Predicting the Rotation Profile in ITER

Size: px
Start display at page:

Download "Predicting the Rotation Profile in ITER"

Transcription

1 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 Plasma Physics Laboratory 3Oak Ridge National Laboratory Presented at the 27th IAEA Fusion Energy Conference Ghandinagar, Gujarat, India October 22-27, 18!1

2 Rotation Is Important for Determining Stability and Performance in Tokamaks, Affects Predictions of ITER Performance Rotation is important for determining ExB shear, MHD stability, transport of high-z particles All key for determining fusion power output Also key for ITER is affect of pedestal rotation on access to ELM free H-mode via QH-mode 1 and RMP ELM suppression 2 Scaling arguments offer favorable prospect of RMP ELM suppression (krad/s) ω ITER ITER modeling has shown a doubling of fusion power when taking rotation into account due to ExB shear suppression of turbulence 8! [1] Garofalo, Nucl. Fusion 51, 8318 (11) [2] Moyer, Phys. Plasmas 24, 1251 (17)

3 Determining Rotation in ITER Is Difficult Due to the Presence of Many Similar Size Momentum Sources Momentum source in many current tokamaks dominated by NBI ITER s larger moment of inertia means non-nbi sources need to be well understood because NBI torque will not be dominant 8 DIII-D Intrinsic rotation profiles display features caused by many physical effects that may be present in ITER Deuterium V ϕ (km/s) 6 4 H-mode Intrinsic Rotation Examples!

4 Determining Rotation in ITER Is Difficult Due to the Presence of Many Similar Size Momentum Sources Momentum source in many current tokamaks dominated by NBI ITER s larger moment of inertia means non-nbi sources need to be well understood because NBI torque will not be dominant Co-current LCFS feature: -Orbit loss 8 DIII-D -Co/counter current transport -Residual stress -Neutral particles -Fast-ion loss -Field ripple/ntv Deuterium V ϕ (km/s) 6 4 H-mode Intrinsic Rotation Examples!

5 Determining Rotation in ITER Is Difficult Due to the Presence of Many Similar Size Momentum Sources Momentum source in many current tokamaks dominated by NBI ITER s larger moment of inertia means non-nbi sources need to be well understood because NBI torque will not be dominant Co-current LCFS feature: -Orbit loss -Co/counter current Core gradient: caused by many physical effects that transport -Residual stress may be present in ITER -Residual stress -Beam torque -Neutral particles -MHD/NTV Intrinsic rotation profiles display features -Fast-ion loss -Field ripple/ntv Deuterium V ϕ (km/s) DIII-D H-mode Intrinsic Rotation Examples!

6 Determining Rotation in ITER Is Difficult Due to the Presence of Many Similar Size Momentum Sources Momentum source in many current tokamaks dominated by NBI ITER s larger moment of inertia means non-nbi sources need to be well understood because NBI torque will not be dominant Co-current LCFS feature: -Orbit loss -Co/counter current Core gradient: caused by many physical effects that transport -Residual stress may be present in ITER -Residual stress -Beam torque -Neutral particles -MHD/NTV -Fast-ion loss -Field ripple/ntv Intrinsic rotation profiles display features Evaluating 3D field torques requires Deuterium V ϕ (km/s) DIII-D!6 rotation profile, subject of future work after initial condition is laid down H-mode Intrinsic Rotation Examples

7 Outline DIII-D investigation of LCFS co-current feature in intrinsic rotation plasmas Fast-ion effects on scaling Neutral particle effects on intrinsic momentum transport ITER prediction based on co-current feature and core NBI Implications for RMP ELM suppression and conclusion!7

8 Scaling of Intrinsic Co-current Rotation Feature Is Key for Predicting ITER Rotation Boundary Condition Low operating regime of ITER cannot be achieved in current tokamaks Robust co-current rotation near LCFS is a boundary condition, investigated by: empirical scaling 1,2, dimensionless parameters scans 3, reduced physics models 4,5 DIII-D Pedestal Top (krad/s) Counter-Ip QH-mode 25 5 Low Torque: Intrinsic, QH, High Co-Ip Torque IBS, etc. ITER [2] [5] [3] [4]!8 Similar predictions: 4-1 krad/s, but discrepancy exists between databases (M~ 1 ) and dimensionless parameter scan (M~ -1 ) Databases vary more widely, dimensionless parameter scan varies alone BUT had significant fast-ion population Dimensionless parameter scan (intrinsic torque) results need to be verified in intrinsic rotation conditions [1] Rice, Nucl. Fusion 47, 1618 (7) [2] degrassie, Phys. Plasmas 23, 8251 (16) [3] Chrystal, Phys. Plasmas 24, 4251 (17) [4] Rice, Nucl. Fusion 57, 1164 (17) [5] Ashourvan, Phys. Plasmas 25, (18)

9 Measured Scaling of Intrinsic Rotation in ECH H-modes Has Smaller Discrepancy and Increases Confidence in ITER Prediction No significant scaling of intrinsic Mach number measured with in dimensionless parameter scan, defying both possible expectations Fundamentally different from observing variation with Mach number in a database Expectation was M~ -1±.9, new result not quite within error bar, perhaps edge plasma factors or Zeff changes are the cause of variation in results Other dimensionless parameters matched Adjust previous intrinsic torque based ITER prediction of ~1 krad/s: result is 3 krad/s, very near the previous Mach Number (=.8).1 1 predictions (4-1 krad/s) 1 1 1!9

10 Measured Scaling of Intrinsic Rotation in ECH H-modes Has Smaller Discrepancy and Increases Confidence in ITER Prediction No significant scaling of intrinsic Mach number measured with in dimensionless parameter scan, defying both possible expectations Fundamentally different from observing variation with Mach number in a database Expectation was M~ -1±.9, new result not quite within error bar, perhaps edge plasma factors or Zeff changes are the cause of variation in results Other dimensionless parameters matched Adjust previous intrinsic torque based ITER prediction of ~1 krad/s: result is 3 krad/s, very near the previous Mach Number (=.8) predictions (4-1 krad/s) 1 1 1!1

