The performance of improved H-modes at ASDEX Upgrade and projection to ITER
|
|
- Lee McDowell
- 6 years ago
- Views:
Transcription
1 EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy 3, A. Gude 1, L.D. Horton 1, V. Igochine 1, O. Kardaun 1, C.F. Maggi 1, M. Maraschek 1, V. Mertens 1, R. Neu 1, A. Peeters 1, G. V. Pereverzev 1, A. Stäbler 1, J. Stober 1, W. Suttrop 1 and the ASDEX Upgrade Team. 1 Max-Planck-Institut für Plasmaphysik, EURATOM-Association, D-85748, Germany. 2 The University of Wisconsin, Madison, USA. 3 Dep. of Physics, University College Cork, Association EURATOM-DCU, Cork, Ireland. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 1
2 Motivation: performance 8 :15 MA, <n e >/n GW = P aux = 4MW P fus 6 primary goal: Q=1, P fus ~4MW. Q 4 β N =1.8 4 Energy confinement: IPB98(y,2) scaling expression. 2 2 size, 15MA/5.3T, P aux 73 MW, <n e >=.85, H 98 (y,2) Mukhovatov V. et al Nucl. Fusion 43 (23) 942 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 2
3 Motivation: performance Q :15 MA, <n e >/n GW =.85 P aux = 4MW β N =1.8 β N >2 P fus Integrated simulation codes: envelope of performance. Strong dependence, of Q and P fus with H 98 (y,2). Significant increase in performance for small increase in energy confinement ±1 tech. st. dev log non-linear int H 98 (y,2) Mukhovatov V. et al Nucl. Fusion 43 (23) 942 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 3
4 Motivation: performance Q :15 MA, <n e >/n GW =.85 P aux = 4MW β N =1.8 β N >2 P fus Integrated simulation codes: envelope of performance. Strong dependence, of Q and P fus with H 98 (y,2). Significant increase in performance for small increase in energy confinement ±1 tech. st. dev log non-linear int Mukhovatov V. et al Nucl. Fusion 43 (23) H 98 (y,2) H 98 (y,2) > 1, and β N > 2: Higher performance at 15 MA. Long pulse operation, I p =11 to 14 MA, with Q=5-1 (Hybrid). DEMO: H 98 (y,2) 1.2, β N 3.5. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 4
5 Motivation Outline ASDEX Upgrade: Improved H-modes (H 98 (y,2) > 1, and β N > 2). Operational range: - wide range in density, T i /T e and ν*. - at q high beta: Limits and control of NTMs. Scaling to using experimental data. Conclusions. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 5
6 ASDEX Upgrade: H-mode data 1.6 ASDEX Upgrade H-mode data 1.4 H-mode operation for a wide range of plasma conditions: H 98 (y,2) I p =.6-1.4MA, B T =1.6-3.T. All type I ELMy H-modes:.8 q 95 < 5.5, stationary >.2 s. (values shown are averaged).6 H-modes with Type I ELMs β N George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 6
7 Current rise phase Low magnetic shear z(m) I p =3 ka z(m) I p =54 ka z(m) I p =7 ka z(m) I p = MA W C R(m) -1. W C R(m) -1. W C R(m) -1. W C R(m) heating >1. time (s) Current rise: 1. Early divertor configuration t~.5s. 2. low <n e > ~ 3x1 19 m -3, control of impurities. 3. Additional heating: Slow down the current penetration. Low magnetic shear in the centre. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 7
8 Low magnetic shear Improved H-mode 5 4 ASDEX Upgrade: Equilibrated q-profiles ~ zero magnetic shear q q 95 = shear/q ρ tor 1 MSE data available in 26. Timing of preheating: control of q-profile H 98 (y,2). The q-profile remains flat in the core. McCarthy P. et al, EX/P3-7 Stober J. et al, EX/P1-7 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 8
9 Low magnetic shear Improved H-mode ASDEX Upgrade: Equilibrated q-profiles ~ zero magnetic shear (3,2) NTM activity Fishbone activity q q 95 = shear/q ρ tor 1 MSE data available in 26. Timing of preheating: control of q-profile H 98 (y,2). The q-profile remains flat in the core. MHD modes main candidate. Typically (3,2) NTMs and higher (m,n) activity or fishbone activity. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 9
10 ASDEX Upgrade: Improved H-mode data ASDEX Upgrade, all improved H-modes A second dataset includes all improved H-mode discharges: H 98 (y,2) Minimum values required for DEMO Early heating (some selected cases with late heating). Stationary for >.5 s..8 NOT just a selection of the best discharges..6 Improved H-modes β N George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 1
11 ASDEX Upgrade: Improved H-mode data 1.6 ASDEX Upgrade Improved H-modes do not exclusively occupy the domain 1.4 H 98 (y,2) > 1 at β N = 2-3. H 98 (y,2) Any H-mode, when it manages to achieve high beta is likely to develop low central shear in the.8 centre, due to bootstrap current (overlap of grey and red data)..6 Improved H-modes H-modes (Type I) Physics criteria for improved H β N modes would depend on the details of the current density profile (not routinely available). George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 11
