu 1), N. Hayashi 1), M. Hosokawa 2), M. Yagi 3) 1 Two-dimensional Full Particle Simulation of the Flow Patterns in the Scrape-off-layer Plasma for Upper- and Lower- Null Point Divertor Configurations in Tokamaks T. Takizuka 1), K. Shimizu 1), N. Hayashi

More information

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor

Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor IAEA-CRP Plasma-Wall Interaction with Reduced Activation Steel Surfaces in Fusion Devices

More information

Erosion and Confinement of Tungsten in ASDEX Upgrade

Erosion and Confinement of Tungsten in ASDEX Upgrade ASDEX Upgrade Max-Planck-Institut für Plasmaphysik Erosion and Confinement of Tungsten in ASDEX Upgrade R. Dux, T.Pütterich, A. Janzer, and ASDEX Upgrade Team 3rd IAEA-FEC-Conference, 4.., Daejeon, Rep.

More information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

D- 3 He HA tokamak device for experiments and power generations

D- 3 He HA tokamak device for experiments and power generations D- He HA tokamak device for experiments and power generations US-Japan Fusion Power Plant Studies Contents University of Tokyo, Japan January -, 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,

More information

Passive, Active and Feedback Stabilization of Thick, Flowing Liquid Metal Walls

Passive, Active and Feedback Stabilization of Thick, Flowing Liquid Metal Walls 21 st MHD Control Workshop, San Diego, CA, November 7-9, 2016 Passive, Active and Feedback Stabilization of Thick, Flowing Liquid Metal Walls Francesco A. Volpe, S.M.H. (Taha) Mirhoseini Dept. Applied

More information

Implantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten

Implantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten J. Plasma Fusion Res. SERIES, Vol. 10 (2013) Implantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten Yasuhisa Oya 1) *, Makoto Kobayashi 1), Naoaki Yoshida 2),

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

Progress of Confinement Physics Study in Compact Helical System

Progress of Confinement Physics Study in Compact Helical System 1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress

More information

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer PHYSICS OF PLASMAS VOLUME 7, NUMBER 11 NOVEMBER 2000 Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer R. Nachtrieb a) Lutron Electronics Co.,

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

Effect of magnetic reconnection on CT penetration into magnetized plasmas

Effect of magnetic reconnection on CT penetration into magnetized plasmas Earth Planets Space, 53, 547 55, 200 Effect of magnetic reconnection on CT penetration into magnetized plasmas Yoshio Suzuki, Takaya Hayashi 2, and Yasuaki Kishimoto Naka Fusion esearch Establishment,

More information

Characteristics of the H-mode H and Extrapolation to ITER

Characteristics of the H-mode H and Extrapolation to ITER Characteristics of the H-mode H Pedestal and Extrapolation to ITER The H-mode Pedestal Study Group of the International Tokamak Physics Activity presented by T.Osborne 19th IAEA Fusion Energy Conference

More information

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod EX/D- Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod B. LaBombard ), M. Greenwald ), R.L. Boivin ), B..A. Carreras 3), J.W. Hughes ), B. Lipschultz ), D. Mossessian ), C.S. Pitcher

More information

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011 Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor

More information

Runaway electron losses enhanced by resonant magnetic perturbations

Runaway electron losses enhanced by resonant magnetic perturbations Runaway electron losses enhanced by resonant magnetic perturbations G. Papp 1,2, M. Drevlak 3, T. Fülöp 1, P. Helander 3, G. I. Pokol 2 1) Chalmers University of Technology, Göteborg, Sweden 2) Budapest

More information

Turbulence and Transport The Secrets of Magnetic Confinement

Turbulence and Transport The Secrets of Magnetic Confinement Turbulence and Transport The Secrets of Magnetic Confinement Presented by Martin Greenwald MIT Plasma Science & Fusion Center IAP January 2005 FUSION REACTIONS POWER THE STARS AND PRODUCE THE ELEMENTS

More information

Toroidal confinement devices

Toroidal confinement devices Toroidal confinement devices Dr Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th January 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 20) Last time... Power

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

PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT. Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford

PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT. Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford 1 PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford 2 Overview Why do we need plasmas? For fusion, among other things

More information

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod B. LaBombard, M. Umansky, R.L. Boivin, J.A. Goetz, J. Hughes, B. Lipschultz, D. Mossessian, C.S. Pitcher, J.L.Terry,

More information

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Impact of neutral atoms on plasma turbulence in the tokamak edge region Impact of neutral atoms on plasma turbulence in the tokamak edge region C. Wersal P. Ricci, F.D. Halpern, R. Jorge, J. Morales, P. Paruta, F. Riva Theory of Fusion Plasmas Joint Varenna-Lausanne International

More information

Single particle motion and trapped particles

Single particle motion and trapped particles Single particle motion and trapped particles Gyromotion of ions and electrons Drifts in electric fields Inhomogeneous magnetic fields Magnetic and general drift motions Trapped magnetospheric particles

More information

Particle transport results from collisionality scans and perturbative experiments on DIII-D

Particle transport results from collisionality scans and perturbative experiments on DIII-D 1 EX/P3-26 Particle transport results from collisionality scans and perturbative experiments on DIII-D E.J. Doyle 1), L. Zeng 1), G.M. Staebler 2), T.E. Evans 2), T.C. Luce 2), G.R. McKee 3), S. Mordijck

More information

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE T.H. Osborne 1, P.B. Snyder 1, R.J. Groebner 1, A.W. Leonard 1, M.E. Fenstermacher 2, and the DIII-D Group 47 th Annual Meeting

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

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

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