11 Measured Scaling of Intrinsic Rotation in ECH H-modes Has Smaller Discrepancy and Increases Confidence in ITER Prediction No significant scaling of intrinsic Mach number measured with in dimensionless parameter scan, defying both possible expectations Fundamentally different from observing variation with Mach number in a database Expectation was M~ -1±.9, new result not quite within error bar, perhaps edge plasma factors or Zeff changes are the cause of variation in results Other dimensionless parameters matched Adjust previous intrinsic torque based ITER prediction of ~1 krad/s: result is 3 krad/s, very near the previous Intrinsic rotation predictions are consistent enough for ITER prediction Mach Number (=.8) Are there boundary.1 effects 1 influencing attempts to measure the scaling? -1 predictions (4-1 krad/s) 1 1 1!11

12 <latexit sha1_base64="rnf1usclqy25ler7u6uhqgc2ljo=">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</latexit> <latexit sha1_base64="rnf1usclqy25ler7u6uhqgc2ljo=">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</latexit> <latexit sha1_base64="rnf1usclqy25ler7u6uhqgc2ljo=">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</latexit> <latexit sha1_base64="rnf1usclqy25ler7u6uhqgc2ljo=">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</latexit> Momentum Transport from Neutrals in Pedestal Is a Hidden Variable that May Affect Current Tokamaks Much More than ITER Neutral particles in pedestal are a hidden variable for most current experiments because they are rarely measured, may be corrupting ITER predictions Experiment in DIII-D made proxy investigation: change neutrals particles significantly through SOL conditions, observe intrinsic rotation M ped f nnuet n e, n neut arn neut Basic idea: neutrals affect rotation via charge exchange and ionization, effect is much reduced in ITER due to decreased neutral penetration into plasma ASDEX-U Inward Outward Integrated Momentum Flux!12 Omotani, Nucl. Fusion 57, 6648 (17)

13 Proxy Investigation Uses Divertor Closure to Change Neutral Trapping, Effect Shown by SOLPS Modeling 1.5 Closed Open Mirrored Open.5 DIII-D upper divertor can be made significantly more closed than lower divertor Create similar intrinsic rotation discharges (ECH H-modes) in 1..5 Gas Puff n e (1 /m 3 ) (b)!13 these two configurations Measure main-ion rotation from core to LCFS with main-ion CER z (m) B B B B Gas Puff (a) R (m) T i (kev) V ϕ (km/s) 6 4 (c) (d)

14 Proxy Investigation Uses Divertor Closure to Change Neutral Trapping, Effect Shown by SOLPS Modeling DIII-D upper divertor can be made significantly more 1e18 closed than lower divertor Create similar intrinsic rotation discharges (ECH H-modes) in these two configurations Measure main-ion rotation from core to LCFS with main-ion CER SOLPS modeling shows neutrals in open configuration more easily reach and penetrate LCFS, increasing z (m) Closed Open 1e17 1e16 1e15 1e14 1e13 Hydrogenic Atom Density (m -3 ) neutral density R (m) R (m)!14

15 Proxy Investigation Uses Divertor Closure to Change Neutral Trapping, Effect Shown by SOLPS Modeling DIII-D upper divertor can be made significantly more closed than lower divertor Create similar intrinsic rotation discharges (ECH H-modes) in these two configurations Measure main-ion rotation from core to LCFS with main-ion CER SOLPS modeling shows neutrals in open configuration more easily reach and penetrate LCFS, increasing z (m) Closed Open 1e24 1e23 1e22 1e21 1e 1e19 Recycling Particle Source (s -1 m -3 ) neutral density and particle source in pedestal region R (m) R (m)!15

16 Across Database of Open/Closed Plasmas, Pedestal Top Rotation Constant While Midplane Neutral Emission Changes Pedestal top intrinsic rotation (carbon) gives basic indication of changes in edge/ pedestal rotation For the parameters varied in these discharges, main trend is expected to be with Ti LFS Midplane D α (1 14 ph/sr/s/cm 2 ) Closed Open R-R sep ω (krad/s) Closed Open T (kev) i Neutrals appear to have little effect because rotation data sets essentially the same while midplane neutral emission clearly increase for open cases!16

17 DIII-D Intrinsic Rotation in Open/Closed Divertors Do Not Change Significantly with Changes in Pedestal Fueling Divertor closure affects amount of neutral fueling near LCFS as seen by SOLPS modeling and density profile results, even when other parameters are the same Density profiles changes are significant given the same Ip, β, etc. Main-ion intrinsic rotation is largely unaffected compared to normal experimental variation Edge neutrals have no significant effect on intrinsic rotation z (m) Closed Open Mirrored Open B B B B Gas Puff Gas Puff (a) R (m) n e (1 /m 3 ) T i (kev) V ϕ (km/s) (b) (c) (d) s s !17

18 DIII-D Intrinsic Rotation in Open/Closed Divertors Do Not Change Significantly with Changes in Pedestal Fueling Divertor closure affects amount of neutral fueling near LCFS as seen by SOLPS modeling and density profile results, even when other parameters are the same Density profiles changes are significant given the same Ip, β, etc. Main-ion intrinsic rotation is largely unaffected compared to normal experimental variation Edge neutrals have no significant effect on intrinsic rotation z (m) Closed Open Mirrored Open B B B B Gas Puff Intrinsic rotation predictions are consistent enough for ITER prediction No significant contamination of Gas Puff (a) R (m) n e (1 /m 3 ) T i (kev) intrinsic rotation experiment from neutral particles With increased confidence in boundary condition for ITER, we proceed with prediction V ϕ (km/s) (b) (c) (d) s s !18

19 Initial ITER Modeling Done Without Rotation Is Baseline for Evaluating Effect of Rotation Predictive TRANSP determines sources ITER baseline scenario (15 MA), EPED pedestal 35 N m and 33 MW NBI, 1 MW ICRF, 6 MW ECCD (at q=3/2, 2 surfaces) Core solution with TGYRO with TGLF+NEO transport Next, use edge rotation boundary condition and also solve transport in momentum channel with NBI TGLF momentum transport worked well in DIII-D 1 at lower collisionality and q ω (krad/s) (kev) Te Rotation Set Uniformly to (kev) ne (1 19 /m 3 ) Ti ! [1] Chrystal, Phys. Plasmas 24, (17)

20 Core Rotation Shear in ITER Is Predicted to Significantly Improve Fusion Performance! Rotation boundary condition of 4 krad/s is used, relatively modest value within 3-1 krad/s range of predictions Core rotation determined from TGLF momentum flux and 35 N m source Deuterium Mach numbers are modest: Mcore~.2, Mped~4 Significant for heavy impurity transport Qfus approximately doubles due to density peaking and increased temperatures caused by rotation shear Grains of salt: Q values are idiosyncratic to the impurities and radiated power, there are nonlinearities and initial condition is important, residual stress not included in core (see Grierson EX/P6-3 this afternoon) (krad/s) ω (kev) Te No Rotation With Rotation (kev) ne (1 19 /m 3 ) Ti