12 ASDEX Upgrade: Improved H-mode data Average values q 95 H 98 (y,2) β N Type I ELMy H-modes (944) Improved H-modes (259) Various physics studies on the reason for the high stability/ confinement in improved H-modes. Core: Stober J. et al, EX/P1-7 Pedestal: Suttrop W. et al, EX/8-5 Maggi C. et al, IT/P1-6 (various experiments) l i Similar results have been obtained in other experiments (DIII-D, JET, JT-6U, NSTX..), for a range of conditions (See this conference!!). George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 12
13 Operational range: Density ASDEX Upgrade Improved H-modes: Typically operate at low density, <n e >/n GW = H 98 (y,2) After formation of q(r), the density can be increased together with an increase in.8 heating power and δ..6 Improved H-modes H-modes (Type I) <n e >/n GW <n e >/n GW =.85, H 98 (y,2) ~ 1.2 are obtained at high δ=.4. At 1MA: <n e >=1.1x 1 2 m -3. Tolerable ELMs. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 13
14 Operational range: T i /T e ASDEX Upgrade improved H-modes 1. Operation at high <n e >. 2. ICRH and NBI at low <n e >..7 < T i /T e < 2.5 T i /T e T i /T e ~ 1 for a substantial subset of the data, while maintaining high confinement..5. NBI only NBI+ICRH <n e >/n GW Moreover, some of these discharges have low plasma rotation (low momentum input). George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 14
15 Operational range: ν* H 98 (y,2) ASDEX Upgrade Improved H-modes H-modes (Type I) ν*/ν* Strongest correlation of maximum H 98 (y,2) with plasma collisionality (ν*/ν* ). Also density peaking (n e /<n e >) can be higher at lower ν*/ν*. Weisen H. et al, EX/8-4 β and v* dependence of the IPB98(y,2) scaling expression are under investigation. McDonald D. et al, EX/P3-5 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 15
16 Operational range: low q 95 = I p (MA) P NBI even n odd n D α # 2449 P ICH 1.2MA/2.T q 95 = 3.17, NBI used with beta feedback, 5% of NBI is off-axis! Central ICRF heating. <n e >=6.4x1 19 m -3, T i /T e =1.4 <n e >/n GW =.42, ν*/ν* =2. H 98 (y,2) rises to 1.4 at β N =2.9. C W,core = 2.5x1-5 (< 1-4 ). 3 β N 1 H 98 (y,2) time (s) George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 16
17 Operational range: low q 95 = I p (MA) P NBI even n odd n D α # 2449 P ICH 1.2MA/2.T q 95 = 3.17, NBI used with beta feedback, 5% of NBI is off-axis. Central ICRF heating. <n e >=6.4x1 19 m -3, T i /T e =1.4 <n e >/n GW =.42, ν*/ν* =2. H 98 (y,2) rises to 1.4 at β N =2.9. C W,core = 2.5x1-5 (< 1-4 ). 3 1 β N H 98 (y,2) time (s) Core MHD: (1,1) fishbones. (4,3) NTMs. NO sawteeth. Early (3,2) NTM when β N ~2. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 17
18 Operational range: ECCD, stabilise (3,2) NTM # (1MW ECRH) β N H 98 (y,2) P ECRH # Time (s) 3,2 activity Killer gas disruption at q=1.5 position 1. ECCD: Stabilise this (3,2) NTM at q 95 ~3.1 After ECCD, discharge continues as improved H-mode (shown before). Zohm H. et al, EX/4-1Rb 2. Otherwise (2,1) NTM may develop, and disruption recognition algorithms will act: (mode-lock, radiation peaking, regime identification, neural net): React by issuing a soft stop or triggering killer gas injection. Pautasso G. et al, EX/P Stabilisation of (3,2) NTM is not required for improved H-modes with q 95 > 4. Stober J. et al, EX/P1-7 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 18
19 Scaling to using experimental data Motivation: Integrated simulation codes rely on use of transport models and models for actuators, require benchmarking on current experiments. Scaling the measured kinetic profiles to : 1% fit to experimental data, gradient length preserved, pedestal. Use experimental profile shapes. Same β N, H-factor's. Use geometry. Impurities: Be 2 %, Ar.12 %, He 4.3 % (n D +n T )/n e ~.8. Luce T. et al 24 Phys. Plasmas Assemble set of discharges with good profile measurements. predictions: P fus, P aux, Q (+ other parameters using ASTRA). Tardini G. et al 33rd EPS Conference, Rome June 26, P1.112 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 19
20 Scaling to using experimental data Density: Use shape of n e profile from ASDEX Upgrade, set <n e > =.85n GW. Temperatures: Use shape of T i profile or use shape of T e profile from ASDEX Upgrade (select highest), set T i =T e and β N =β N AUG. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 2
21 Scaling to : q 95 =3., β N =2.1, high <n e > n e (x1 19 m -3 ) n e r min (m) T i,e (kev) β N,th = β N,th AUG T i = T e r min (m) Density: Use shape of n e profile from ASDEX Upgrade, set <n e > =.85n GW. Temperatures: Use shape of T i profile or use shape of T e profile from ASDEX Upgrade (select highest), set T i =T e and β N =β N AUG. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 21
22 Scaling to : q 95 =3., β N =2.1, high <n e > n e (x1 19 m -3 ) n e Scenario 2 T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) r min (m) Comparison with integrated scenario modelling (Scenario 2): Density: Assumed flat. Temperatures: Set pedestal, models for core transport & heating systems. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 22