21 Performance Improvement From Rotation Shear Is Due to Reduction of Low-k Turbulence and Increase in Density Peaking In simulation with rotation, low-k turbulence => outward particle flux, intermediate-k => inward particle flux Without ExB shear, total flux would be outward, force TGYRO to flatten density profile ExB shear suppresses low-k turbulence more strongly, so flux Γ/ΓGB V E B.25 V E B.5 V E B.75 V E B 1. V E B is balanced even with a peaked density profile k θ V Increased Te due to reduced transport further destabilizes intermediate-k turbulence, increasing inward particle flux, as seen in similar studies 1 [1] Grierson, Phys. Plasmas 25, 2259 (18)!21

22 Performance Improvement From Rotation Shear Is Due to Reduction of Low-k Turbulence and Increase in Density Peaking In simulation with rotation, low-k turbulence => outward particle flux, 6 intermediate-k => inward particle flux Without ExB shear, total flux would be outward, force TGYRO to flatten density profile Γ/ΓGB 4 2 Total Flux: +45 V E B.25 V E B.5 V E B.75 V E B 1. V E B ExB shear suppresses low-k turbulence more strongly, so flux is balanced even with a peaked density profile k θ V Increased Te due to reduced transport further destabilizes intermediate-k turbulence, increasing inward particle flux, as seen in similar studies 1 [1] Grierson, Phys. Plasmas 25, 2259 (18)!22

23 Performance Improvement From Rotation Shear Is Due to Reduction of Low-k Turbulence and Increase in Density Peaking In simulation with rotation, low-k turbulence => outward particle flux, intermediate-k => inward particle flux Without ExB shear, total flux would be outward, force TGYRO to flatten density profile ExB shear suppresses low-k turbulence more strongly, so flux Γ/ΓGB Total Flux: +45 V E B.25 V E B.5 V E B.75 V E B 1. V E B Total Flux: -1 is balanced even with a peaked density profile k θ V Increased Te due to reduced transport further destabilizes intermediate-k turbulence, increasing inward particle flux, as seen in similar studies 1 [1] Grierson, Phys. Plasmas 25, 2259 (18)!23

24 <latexit sha1_base64="mpqoisvjo1xji2gn8mvmexufyn8=">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</latexit> <latexit sha1_base64="mpqoisvjo1xji2gn8mvmexufyn8=">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</latexit> <latexit sha1_base64="mpqoisvjo1xji2gn8mvmexufyn8=">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</latexit> <latexit sha1_base64="mpqoisvjo1xji2gn8mvmexufyn8=">aaacynicbvfnaxsxfnrumzz128rpjs1b1cmklibdxnplikquenrm7yraxryv33qftdpfepuylpsnc8upl/6qyh+ffhrammy8qxqjpntkurtdbugtp1vpnm+/6lx89xpnt7v3zuskykocykix9iobh1ozhjiijvelrcgtjzfj4uvsv7xg61rhflbd4ishuvgpkkbemnbrqzftrtrqo6o1cpedzunajnrtxzeonfrwtzlvp4oixzmszt4qgzc4bltmioubmmce1ha/+cerwpcnmjbo4p22mt+xpv1n+eb8kihdgsnptxcdryvwxytekb7bod/t3ohziascduknzo3jqkrja5au1nh2rowwblmaoy49nzcjmzsrilr+3isznhbwhn8pd5nnja7v+ejn1zu6x56s/f/3rii9mukuaasci1cx5rwmlpbl33zmbiosdeegltkv5xldhxb5h+l4uih678mixojmppl56z982dwyzt+wdo2ix+8zo2hfwzmm2e9gk9gjdom/ysfcc/fxo2gwyeyzewgp/gjoa7ep</latexit> <latexit sha1_base64="fzoicufux2slrxu9ocyyvdv672k=">aaaccxicbzdlssnafiyn9vbrlerszwarujcsdkplggguk9glncfmpqftekyzeyeelp146u4cagiw9/anw/jtm1cw38y+pjpozw5fyg4u9pxvq3s2vrg5lz5u7kzu7d/yb8edvsssgptmvbe9kkiglmy2pppdjhguqhh244uz7vuw8gfuvie5j8cmyitmquaknfdi45g2yepxksmccsjdemcjb7gmq4gkmtccuonvnlrwkbgfvvkgv2f/eikfpblgmncjvdx2h/zxizsihacvlfqhcj2qefymxiud5+fyskt4zzgape2lerphc/t2rkiplapnztwc3xzuz/tx6qh1d+zmkraojpytew5vgnebylhjajvppmakgsmb9ioiasug3cq5gq3owtv6htqlug7xrv5krrxmdofnjlxizrofrvqg1hij7rk3qznqwx6936wlswrglmgp2r9fkdituanw==</latexit> <latexit sha1_base64="fzoicufux2slrxu9ocyyvdv672k=">aaaccxicbzdlssnafiyn9vbrlerszwarujcsdkplggguk9glncfmpqftekyzeyeelp146u4cagiw9/anw/jtm1cw38y+pjpozw5fyg4u9pxvq3s2vrg5lz5u7kzu7d/yb8edvsssgptmvbe9kkiglmy2pppdjhguqhh244uz7vuw8gfuvie5j8cmyitmquaknfdi45g2yepxksmccsjdemcjb7gmq4gkmtccuonvnlrwkbgfvvkgv2f/eikfpblgmncjvdx2h/zxizsihacvlfqhcj2qefymxiud5+fyskt4zzgape2lerphc/t2rkiplapnztwc3xzuz/tx6qh1d+zmkraojpytew5vgnebylhjajvppmakgsmb9ioiasug3cq5gq3owtv6htqlug7xrv5krrxmdofnjlxizrofrvqg1hij7rk3qznqwx6936wlswrglmgp2r9fkdituanw==</latexit> <latexit sha1_base64="fzoicufux2slrxu9ocyyvdv672k=">aaaccxicbzdlssnafiyn9vbrlerszwarujcsdkplggguk9glncfmpqftekyzeyeelp146u4cagiw9/anw/jtm1cw38y+pjpozw5fyg4u9pxvq3s2vrg5lz5u7kzu7d/yb8edvsssgptmvbe9kkiglmy2pppdjhguqhh244uz7vuw8gfuvie5j8cmyitmquaknfdi45g2yepxksmccsjdemcjb7gmq4gkmtccuonvnlrwkbgfvvkgv2f/eikfpblgmncjvdx2h/zxizsihacvlfqhcj2qefymxiud5+fyskt4zzgape2lerphc/t2rkiplapnztwc3xzuz/tx6qh1d+zmkraojpytew5vgnebylhjajvppmakgsmb9ioiasug3cq5gq3owtv6htqlug7xrv5krrxmdofnjlxizrofrvqg1hij7rk3qznqwx6936wlswrglmgp2r9fkdituanw==</latexit> <latexit sha1_base64="fzoicufux2slrxu9ocyyvdv672k=">aaaccxicbzdlssnafiyn9vbrlerszwarujcsdkplggguk9glncfmpqftekyzeyeelp146u4cagiw9/anw/jtm1cw38y+pjpozw5fyg4u9pxvq3s2vrg5lz5u7kzu7d/yb8edvsssgptmvbe9kkiglmy2pppdjhguqhh244uz7vuw8gfuvie5j8cmyitmquaknfdi45g2yepxksmccsjdemcjb7gmq4gkmtccuonvnlrwkbgfvvkgv2f/eikfpblgmncjvdx2h/zxizsihacvlfqhcj2qefymxiud5+fyskt4zzgape2lerphc/t2rkiplapnztwc3xzuz/tx6qh1d+zmkraojpytew5vgnebylhjajvppmakgsmb9ioiasug3cq5gq3owtv6htqlug7xrv5krrxmdofnjlxizrofrvqg1hij7rk3qznqwx6936wlswrglmgp2r9fkdituanw==</latexit> Simple Scaling Relation Offers Favorable Prospect of Achieving RMP ELM Suppression in ITER Low rotation RMP ELM suppression is hard to achieve, hypothesized to be a result of inward movement of Er= 1!?,e also hypothesized 2, movement is typically correlated with Er= movement Relation for Er=, divergence free flow: V = k( )B +!( )R ˆ' ) ITER needs less rotation because of: Larger gradient scale length (larger size) Larger poloidal field rp nze =!RB Edge C 6+ Rotation (km/s) ELMing Suppressed t (s) 1 #slices (a.u.) 5-9 krad/s of pedestal top rotation is lower limit for suppression in DIII-D, translates to.2-.5 krad/s for ITER, <3 krad/s prediction Effect of RMP field on rotation prediction still needed to fully answer this question!24 [1] Paz-Soldan, Nucl. Fusion (in review) [2] Moyer, Phys. Plasmas 24, 1251 (17)

25 Conclusions Edge rotation prediction for ITER is made with increased confidence: 3-1 krad/s Fast-ion effect on results is relatively small while reducing discrepancies between predictions Neutral particle induced transport found to be small ITER, though large and with relatively small NBI torque, will still have significant enough ExB to decrease turbulent transport Prospect of RMP ELM suppression is good These rotation predictions must now be ω (krad/s) (kev) Te No Rotation With Rotation (kev) ne (1 19 /m 3 ) Ti !25 integrated with effects from intrinsic and applied 3D fields

26 BACKUP SLIDES!26

27 Intrinsic Rotation Does Not Vary with Gross Change in Neutrals Associated with Divertor Detachment!27 Detached divertors have higher neutral particle pressures These conditions were created with significant main-chamber gas fueling in order to increase plasma density These changes are expected to increase neutral densities inside the confined plasma, but this causes no significant change to the intrinsic rotation So long as Ti does not begin to drop This result supports conclusions drawn from open/closed divertor comparisons J sat (A/cm 2 ) Neut. Press. (mtorr) T i (kev) ω (krad/s) (a) (b) (c) (d) Time (s) NBI Blips Detachment Onset

28 Dimensionless Parameter Scan Executed in ECH H-modes in DIII-D Achieved Desired Variation in was decreased by ~3%, the expected range achievable in DIII-D with limitations on field β variation due to ECH absorption 6 2 Change in Zeff is likely due to a change in carbon source due to a hard to control change in boundary conditions This is a potential confounding factor for the results, though previous work has not seen causal changes in intrinsic rotation with Zeff (a) (c) ν (b) (d) Z eff !28