23 Scaling to : q 95 =3.17, β N =2.9 n e (x1 19 m -3 ) n e n D +n T Scenario 2 T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) r min (m) At higher β N (Improved H-mode): Temperature profiles rise over whole plasma region. Consistent with observations of increased edge pedestal. Suttrop W. et al, EX/8-5 Maggi C. et al, IT/P1-6 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 23
24 Prediction of fusion performance in P fus Q=6.5 Q=11.4 predictions at <n>/n GW =.85 Q= Q=8 15 MA 4 typical cases: q 95 β N H 98 (y,2) Open symbols P aux > 73 MW* Closed symbols P aux 73 MW* I p (MA) *P aux based on using IPB98(y,2) scaling. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 24
25 Prediction of fusion performance in 12 predictions at <n>/n GW =.85 Operation at β N,th =2-3: P fus β N,th = 2-3 β N,th MA Significant fusion power for I p =9.5MA to I p =12MA. With bootstrap current fraction f BS ~.4, and Q=6-15. Long pulse lengths (> 4s). 2 Open symbols P aux > 73 MW* Closed symbols P aux 73 MW* I p (MA) At low q 95 ~3 (I p =14-15 MA) would in principle be able to reach P fus ~1GW, Q=. *P aux based on using IPB98(y,2) scaling. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 25
26 Prediction of fusion performance in 4 Physics Basis 1999 Nucl. Fusion IPB98 scaling Petty G. et al 23 Fusion Sci. Technol GyroBohm scaling Cordey J. G. et al 25 Nucl. Fusion Cordey5 scaling P aux 2 P aux = 73 MW Q = β N,th - Q = β N,th - Q = β N,th - Q and input power (P aux ) required (ASDEX Upgrade profile data): Calculated for three different energy confinement scaling expressions. Using IPB98(y,2): In some high β cases : P aux > 73MW. I p <11MA, despite H 98 (y,2)~1.4. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 26
27 Conclusions ASDEX Upgrade: H-modes with low magnetic shear in the centre: H 98 (y,2) > 1 and β N = Operation at high density and T i /T e ~ 1 is demonstrated. Highest H 98 (y,2) values are achieved at relevant ν*. At q 95 =3.1: H 98 (y,2)=1.4, β N =2.9, fishbone activity keeps q(r) stationary. ECCD can be used to stabilise (3,2) NTM activity (q 95 ~3). predictions, scaling kinetic profile shapes : <n e >=.85n GW, keep β N,th. At q 95 =3.1: P fus =17 MW, Q=. At I p =9.5-12MA: P fus 3-6 MW, Q=6-15 (some cases P aux >73 MW). George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 27
28 Back-up slides George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 28
29 Operation: Tungsten coverage 85% W CONC, in the core 1e-2 1e-3 1e-4 1e-5 ASDEX Upgrade Improved H-modes All AUG discharges 1e-6 Gruber O. et al, OV/2-3 Dux R. et al, EX/3-3Ra 1e Discharge # All H-modes require central ICRH or ECRH to avoid impurity accumulation. Operation at <n e > ~ 4-6x1 19 m -3 requires a boronisation to minimise tungsten influxes. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 29
30 Operational range: Density, ν* Contours for H 98 (y,2) values Strongest correlation of maximum H 98 (y,2) with plasma collisionality (ν*/ν* ). ν*/ν* Also density peaking (n e /<n e >) can be higher at lower ν*/ν*. 2 1 β and v* dependence of the IPB98(y,2) scaling expression are under investigation β N McDonald D. et al, EX/P3-5 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 3
31 Operational range: low q 95 = F (khz) Core MHD activity ELMs Soft X-ray data 6 4 (4,3) NTMs 2 fishbone activity time (s) George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 31
32 Use of ECCD to stabilise (3,2) NTM # (1MW ECRH) # T e _Fit (kev) # ECRH deposition 4 T i _Fit (kev) # ECRH deposition 3,2 activity β N H 98 (y,2) Killer gas disruption 1 NTM t=1.9s With ECRH t=2.3s rho_pol # n e _Fit (x1 19 m -3 ) ECRH deposition 1 NTM t=1.9s With ECRH t=2.3s rho_pol Zohm H. et al, EX/4-1Rb P ECRH Time (s) 2 NTM t=1.9s With ECRH t=2.3s rho_pol George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 32
33 Scenario 2 Physics Basis 1999 Nucl. Fusion n e (x1 19 m -3 ) n e n D +n T T i,e (kev) T i, T e (T i +T e )/ r min (m) r min (m) <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) Sc / 21.2 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 33
34 Scaling to : q 95 =3., β N =2.1, high <n e > n e (x1 19 m -3 ) n e n D +n T Scenario 2 T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) r min (m) <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) AUG # (78) George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 34
35 Scaling to : q 95 =3.17, β N =2.9 n e (x1 19 m -3 ) n e n D +n T Scenario 2 T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) r min (m) <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) AUG # George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 35
36 Scaling to : q 95 =3.8, β N =2.6 n e (x1 19 m -3 ) n e n D +n T Scenario r min (m) T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) AUG # George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 36