29 <latexit sha1_base64="nqck9i3sz5oqrrizuvq8l1inh7e=">aaach3icbvbnsynbeo3x2/ivxy9egqpgxtdjqbisovgmyprmrnctacmaezpgbprhghip9nl/huvhprl8zz/y+fj4nedgsd7vvtvizillfn+juznztfwfxarqysrq1vvh/8vlzpbgq2rapscxubrsu1nkmswtvmicsrwpvo/vfiv3lay2wqr6jisj1at8tyciandaqho2fx2kxbyalqypfd2iaoqw2rat4ylpoobydhmmap+owvtkh9jnjpvgt+3r+dfyxblntyfi1o9txspijpujnqygr8dnql2bicowdsphbzedcqw9bjmpilbl8x8dvuuulo9t4oth6vvjpirc2syhumqh372ruj33mtnoljdil1lhnqmvku54ptykdh8a4kegvjoawt3krr9cqoqirbgqgs8vfyxxb/xarwcxb7xts2kcs2ylbbm9frajdsrowym1mwb/2cn7zi/ex+/j++f9n7toenoztfyb3van+f+i5g==</latexit> <latexit sha1_base64="nqck9i3sz5oqrrizuvq8l1inh7e=">aaach3icbvbnsynbeo3x2/ivxy9egqpgxtdjqbisovgmyprmrnctacmaezpgbprhghip9nl/huvhprl8zz/y+fj4nedgsd7vvtvizillfn+juznztfwfxarqysrq1vvh/8vlzpbgq2rapscxubrsu1nkmswtvmicsrwpvo/vfiv3lay2wqr6jisj1at8tyciandaqho2fx2kxbyalqypfd2iaoqw2rat4ylpoobydhmmap+owvtkh9jnjpvgt+3r+dfyxblntyfi1o9txspijpujnqygr8dnql2bicowdsphbzedcqw9bjmpilbl8x8dvuuulo9t4oth6vvjpirc2syhumqh372ruj33mtnoljdil1lhnqmvku54ptykdh8a4kegvjoawt3krr9cqoqirbgqgs8vfyxxb/xarwcxb7xts2kcs2ylbbm9frajdsrowym1mwb/2cn7zi/ex+/j++f9n7toenoztfyb3van+f+i5g==</latexit> <latexit sha1_base64="nqck9i3sz5oqrrizuvq8l1inh7e=">aaach3icbvbnsynbeo3x2/ivxy9egqpgxtdjqbisovgmyprmrnctacmaezpgbprhghip9nl/huvhprl8zz/y+fj4nedgsd7vvtvizillfn+juznztfwfxarqysrq1vvh/8vlzpbgq2rapscxubrsu1nkmswtvmicsrwpvo/vfiv3lay2wqr6jisj1at8tyciandaqho2fx2kxbyalqypfd2iaoqw2rat4ylpoobydhmmap+owvtkh9jnjpvgt+3r+dfyxblntyfi1o9txspijpujnqygr8dnql2bicowdsphbzedcqw9bjmpilbl8x8dvuuulo9t4oth6vvjpirc2syhumqh372ruj33mtnoljdil1lhnqmvku54ptykdh8a4kegvjoawt3krr9cqoqirbgqgs8vfyxxb/xarwcxb7xts2kcs2ylbbm9frajdsrowym1mwb/2cn7zi/ex+/j++f9n7toenoztfyb3van+f+i5g==</latexit> <latexit sha1_base64="nqck9i3sz5oqrrizuvq8l1inh7e=">aaach3icbvbnsynbeo3x2/ivxy9egqpgxtdjqbisovgmyprmrnctacmaezpgbprhghip9nl/huvhprl8zz/y+fj4nedgsd7vvtvizillfn+juznztfwfxarqysrq1vvh/8vlzpbgq2rapscxubrsu1nkmswtvmicsrwpvo/vfiv3lay2wqr6jisj1at8tyciandaqho2fx2kxbyalqypfd2iaoqw2rat4ylpoobydhmmap+owvtkh9jnjpvgt+3r+dfyxblntyfi1o9txspijpujnqygr8dnql2bicowdsphbzedcqw9bjmpilbl8x8dvuuulo9t4oth6vvjpirc2syhumqh372ruj33mtnoljdil1lhnqmvku54ptykdh8a4kegvjoawt3krr9cqoqirbgqgs8vfyxxb/xarwcxb7xts2kcs2ylbbm9frajdsrowym1mwb/2cn7zi/ex+/j++f9n7toenoztfyb3van+f+i5g==</latexit> <latexit sha1_base64="av2c12d8xrxaxgnkllhtwod2er=">aaacknicbvdlsgmxfm3ud31vxbojvsehlhk3uheuedwifwwrdoqqydzaewyjhlhgpo9bvwvny6u4typmav1hogco459ya5jw48z1+5hynjqemz2rji/slixfpzrwuzkgo1krlunyhrwjmammggw2igmqhhbyprv4jqdqmklxbbiewjg5e6znkdfwckqnm37edmjjpk3gav/6kgjgptje91vhbrv32z631ukul7n973e3ncphuxozlaquxv3cdxovbepoxgqqenfjyrnyxcgcqj13mt8qjmoxy6bx9vencajfcqdnsqwlqrxy4ag9vwsxcbanseqyp1z8toym1zulqdsbedprfbyd+5zvtz5q5uwkqqfbvx5qpxwbiqe54ygpoiznlhcqmprph2icdu23ainwfu78jiph1q8t+jdhzrpzkdxzkj1tig2kycoqm6qfvuqxq9omfit6cj+ff6tvvx6fzzszhn7b+fgejtamqw==</latexit> <latexit sha1_base64="av2c12d8xrxaxgnkllhtwod2er=">aaacknicbvdlsgmxfm3ud31vxbojvsehlhk3uheuedwifwwrdoqqydzaewyjhlhgpo9bvwvny6u4typmav1hogco459ya5jw48z1+5hynjqemz2rji/slixfpzrwuzkgo1krlunyhrwjmammggw2igmqhhbyprv4jqdqmklxbbiewjg5e6znkdfwckqnm37edmjjpk3gav/6kgjgptje91vhbrv32z631ukul7n973e3ncphuxozlaquxv3cdxovbepoxgqqenfjyrnyxcgcqj13mt8qjmoxy6bx9vencajfcqdnsqwlqrxy4ag9vwsxcbanseqyp1z8toym1zulqdsbedprfbyd+5zvtz5q5uwkqqfbvx5qpxwbiqe54ygpoiznlhcqmprph2icdu23ainwfu78jiph1q8t+jdhzrpzkdxzkj1tig2kycoqm6qfvuqxq9omfit6cj+ff6tvvx6fzzszhn7b+fgejtamqw==</latexit> <latexit sha1_base64="av2c12d8xrxaxgnkllhtwod2er=">aaacknicbvdlsgmxfm3ud31vxbojvsehlhk3uheuedwifwwrdoqqydzaewyjhlhgpo9bvwvny6u4typmav1hogco459ya5jw48z1+5hynjqemz2rji/slixfpzrwuzkgo1krlunyhrwjmammggw2igmqhhbyprv4jqdqmklxbbiewjg5e6znkdfwckqnm37edmjjpk3gav/6kgjgptje91vhbrv32z631ukul7n973e3ncphuxozlaquxv3cdxovbepoxgqqenfjyrnyxcgcqj13mt8qjmoxy6bx9vencajfcqdnsqwlqrxy4ag9vwsxcbanseqyp1z8toym1zulqdsbedprfbyd+5zvtz5q5uwkqqfbvx5qpxwbiqe54ygpoiznlhcqmprph2icdu23ainwfu78jiph1q8t+jdhzrpzkdxzkj1tig2kycoqm6qfvuqxq9omfit6cj+ff6tvvx6fzzszhn7b+fgejtamqw==</latexit> <latexit sha1_base64="av2c12d8xrxaxgnkllhtwod2er=">aaacknicbvdlsgmxfm3ud31vxbojvsehlhk3uheuedwifwwrdoqqydzaewyjhlhgpo9bvwvny6u4typmav1hogco459ya5jw48z1+5hynjqemz2rji/slixfpzrwuzkgo1krlunyhrwjmammggw2igmqhhbyprv4jqdqmklxbbiewjg5e6znkdfwckqnm37edmjjpk3gav/6kgjgptje91vhbrv32z631ukul7n973e3ncphuxozlaquxv3cdxovbepoxgqqenfjyrnyxcgcqj13mt8qjmoxy6bx9vencajfcqdnsqwlqrxy4ag9vwsxcbanseqyp1z8toym1zulqdsbedprfbyd+5zvtz5q5uwkqqfbvx5qpxwbiqe54ygpoiznlhcqmprph2icdu23ainwfu78jiph1q8t+jdhzrpzkdxzkj1tig2kycoqm6qfvuqxq9omfit6cj+ff6tvvx6fzzszhn7b+fgejtamqw==</latexit> <latexit sha1_base64="hs6hdyt42dquyh9kjyud3h2nmqg=">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</latexit> <latexit sha1_base64="hs6hdyt42dquyh9kjyud3h2nmqg=">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</latexit> <latexit sha1_base64="hs6hdyt42dquyh9kjyud3h2nmqg=">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</latexit> <latexit sha1_base64="hs6hdyt42dquyh9kjyud3h2nmqg=">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</latexit> <latexit sha1_base64="sacc3ix45qof2bhp89/macalqwy=">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</latexit> <latexit sha1_base64="sacc3ix45qof2bhp89/macalqwy=">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</latexit> <latexit sha1_base64="sacc3ix45qof2bhp89/macalqwy=">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</latexit> <latexit sha1_base64="sacc3ix45qof2bhp89/macalqwy=">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</latexit> Simple Scaling Relation Offers Favorable Prospect of Achieving RMP ELM Suppression in ITER RMP ELM Suppression at low rotation is thought to be difficult due to the movement of the Er= crossing to lower minor radius Using the divergence-free form of velocity: V = k( )B +!( )R ˆ' a relation for Er= can be made into scaling requirement for Mach! number rp nze =!RB ) rp nze =!RB M = q( 1 T + 1 n ) R p T/m/B/a R p T/m/B/a ω is the toroidal rotation frequency if poloidal rotation is zero, B approximated as toroidal field to make factor of q We will assume the normalized gradient scale lengths will NOT change in ITER 5-9 krad/s of pedestal top rotation is current lower limit for RMP ELM suppression in DIII-D, yields a lower limit of.2-.5 krad/s for ITER, <3 krad/s prediction Effect of RMP ELM suppression on rotation prediction still needed to fully answer this question!29

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling by B.A. Grierson1, C. Chrystal2, W.X. Wang1, J.A. Boedo3, J.S. degrassie2, W.M. Solomon2,

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

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

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas

First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas 1 PD/1-1 First Observation of ELM Suppression by Magnetic Perturbations in ASDEX Upgrade and Comparison to DIII-D Matched-Shape Plasmas R. Nazikian 1, W. Suttrop 2, A. Kirk 3, M. Cavedon 2, T.E. Evans

More information

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu

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

DIII-D RESEARCH TOWARDS ESTABLISHING THE SCIENTIFIC BASIS FOR FUTURE FUSION REACTORS

DIII-D RESEARCH TOWARDS ESTABLISHING THE SCIENTIFIC BASIS FOR FUTURE FUSION REACTORS IAEA-CN-258/OV1-4 DIII-D RESEARCH TOWARDS ESTABLISHING THE SCIENTIFIC BASIS FOR FUTURE FUSION REACTORS C.C. Petty for the DIII-D team General Atomics San Diego, California, USA Email: petty@fusion.gat.com

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height

Influence of Beta, Shape and Rotation on the H-mode Pedestal Height Influence of Beta, Shape and Rotation on the H-mode Pedestal Height by A.W. Leonard with R.J. Groebner, T.H. Osborne, and P.B. Snyder Presented at Forty-Ninth APS Meeting of the Division of Plasma Physics

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

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

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012 Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty

More information

High fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing

High fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing High fusion performance at high T i /T e in JET-ILW baseline plasmas with high NBI heating power and low gas puffing Hyun-Tae Kim, A.C.C. Sips, C. D. Challis, F. Rimini, L. Garzotti, E. Lerche, L. Frassinetti,

More information

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas

Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H- and QH-mode Plasmas EX/P5-35 L. Schmitz 1), A.E. White 1), G. Wang 1), J.C. DeBoo 2),

More information

Progress in characterization of the H-mode pedestal

Progress in characterization of the H-mode pedestal Journal of Physics: Conference Series Progress in characterization of the H-mode pedestal To cite this article: A W Leonard 2008 J. Phys.: Conf. Ser. 123 012001 View the article online for updates and

More information

Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges

Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges Dependences of Critical Rotational Shear in DIII-D QH-mode Discharges by T.M. Wilks 1 with K.H. Burrell 2, Xi. Chen 2, A. Garofalo 2, R.J. Groebner 2, P. Diamond 3, Z. Guo 3, and J.W. Hughes 1 1 MIT 2

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

Correlations of ELM frequency with pedestal plasma characteristics

Correlations of ELM frequency with pedestal plasma characteristics cpp header will be provided by the publisher Correlations of ELM frequency with pedestal plasma characteristics G. Kamberov 1 and L. Popova 2 1 Stevens Institute of Technology, Hoboken NJ, USA 2 Institute

More information

Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas

Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas Low-collisionality density-peaking in GYRO simulations of C-Mod plasmas D. R. Mikkelsen, M. Bitter, K. Hill, PPPL M. Greenwald, J.W. Hughes, J. Rice, MIT J. Candy, R. Waltz, General Atomics APS Division

More information

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations

Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER

More information

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport*

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* E. Marmar, B. Lipschultz, A. Dominguez, M. Greenwald, N. Howard, A. Hubbard, J. Hughes, B. LaBombard, R. McDermott, M. Reinke,

More information

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod 1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.

More information

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

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

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

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS by T.C. LUCE, G.L. JACKSON, T.W. PETRIE, R.I. PINSKER, W.M. SOLOMON, F. TURCO, N. COMMAUX, J.R. FERRON, A.M. GAROFALO,

More information

Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence

Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence 1 Reduced Electron Thermal Transport in Low Collisionality H-mode Plasmas in DIII-D and the Importance of Small-scale Turbulence L. Schmitz, 1 C. Holland, 2 T.L. Rhodes, 1 G. Wang, 1 L. Zeng, 1 A.E. White,

More information

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

Edge Momentum Transport by Neutrals

Edge Momentum Transport by Neutrals 1 TH/P3-18 Edge Momentum Transport by Neutrals J.T. Omotani 1, S.L. Newton 1,2, I. Pusztai 1 and T. Fülöp 1 1 Department of Physics, Chalmers University of Technology, 41296 Gothenburg, Sweden 2 CCFE,

More information

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly

More information

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J.