37 Scaling to : q 95 =4.6, β N =2.4 n e (x1 19 m -3 ) n D +n T n e Scenario r min (m) T i,e (kev) Scenario 2 β N,th = β N,th AUG T i = T e r min (m) <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) AUG # George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 37
38 Prediction of fusion performance in <n e >/n GW =.85 q 95 I p (MA) β N P fus H 98 (y,2) Q P aux <n e > (1 19 m -3 ) n e (1 19 m -3 ) T e /T i (kev) profile shapes Sc / 21.2 AUG # (78) AUG # AUG # AUG # George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 38
39 Prediction of fusion performance in 12 I BS /I p predictions at <n>/n GW =.85 Calculated bootstrap fraction f BS increases at lower current. P fus =.25 =.3 =.35 =.4 (15MA) ~.18. Maximum of cases presented here: f BS ~ MA A current ramp to lower plasma 2 currents compared to reference design AND the I p (MA) ability to operate at same stored energy. longer pulse length. George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 39
40 Prediction of fusion performance in P fus ASDEX Upgrade Improved H-modes Open symbols P aux > 73 MW Closed symbols P aux 73 MW 5.3 kev ± 23% T e,ped _ (kev) Most of the scaled edge pedestal temperatures are within range of what is expected for typical H-modes in. 5.3keV ± 23% Sugihara M. et al 23 Plasma Phys. Control. Fusion 45 L55 George Sips 21 st IAEA Fusion Energy Conference, Chengdu, China, October 26 4
INTERNATIONAL ATOMIC ENERGY AGENCY 21 st IAEA Fusion Energy Conference Chengdu, China, October 2006
IAEA INTERNATIONAL ATOMIC ENERGY AGENCY st IAEA Fusion Energy Conference Chengdu, China, 6 - October 6 IAEA-CN-9/EX/- THE PERFORMANCE OF IMPROVED H-MODES AT ASDEX UPGRADE AND PROJECTION TO A.C.C. SIPS,
More informationAlcator 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 informationPhysics studies of the improved H-mode scenario in ASDEX Upgrade
1 EX/P1-7 Physics studies of the improved H-mode scenario in ASDEX Upgrade J. Stober 1, A.C.C. Sips 1, C. Angioni 1, C. Forest, O. Gruber 1, J. Hobirk 1, L.D. Horton 1, C.F. Maggi 1, M. Maraschek 1, P.
More informationPhysics Basis of ITER-FEAT
IAEA-CN-77/ITERP/05 Physics Basis of ITER-FEAT M. Shimada 1), D. J. Campbell 2), M. Wakatani 3), H. Ninomiya 4), N. Ivanov 5), V. Mukhovatov 1) and the ITER Joint Central Team and Home Teams 1) ITER Joint
More informationTungsten: An option for divertor and main chamber PFCs in future fusion devices
ASDEX Upgrade Tungsten: An option for divertor and main chamber PFCs in future fusion devices R. Neu, R. Dux, A. Kallenbach, C.F. Maggi, T. Pütterich, M. Balden, T. Eich, J.C. Fuchs, O. Gruber, A. Herrmann,
More informationCharacterization 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 informationExperimental studies of ITER demonstration discharges
IT/2-2 Experimental studies of ITER demonstration discharges George Sips MPI für Plasmaphysik, EURATOM-Association, Garching, Germany T.A. Casper 2, E.J. Doyle 3, G. Giruzzi 4, Y. Gribov 5, J. Hobirk 1,
More informationSummary of CDBM Joint Experiments
11th Meeting of the ITPA CDBM TG, Chengdu, 23-24 Oct. 2006 Summary of CDBM Joint Experiments Mon. 23 Oct, morning T. Takizuka (JAEA) CDB-2: Confinement scaling in ELMy H-modes; β degradation C.C. Petty
More informationRadiative type-iii ELMy H-mode in all-tungsten ASDEX Upgrade
Radiative type-iii ELMy H-mode in all-tungsten ASDEX Upgrade J. Rapp 1, A. Kallenbach 2, R. Neu 2, T. Eich 2, R. Fischer 2, A. Herrmann 2, S. Potzel 2, G.J. van Rooij 3, J.J. Zielinski 3 and ASDEX Upgrade
More informationCritical Physics Issues for DEMO
Max-Planck-Institut für Plasmaphysik Critical Physics Issues for DEMO L.D. Horton with thanks to the contributors to the EFDA DEMO physics tasks in 2006 and to D.J. Campbell, who organized this effort
More informationRecent 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 informationCurrent density modelling in JET and JT-60U identity plasma experiments. Paula Sirén
Current density modelling in JET and JT-60U identity plasma experiments Paula Sirén 1/12 1/16 Euratom-TEKES Euratom-Tekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET
More informationConfinement and edge studies towards low ρ* and ν* at JET
1 Confinement and edge studies towards low ρ* and ν* at JET I Nunes 1,2, P J Lomas 3, D C McDonald 3, G Saibene 4, R Sartori 4, I Voitsekhovitch 3, M Beurskens 3, G Arnoux 3, A Boboc 3, T Eich 5, C Giroud
More informationMHD Induced Fast-Ion Losses in ASDEX Upgrade
Max-Planck-Insititut für Plasmaphysik MHD Induced Fast-Ion Losses in ASDEX Upgrade Manuel García-Muñoz1 H.-U. Fahrbach1, M. Bruedgam1, V. Bobkov1, A. Flaws1, M. Gobbin2, S. Günter1, P. Lauber1, M. Mantsinen1,4,
More informationDevelopment in DIII D Tokamak Hybrid Operation Scenarios
Development in Tokamak Hybrid Operation Scenarios by R.J. Jayakumar in collaboration with M.R. Wade, T.C. Luce, P.A. Politzer, A.W. Hyatt, J.R. Ferron, C.M. Greenfield, E.H. Joffrin, M. Murakami, C.C.