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J. GA A27822 THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J. GROEBNER JUNE 2014 DISCLAIMER This report was prepared as an account of work

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

Edge Impurity Dynamics During an ELM Cycle in DIII D

Edge Impurity Dynamics During an ELM Cycle in DIII D Edge Impurity Dynamics During an ELM Cycle in by M.R. Wade 1 in collaboration with K.H. Burrell, A.W. Leonard, T.H. Osborne, P.B. Snyder, J.T. Hogan, 1 and D. Coster 3 1 Oak Ridge National Laboratory General

More information

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.

More information

C-Mod Transport Program

C-Mod Transport Program C-Mod Transport Program PAC 2006 Presented by Martin Greenwald MIT Plasma Science & Fusion Center 1/26/2006 Introduction Programmatic Focus Transport is a broad topic so where do we focus? Where C-Mod

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

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139 Alcator C-Mod Double Transport Barrier Plasmas in Alcator C-Mod J.E. Rice for the C-Mod Group MIT PSFC, Cambridge, MA 139 IAEA Lyon, Oct. 17, Outline Double Barrier Plasma Profiles and Modeling Conditions

More information

Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod

Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod Investigation of Intrinsic Rotation Dependencies in Alcator C-Mod D. Kwak, A. E. White, J. E. Rice, N. T. Howard, C. Gao, M. L. Reinke, M. Greenwald, C. Angioni, R. M. McDermott, and the C-Mod and ASDEX

More information

On tokamak plasma rotation without the neutral beam torque

On tokamak plasma rotation without the neutral beam torque On tokamak plasma rotation without the neutral beam torque Antti Salmi (VTT) With contributions from T. Tala (VTT), C. Fenzi (CEA) and O. Asunta (Aalto) 2 Motivation: Toroidal rotation Plasma rotation

More information

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod J.W. Hughes, B. LaBombard, M. Greenwald, A. Hubbard, B. Lipschultz, K. Marr, R. McDermott, M. Reinke, J.L. Terry

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

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

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER by A.M. GAROFALO, K.H. BURRELL, M.J. LANCTOT, H. REIMERDES, W.M. SOLOMON and L. SCHMITZ OCTOBER 2010 DISCLAIMER This report was

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

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

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak

Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak Partially Coherent Fluctuations in Novel High Confinement Regimes of a Tokamak István Cziegler UCSD, Center for Energy Research Center for Momentum Transport and Flow Organization Columbia Seminar Feb

More information

Operational Phase Space of the Edge Plasma in Alcator C-Mod

Operational Phase Space of the Edge Plasma in Alcator C-Mod Operational Phase Space of the Edge Plasma in B. LaBombard, T. Biewer, M. Greenwald, J.W. Hughes B. Lipschultz, N. Smick, J.L. Terry, Team Contributed talk RO.00008 Presented at the 47th Annual Meeting

More information

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations 1 EXC/P5-02 ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science

More information

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D by J.S. degrassie, D.R. BAKER, K.H. BURRELL, C.M. GREENFIELD, H. IKEZI, Y.R. LIN-LIU, C.C. PETTY, and R. PRATER APRIL 1997 This report

More information

GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE

GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE by L. SCHMITZ, C. HOLLAND, T.L. RHODES, G. WANG, L. ZENG, A.E. WHITE,

More information

Possible Pedestal Transport Theory Models And Modeling Tests

Possible Pedestal Transport Theory Models And Modeling Tests Possible Pedestal Transport Theory Models And Modeling Tests J.D. Callen, University of Wisconsin, Madison, WI 53706-1609 DIII-D Pedestal Transport Workshop, General Atomics, San Diego, CA, February 17,

More information

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Transport Improvement Near Low Order Rational q Surfaces in DIII D Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink

More information

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges

MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges P.B. Snyder 1 Contributions from: H.R. Wilson 2, D.P. Brennan 1, K.H.

More information

Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D

Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D Multi-scale turbulence, electron transport, and Zonal Flows in DIII-D L. Schmitz1 with C. Holland2, T.L. Rhodes1, G. Wang1, J.C. Hillesheim1, A.E. White3, W. A. Peebles1, J. DeBoo4, G.R. McKee5, J. DeGrassie4,

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

Extension of High-Beta Plasma Operation to Low Collisional Regime

Extension of High-Beta Plasma Operation to Low Collisional Regime EX/4-4 Extension of High-Beta Plasma Operation to Low Collisional Regime Satoru Sakakibara On behalf of LHD Experiment Group National Institute for Fusion Science SOKENDAI (The Graduate University for

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

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Z. Yan 1, G.R. McKee 1, J.A. Boedo 2, D.L. Rudakov 2, P.H. Diamond 2, G. Tynan 2, R.J. Fonck 1, R.J. Groebner 3, T.H. Osborne 3, and

More information

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport 1 Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama Japan Atomic Energy Agency, Naka, Ibaraki-ken, 311-0193 Japan

More information

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 16th IAEA Fusion Conference

More information

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey

A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal. W. M. Stacey A neoclassical model for toroidal rotation and the radial electric field in the edge pedestal W. M. Stacey Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332, USA October, 2003 ABSTRACT

More information

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING by G.R. McKEE, C. HOLLAND, Z. YAN, E.J. DOYLE, T.C. LUCE, A. MARINONI, C.C. PETTY, T.L. RHODES, J.C. ROST, L. SCHMITZ, W.M. SOLOMON, B.J.