More informationSTUDY OF ADVANCED TOKAMAK PERFORMANCE USING THE INTERNATIONAL TOKAMAK PHYSICS ACTIVITY DATABASE
INTERNATIONAL ATOMIC ENERGY AGENCY 20th IAEA Fusion Energy Conference Vilamoura, Portugal, 1-6 November 2004 IAEA-CN-116/ STUDY OF ADVANCED TOKAMAK PERFORMANCE USING THE INTERNATIONAL TOKAMAK PHYSICS ACTIVITY
More informationPerformance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges
Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges R. C. Wolf, J. Hobirk, G. Conway, O. Gruber, A. Gude, S. Günter, K. Kirov, B. Kurzan, M. Maraschek, P. J.
More informationComparison of ITER Performance Predicted by Semi-Empirical and Theory-Based Transport Models
1 CT/P-3 Comparison of ITER Performance Predicted by Semi-Empirical and Theory-Based Transport Models V. Mukhovatov 1), Y. Shimomura 1), A. Polevoi 1), M. Shimada 1), M. Sugihara 1), G. Bateman 2), J.G.
More informationCorrelations 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 informationINTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, October 2008
IAEA INTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, 13-18 October 2008 IAEA-CN-165/EX/1-4Ra DEVELOPMENT OF THE HYBRID SCENARIO IN JET E. JOFFRIN1) 5), J. HOBIRK
More informationHigh 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 informationIntegrated Modelling of ITER Scenarios with ECCD
Integrated Modelling of ITER Scenarios with ECCD J.F. Artaud, V. Basiuk, J. Garcia, G. Giruzzi*, F. Imbeaux, M. Schneider Association Euratom-CEA sur la Fusion, CEA/DSM/DRFC, CEA/Cadarache, 13108 St. Paul-lez-Durance,
More informationActive Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak
Active Control of Alfvén Eigenmodes in the ASDEX Upgrade tokamak M. Garcia-Munoz, S. E. Sharapov, J. Ayllon, B. Bobkov, L. Chen, R. Coelho, M. Dunne, J. Ferreira, A. Figueiredo, M. Fitzgerald, J. Galdon-Quiroga,
More informationAdvances 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 informationImpurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code
Contrib. Plasma Phys. 56, No. 6-8, 772 777 (2016) / DOI 10.1002/ctpp.201610008 Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code K. Gała zka 1, I. Ivanova-Stanik 1, M. Bernert 2, A. Czarnecka
More informationPredictive Study on High Performance Modes of Operation in HL-2A 1
1 EX/P-0 Predictive Study on High Performance Modes of Oration in HL-A 1 Qingdi GAO 1), R. V. BUDNY ), Fangzhu LI 1), Jinhua ZHANG 1), Hongng QU 1) 1) Southwestern Institute of Physics, Chengdu, Sichuan,
More informationAdvanced Tokamak Research in JT-60U and JT-60SA
I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development
More informationPHYSICS OF CFETR. Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China.
PHYSICS OF CFETR Baonian Wan for CFETR physics group Institute of Plasma Physcis, Chinese Academy of Sciences, Hefei, China Dec 4, 2013 Mission of CFETR Complementary with ITER Demonstration of fusion
More information1999 RESEARCH SUMMARY
1999 RESEARCH SUMMARY by S.L. Allen Presented to DIII D Program Advisory Committee Meeting January 2 21, 2 DIII D NATIONAL FUSION FACILITY SAN DIEGO 3 /SLA/wj Overview of Physics Results from the 1999
More informationT. PÜTTERICH et al. 1
T. PÜTTERICH et al. THE ITER BASELINE SCENARIO INVESTIGATED AT ASDEX UPGRADE T. PÜTTERICH, O. SAUTER, V. BOBKOV, M. CAVEDON, M.G. DUNNE, L. GUIMARAIS, A. KAPPATOU, P.T. LANG, M. MANTSINEN, R.M. MCDERMOTT,
More informationDimensionless Identity Experiments in JT-60U and JET
1 IAEA-CN-116/IT/1-2 Dimensionless Identity Experiments in JT-60U and JET G Saibene 1, N Oyama 2, Y Andrew 3, JG Cordey 3, E de la Luna 4, C Giroud 3, K Guenther 3, T Hatae 2, GTA Huysmans 5, Y Kamada
More informationFirst 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 informationFast Particle Physics on ASDEX Upgrade Interaction of Energetic Particles with Large and Small Scale Instabilities
1 EX/6-1 Fast Particle Physics on ASDEX Upgrade Interaction of Energetic Particles with Large and Small Scale Instabilities S. Günter 1, G. Conway 1, C. Forest 2, H.-U. Fahrbach 1, M. Garcia Muñoz 1, S.
More informationASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER
ASSESSMENT AND MODELING OF INDUCTIVE AND NON-INDUCTIVE SCENARIOS FOR ITER D. BOUCHER 1, D. MOREAU 2, G. VAYAKIS 1, I. VOITSEKHOVITCH 3, J.M. ANÉ 2, X. GARBET 2, V. GRANDGIRARD 2, X. LITAUDON 2, B. LLOYD
More informationTHE 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 informationPower requirement for accessing the H-mode in ITER
Journal of Physics: Conference Series Power requirement for accessing the H-mode in ITER To cite this article: Y R Martin et al 2008 J. Phys.: Conf. Ser. 123 012033 Related content - Dependence of the
More informationOverview of ASDEX Upgrade Results
1 OV/2-2 Overview of ASDEX Upgrade Results O. Gruber for the ASDEX Upgrade Team* Max-Planck-Institut für Plasmaphysik, EURATOM Association-IPP, 85748 Garching, Germany * ASDEX Upgrade Team: see last page
More informationITER 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 informationCharacteristics 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 informationPellet induced high density phases during ELM suppression in ASDEX Upgrade
Pellet induced high density phases during ELM suppression in ASDEX Upgrade P. T. Lang 1), C. Angioni 1), R.M. Mc Dermott 1), R. Fischer 1), J.C. Fuchs 1), O. Kardaun 1), B. Kurzan 1), G. Kocsis 2), M.
More informationContents. Fitting Pedestal data to a) Thermal Conduction Model. b) MHD Limit Model. Determining scaling of Core.
Contents An Analysis of the Multi-machine Pedestal and Core Databases by J.G. Cordey, O. Kardaun, D.C. McDonald and members of the ITPA Pedestal and Global database groups Fitting Pedestal data to a) Thermal
More informationINTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, October 2008
IAEA INTERNATIONAL ATOMIC ENERGY AGENCY 22 nd IAEA Fusion Energy Conference Geneva, Switzerland, 13-18 October 2008 EXPERIMENTAL STUDIES OF ITER DEMONSTRATION DISCHARGES IAEA-CN-165/ A.C.C. SIPS 1, T.A.
More informationProgressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.
Progressing Performance Tokamak Core Physics Marco Wischmeier Max-Planck-Institut für Plasmaphysik 85748 Garching marco.wischmeier at ipp.mpg.de Joint ICTP-IAEA College on Advanced Plasma Physics, Triest,
More informationRole of Magnetic Configuration and Heating Power in ITB Formation in JET.
Role of Magnetic Configuration and Heating Power in ITB Formation in JET. The JET Team (presented by V. Parail 1 ) JET Joint Undertaking, Abingdon, Oxfordshire, United Kingdom 1 present address: EURATOM/UKAEA
More informationAnnual Report Max-Planck-Institut für Plasmaphysik
Annual Report 2002 Max-Planck-Institut für Plasmaphysik Foreword At the Max-Planck-Institut für Plasmaphysik (IPP) we investigate the basic physics associated with the construction and operation of a future
More informationGA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D
GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D by E.J. DOYLE, J.C. DeBOO, T.A. CASPER, J.R. FERRON, R.J. GROEBNER, C.T. HOLCOMB, A.W. HYATT, G.L. JACKSON, R.J. LA HAYE, T.C. LUCE, G.R.