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

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

TOKAMAK EXPERIMENTS - Summary -

TOKAMAK EXPERIMENTS - Summary - 17 th IAEA Fusion Energy Conference, Yokohama, October, 1998 TOKAMAK EXPERIMENTS - Summary - H. KISHIMOTO Japan Atomic Energy Research Institute 2-2 Uchisaiwai-Cho, Chiyoda-Ku, Tokyo, Japan 1. Introduction

More information

ECH Density Pumpout and Small Scale Turbulence in DIII-D

ECH Density Pumpout and Small Scale Turbulence in DIII-D ECH Density Pumpout and Small Scale Turbulence in DIII-D By K.L. Wong, T.L. Rhodes, R. Prater, R. Jayakumar, R. Budny, C.C. Petty, R. Nazikian, and W.A. Peebles Background It has been known for more than

More information

GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY

GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY by B.A. GRIERSON, K.H. BURRELL and W.M. SOLOMON OCTOBER 212 DISCLAIMER This report was prepared as an account of

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

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power

More information

GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D

GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D by T.H. OSBORNE, M.A. MAHDAVI, M.S. CHU, M.E. FENSTERMACHER, R.J. La HAYE, A.W. LEONARD,

More information

Rotation and Neoclassical Ripple Transport in ITER

Rotation and Neoclassical Ripple Transport in ITER Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics

More information

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model 1 THC/3-3 ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model J.E. Kinsey, G.M. Staebler, J. Candy, and R.E. Waltz General Atomics, P.O. Box 8608, San Diego, California

More information

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

Innovative Concepts Workshop Austin, Texas February 13-15, 2006 Don Spong Oak Ridge National Laboratory Acknowledgements: Jeff Harris, Hideo Sugama, Shin Nishimura, Andrew Ware, Steve Hirshman, Wayne Houlberg, Jim Lyon Innovative Concepts Workshop Austin, Texas February

More information

Results From Initial Snowflake Divertor Physics Studies on DIII-D

Results From Initial Snowflake Divertor Physics Studies on DIII-D Results From Initial Snowflake Divertor Physics Studies on DIII-D S. L. Allen, V. A. Soukhanovskii, T.H. Osborne, E. Kolemen, J. Boedo, N. Brooks, M. Fenstermacher, R. Groebner, D. N. Hill, A. Hyatt, C.

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

Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit. Transport Physics of the Density Limit

Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit. Transport Physics of the Density Limit Dynamics of Zonal Shear Collapse in Hydrodynamic Electron Limit Transport Physics of the Density Limit R. Hajjar, P. H. Diamond, M. Malkov This research was supported by the U.S. Department of Energy,

More information

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier EX/C-Rb Relationship between particle and heat transport in JT-U plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),

More information

Thermal ion orbit loss and radial electric field in DIII-D

Thermal ion orbit loss and radial electric field in DIII-D Thermal ion orbit loss and radial electric field in DIII-D J.S. degrassie 1, J.A. Boedo 2, B.A. Grierson 3 1 General Atomics, P.O. Box 85608, San Diego, California, 92186-5608 USA 2 University of California

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

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

Understanding Confinement in Advanced Inductive Scenario Plasmas Dependence on Gyroradius and Rotation

Understanding Confinement in Advanced Inductive Scenario Plasmas Dependence on Gyroradius and Rotation 1 Understanding Confinement in Advanced Inductive Scenario Plasmas Dependence on Gyroradius and Rotation P.A. Politzer 1, C.D. Challis 2, E. Joffrin 3, T.C. Luce 1, M. Beurskens 2, P. Buratti 4, F. Crisanti

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

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

GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE

GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE by E.A. BELLI, J.A. BOEDO, J. CANDY, R.H. COHEN, P. COLELLA, M.A. DORF, M.R. DORR, J.A. HITTINGER,

More information

Modeling of ELM Dynamics for ITER

Modeling of ELM Dynamics for ITER Modeling of ELM Dynamics for ITER A.Y. PANKIN 1, G. BATEMAN 1, D.P. BRENNAN 2, A.H. KRITZ 1, S. KRUGER 3, P.B. SNYDER 4 and the NIMROD team 1 Lehigh University, 16 Memorial Drive East, Bethlehem, PA 18015

More information

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Akio KOMORI and LHD experiment group National Institute for Fusion Science, Toki, Gifu 509-5292, Japan (Received 4 January 2010 / Accepted

More information

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO 21 st IAEA Fusion Energy Conference Chengdu, China Oct. 16-21, 2006 DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO R. Maingi 1, A. Kirk 2, T. Osborne 3, P. Snyder 3, S. Saarelma 2, R. Scannell

More information

Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod

Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod PFC/JA-96-42 Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod A.E. Hubbard, J.A. Goetz, I.H. Hutchinson, Y. In, J. Irby, B. LaBombard, P.J. O'Shea, J.A. Snipes, P.C. Stek, Y. Takase, S.M.

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

DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS

DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS GA A23775 DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS by P. GOHIL NOVEMBER 2001 QTYUIOP DISCLAIMER This report was prepared as

More information

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team*

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team* ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 38th APS/DPP Meeting NOVEMBER 11 15, 1996 Denver, Colorado

More information

Understanding and Predicting Profile Structure and Parametric Scaling of Intrinsic Rotation. Abstract

Understanding and Predicting Profile Structure and Parametric Scaling of Intrinsic Rotation. Abstract Understanding and Predicting Profile Structure and Parametric Scaling of Intrinsic Rotation W. X. Wang, B. A. Grierson, S. Ethier, J. Chen, and E. Startsev Plasma Physics Laboratory, Princeton University,

More information

Core and edge toroidal rotation study in JT-60U

Core and edge toroidal rotation study in JT-60U Core and edge toroidal rotation study in JT-6U Japan Atomic Energy Agency M. Yoshida, Y. Sakamoto, M. Honda, Y. Kamada, H. Takenaga, N. Oyama, H. Urano, and the JT-6 team JT-6U EXC/3-2 1 23rd IAEA Fusion

More information

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions P.B. Snyder 1, T.H. Osborne 1, M.N.A. Beurskens 2, K.H. Burrell 1, R.J. Groebner 1, J.W. Hughes 3, R. Maingi

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

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL

STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL th IAEA Fusion Energy Conference Vilamoura, Portugal, to 6 November IAEA-CN-6/EX/P-7 STATIONARY, HIGH BOOTSTRAP FRACTION PLASMAS IN DIII-D WITHOUT INDUCTIVE CURRENT CONTROL P.A. POLITZER, A.W. HYATT, T.C.

More information

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.

More information

Tuomas Tala. Core Density Peaking Experiments in JET, DIII-D and C-Mod in Various Operational Scenarios Driven by Fueling or Transport?

Tuomas Tala. Core Density Peaking Experiments in JET, DIII-D and C-Mod in Various Operational Scenarios Driven by Fueling or Transport? Tuomas Tala Core Density Peaking Experiments in JET, DIII-D and C-Mod in Various Operational Scenarios Driven by Fueling or Transport? Core Density Peaking Experiments in JET, DIII-D and C-Mod in Various

More information

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod B. LaBombard, D. Brunner, A.Q. Kuang, W. McCarthy, J.L. Terry and the Alcator Team Presented at the International

More information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information