More informationOverview of ASDEX Upgrade results
INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion () 7 8 PII: S9-()68- Overview of ASDEX Upgrade results H. Zohm, C. Angioni, R. Arslanbekov, C. Atanasiu,
More informationErosion 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 informationDimensionless Identity Experiments in JT-60U and JET
Dimensionless Identity Experiments in JT-60U and JET G Saibene 1, N Oyama 2, Y Andrew 3, JG Cordey 3, E de la Luna 4, C Giroud 3, K Guenther 3, T Hatae 2, GTA Huysmans 5, Y Kamada 2, MAH Kempenaars 6,
More informationStudies 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 informationHIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES
HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,
More informationImpact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak
Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak M. Garcia-Munoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,
More informationOptimization of Stationary High-Performance Scenarios
Optimization of Stationary High-Performance Scenarios Presented by T.C. Luce National Fusion Program Midterm Review Office of Fusion Energy Science Washington, DC September, 6 QTYUIOP 8-6/TCL/rs Strategy
More informationOverview of ASDEX Upgrade results
Overview of ASDEX Upgrade results O.Gruber,R.Arslanbekov,C.Atanasiu a,a.bard,g.becker,w.becker, M. Beckmann, K. Behler, K. Behringer, A. Bergmann, R. Bilato, D. Bolshukin, K. Borrass, H.-S. Bosch, B. Braams
More informationUnderstanding 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 informationITR/P1-19 Tokamak Experiments to Study the Parametric Dependences of Momentum Transport
Tokamak Experiments to Study the Parametric Dependences of Momentum Transport T. Tala 1, R.M. McDermott 2, J.E. Rice 3, A. Salmi 1, W. Solomon 4, C. Angioni 2, C. Gao 3, C. Giroud 5, W. Guttenfelder 4,
More informationDeveloping the Physics Basis for the ITER Baseline 15 MA Scenario in Alcator C-Mod
Developing the Physics Basis for the ITER Baseline 15 MA Scenario in Alcator C-Mod C. E. Kessel 1, S. M. Wolfe 2, I. H. Hutchinson 2, J. W. Hughes 2, Y. Lin 2, Y. Ma 2, D. R. Mikkelsen 1, F. M. Poli 1,
More informationPredicting the Rotation Profile in ITER
Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton
More informationDIII 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 informationITER. Power and Particle Exhaust in ITER ITER
Power and Particle Exhaust in ITER ITER G. Janeschitz, C. Ibbott, Y. Igitkhanov, A. Kukushkin, H. Pacher, G. Pacher, R. Tivey, M. Sugihara, JCT and HTs San Diego.5.2 Power and Particle Exhaust in ITER
More informationEffect of ideal kink instabilities on particle redistribution
Effect of ideal kink instabilities on particle redistribution H. E. Ferrari1,2,R. Farengo1, P. L. Garcia-Martinez2, M.-C. Firpo3, A. F. Lifschitz4 1 Comisión Nacional de Energía Atómica, Centro Atomico
More informationThe role of stochastization in fast MHD phenomena on ASDEX Upgrade
1 EX/P9-10 The role of stochastization in fast MHD phenomena on ASDEX Upgrade V. Igochine 1), O.Dumbrajs 2,3), H. Zohm 1), G. Papp 4), G. Por 4), G. Pokol 4), ASDEX Upgrade team 1) 1) MPI für Plasmaphysik,
More information- 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 informationS1/2 EX/S, EX/D, EX/W
S1/2 EX/S, EX/D, EX/W S1/2 EX/S - Magnetic Confinement Experiments: Stability 47 papers EX/W - Magnetic Confinement Experiments: Wave plasma interactions, current drive & heating, energetic particles 58
More informationPROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIIIÐD *
PROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIIIÐD * B.W. RICE, K.H. BURRELL, J.R. FERRON, C.M. GREENFIELD, G.L. JACKSON, L.L. LAO, R.J. LA HAYE, T.C. LUCE, B.W. STALLARD, E.J. STRAIT, E.J.
More informationDevelopment and Validation of a Predictive Model for the Pedestal Height (EPED1)
Development and Validation of a Predictive Model for the Pedestal Height (EPED1) P.B. Snyder 1 with R.J. Groebner 1, A.W. Leonard 1, T.H. Osborne 1, M. Beurskens 3, L.D. Horton 4, A.E. Hubbard 5, J.W.
More informationTungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER
Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER A. Loarte ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex, France
More informationDivertor 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 informationEvolution of Bootstrap-Sustained Discharge in JT-60U
EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University
More informationFAST 1 : a Physics and Technology Experiment on the Fusion Road Map
Fusion Advanced Studies Torus FAST 1 : a Physics and Technology Experiment on the Fusion Road Map Presented by A. A. Tuccillo on behalf of ENEA-Euratom Association Univ. of Rome Tor Vergata Univ. of Catania
More informationIntegrated Core-SOL-Divertor Modelling for ITER Including Impurity: Effect of Tungsten on Fusion Performance in H-mode and Hybrid Scenario
1 TH/P3-45 Integrated Core-SOL-Divertor Modelling for ITER Including Impurity: Effect of Tungsten on Fusion Performance in H-mode and Hybrid Scenario R. Zagórski 1, I.Voitsekhovitch 2, I. Ivanova-Stanik
More informationImproved Confinement in JET High b Plasmas with an ITER-Like Wall
CCFE-PR(15)09 C.D. Challis, J. Garcia, M. Beurskens, P. Buratti, E. Delabie, P. Drewelow, L. Frassinetti, C. Giroud, N. Hawkes, J. Hobirk, E. Joffrin, D. Keeling, D.B. King, C.F. Maggi, J. Mailloux, C.
More informationOVERVIEW 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 informationGlobal stabilization effect of Shafranov shift on the edge pedestal plasmas in JET and JT-60U
26 th IAEA Fusion Energy Conference Kyoto, Japan, 17-22 October 216 IAEA-CN-23/EX/3- Global stabilization effect of Shafranov shift on the edge pedestal plasmas in JET and JT-6U H. Urano 1, S. Saarelma
More informationOn 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 informationMulti-Machine Experiments to Study the Parametric Dependences of Momentum Transport
EUROFUSION WPJET1-PR(16) 15411 TJJ Tala et al. Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport Preprint of Paper to be submitted for publication in 43rd European Physical
More informationTOKAMAK 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 informationGA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D
GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D by C.C. PETTY, P.A. POLITZER, R.J. JAYAKUMAR, T.C. LUCE, M.R. WADE, M.E. AUSTIN, D.P. BRENNAN, T.A. CASPER, M.S. CHU, J.C. DeBOO, E.J. DOYLE,
More informationPerformance limits. Ben Dudson. 24 th February Department of Physics, University of York, Heslington, York YO10 5DD, UK
Performance limits Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 24) Previously... In the last few
More informationModelling of pulsed and steady-state DEMO scenarios
Modelling of pulsed and steady-state DEMO scenarios G. Giruzzi1, J.F. Artaud1, M. Baruzzo2,4, T. Bolzonella2, E. Fable3, L. Garzotti4, I. Ivanova-Stanik5, R. Kemp4, D.B. King4, M. Schneider1, R. Stankiewicz5,
More informationNeoclassical Tearing Modes
Neoclassical Tearing Modes O. Sauter 1, H. Zohm 2 1 CRPP-EPFL, Lausanne, Switzerland 2 Max-Planck-Institut für Plasmaphysik, Garching, Germany Physics of ITER DPG Advanced Physics School 22-26 Sept, 2014,
More informationC-Mod Advanced Tokamak Program: Recent progress and near-term plans
Advanced Tokamak Program: Recent progress and near-term plans Program Advisory Committee Review February 2, 2004 MIT PSFC Presented by A. Hubbard MIT Plasma Science and Fusion Center, for the team Advanced
More informationDevelopment of advanced inductive scenarios for ITER
Development of advanced inductive scenarios for ITER T.C. Luce 1, C.D. Challis 2, S. Ide 3, E. Joffrin 4, Y. Kamada 3, P.A. Politzer 1, J. Schweinzer 5, A.C.C. Sips 6, J. Stober 5, G. Giruzzi 4, C.E. Kessel
More informationPower Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography
EFDA JET CP(02)01/03 T Eich, A Herrmann, P Andrew and A Loarte Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography . Power Deposition Measurements
More informationThe 2008 Public Release of the International Multi-tokamak Confinement Profile Database
The 2008 Public Release of the International Multi-tokamak Confinement Profile Database C M Roach 1, M Walters 1, R V Budny 2, F Imbeaux 3, T W Fredian 4, M Greenwald 4, J A Stillerman 4, D A Alexander
More informationEX/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 informationNIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997
NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU General Atomics Nimrod Project Review Meeting July 21 22, 1997 Work supported by the U.S. Department of Energy under Grant DE-FG03-95ER54309 and Contract
More informationImpact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas
1 P/233 Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas D. Frigione 1, M. Romanelli 2, C. Challis 2, J. Citrin 3, L. Frassinetti 4, J. Graves 5, J. Hobirk 6, F. Koechl 2, M.
More informationModelling plasma scenarios for MAST-Upgrade
Modelling plasma scenarios for MAST-Upgrade Neutral beam requirements, sensitivity studies and stability D. Keeling R. Akers, I. Chapman, G. Cunningham, H. Meyer, S. Pinches, S. Saarelma, O. Zolotukhin
More informationStudies of the Quiescent H-mode regime in ASDEX Upgrade and JET
IAEA INTERNATIONAL ATOMIC ENERGY AGENCY th IAEA Fusion Energy Conference Vilamoura, Portugal, -6 November IAEA-CN-6 / EX / - Studies of the Quiescent H-mode regime in ASDEX Upgrade and JET W. Suttrop,
More informationProgress Toward High Performance Steady-State Operation in DIII D
Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,
More informationUnderstanding physics issues of relevance to ITER
Understanding physics issues of relevance to ITER presented by P. Mantica IFP-CNR, Euratom/ENEA-CNR Association, Milano, Italy on behalf of contributors to the EFDA-JET Work Programme Brief summary of
More informationHFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION
ASDEX Upgrade Session: "Issues and prospects of effcient fueling for magnetic confinement" HFS ELLET REFUELING FOR HIGH DENSITY TOKAMAK OERATION.T. Lang for the ASDEX Upgrade and JET teams Cubic mm size
More informationLocalized Electron Cyclotron Current Drive in DIII D: Experiment and Theory
Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,
More informationImpurity transport analysis & preparation of W injection experiments on KSTAR
Impurity transport analysis & preparation of W injection experiments on KSTAR J. H. Hong, H. Y. Lee, S. H. Lee, S. Jang, J. Jang, T. Jeon, H. Lee, and W. Choe ( ) S. G. Lee, C. R. Seon, J. Kim, ( ) 마스터부제목스타일편집
More informationITER 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 informationDivertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET
Journal of Nuclear Materials 363 365 (2007) 989 993 www.elsevier.com/locate/jnucmat Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET T. Eich a, *, A.
More informationInternal Transport Barrier Triggering by Rational Magnetic Flux Surfaces in Tokamaks
EFDA JET CP(0)07/09 E. Joffrin, C.D. Challis, G.D. Conway, X. Garbet, A. Gude, S. Guenther, N. C. Hawkes, T.C. Hender, D. Howell, G.T.A. Huysmans, E. Lazarro, P. Maget, M. Marachek, A.G. Peeters, S.D.
More informationIntegrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform
EUROFUSION WPCD-PR(16) 15379 R Coelho et al. Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform Preprint of Paper to be submitted for publication
More informationEnhanced 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