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

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

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

Transcription

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

2 Physics at the periphery of a fusion plasma Toroidal limiter Limiter Core Edge SOL Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

3 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Plasma Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

4 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Parallel flow in the SOL to the limiter Plasma Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

5 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Parallel flow in the SOL to the limiter Recombination on the limiter Plasma Neutrals Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

6 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Parallel flow in the SOL to the limiter Recombination on the limiter Ionization of neutrals Ionization Density source Energy sink Plasma Neutrals Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

7 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Parallel flow in the SOL to the limiter Recombination on the limiter Ionization of neutrals Ionization Density source Energy sink Plasma Neutrals Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

8 Physics at the periphery of a fusion plasma Toroidal limiter Radial transport due to turbulence Parallel flow in the SOL to the limiter Recombination on the limiter Ionization of neutrals Ionization Recycling Density source Energy sink Plasma Neutrals Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 37

9 Movie Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 3 / 37

10 The tokamak scrape-off layer (SOL) Heat exhaust Confinement Impurities Fusion ash removal Fueling the plasma (recycling) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 4 / 37

11 1. Modeling the periphery 2. A refined two-point model with neutrals 3. Gas puff fueling simulations Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 5 / 37

12 Modeling the periphery Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

13 Modeling the periphery High plasma collisionality, local Maxwellian Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

14 Modeling the periphery High plasma collisionality, local Maxwellian d/dt ω ci,k 2 k 2 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

15 Modeling the periphery High plasma collisionality, local Maxwellian d/dt ω ci,k 2 k 2 Drift-reduced Braginskii equations n,ω,v e,v,i,t e,t i Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

16 Modeling the periphery High plasma collisionality, local Maxwellian d/dt ω ci,k 2 k 2 Drift-reduced Braginskii equations n,ω,v e,v,i,t e,t i Flux-driven, no separation between equilibrium and fluctuations Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

17 Modeling the periphery High plasma collisionality, local Maxwellian d/dt ω ci,k 2 k 2 Drift-reduced Braginskii equations n,ω,v e,v,i,t e,t i Flux-driven, no separation between equilibrium and fluctuations Kinetic neutral equation Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

18 Modeling the periphery High plasma collisionality, local Maxwellian d/dt ω ci,k 2 k 2 Drift-reduced Braginskii equations n,ω,v e,v,i,t e,t i Flux-driven, no separation between equilibrium and fluctuations Kinetic neutral equation Interplay between plasma outflow from the core, turbulent transport, sheath losses, and recycling Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 6 / 37

19 Fluid plasma model and interaction with neutrals n = ρ 1 [φ,n] + 2 t B [C(pe) nc(φ)] (nv e ) + Dn(n) + Sn+nnν iz nν rec (1) ω t v e t v i t T e t T i t = ρ 1 [φ, ω] v i ω + B2 = ρ 1 [φ,v e ] v e v e + m i m e n j + 2B n C(p) + D nn ω ( ω) n νcx ω (2) ( ν j ) n + φ 1 n pe 0.71 Te = ρ 1 [φ,v i ] v i v i 1 n p + Dv i (v nn i )+ = ρ 1 [φ,t e] v e T e + 4Te 3B [ 1 n C(pe) + 5 C(Te) C(φ) 2 + D Te (T e) + D Te (Te) + S Te + nn n ν iz ( 2 3 E iz T e + me = ρ 1 [φ,t i ] v i T i + 4T [ i 1 3B n C(pe) τ 5 ] 2 C(T i ) C(φ) + D v e (v e )+ nn n (νen + 2ν iz )(v n v e ) n (ν iz + ν cx )(v n v i ) (4) ] [ ] + 2Te n j v e (5) v m e (v e 4 i 3 v n [ + 2T i 3 + D Ti (T i ) + D T i (T i ) + S Ti + nn n (ν iz + ν cx )(T n T i (v n v i )2 ) 2 φ =ω, ρ = ρs/r, f = b 0 f, ω = ω + τ 2 T i, p = n(t e + τt i ) nn me 2 )) + νen n m i (v i v e ) n n v e 3 v e (v n v e )) ] (3) (6) + boundary conditions + kinetic neutral equation Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 7 / 37

20 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

21 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

22 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

23 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

24 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

25 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

26 The density equation n t = ρ 1 [φ,n] + 2 B [C(p e) nc(φ)] (nv e ) (7) + S n + n n ν iz nν rec + D n (n) ExB drift Curvature terms Parallel advection Plasma source from core Interaction with neutrals Perpendicular diffusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 8 / 37

27 The kinetic model of the neutrals One mono-atomic neutral species Krook operators for ionization, charge-exchange, and recombination C. Wersal and P. Ricci 2015 Nucl. Fusion Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 9 / 37

28 The neutral model f n t + v f n x = ν izf n ν cx (f n n n Φ i ) + ν rec n i Φ i (8) ν iz = n e v e σ iz (v e ), ν cx = n i v rel σ cx (v rel ) ν rec = n e v e σ rec (v e ), Φ i = f i /n i Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 10 / 37

29 The neutral model f n t + v f n x = ν izf n ν cx (f n n n Φ i ) + ν rec n i Φ i (8) ν iz = n e v e σ iz (v e ), ν cx = n i v rel σ cx (v rel ) ν rec = n e v e σ rec (v e ), Φ i = f i /n i Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 10 / 37

30 The neutral model f n t + v f n x = ν izf n ν cx (f n n n Φ i ) + ν rec n i Φ i (8) ν iz = n e v e σ iz (v e ), ν cx = n i v rel σ cx (v rel ) ν rec = n e v e σ rec (v e ), Φ i = f i /n i Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 10 / 37

31 The neutral model f n t + v f n x = ν izf n ν cx (f n n n Φ i ) + ν rec n i Φ i (8) ν iz = n e v e σ iz (v e ), ν cx = n i v rel σ cx (v rel ) ν rec = n e v e σ rec (v e ), Φ i = f i /n i Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 10 / 37

32 The neutral model f n t + v f n x = ν izf n ν cx (f n n n Φ i ) + ν rec n i Φ i (8) ν iz = n e v e σ iz (v e ), ν cx = n i v rel σ cx (v rel ) ν rec = n e v e σ rec (v e ), Boundary conditions Φ i = f i /n i (v in respect to the surface; θ between v and normal vector to the surface) dv v f n ( x w, v) + u i n i = 0 (9) f n ( x w, v) cos(θ)e mv 2 /2T w for v > 0 (10) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 10 / 37

33 Boundary conditions for the neutrals Partial reflection at the limiters Window averaged particle flux conservation at the outer boundary nn nn Z/ ρ s Z/ ρ s R/ ρ s R/ ρ s Gas puffs and neutral background Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 11 / 37

34 Further simplifications Separation of time scales The neutrals time of life is typically shorter than the turbulent time scale T e = 20eV, n 0 = cm 3 τ neutral losses ν 1 eff s τ turbulence R 0 L p /c s s Assume fn / t 0 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 12 / 37

35 Further simplifications Separation of time scales The neutrals time of life is typically shorter than the turbulent time scale T e = 20eV, n 0 = cm 3 τ neutral losses ν 1 eff s τ turbulence R 0 L p /c s s Assume fn / t 0 Plasma anitrosopy The plasma elongation along the field lines is much longer than the typical neutral mean free path Assume f n 0 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 12 / 37

36 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

37 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) v 0 x f n (x,v) (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

38 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) v 0 x f n (x,v) = x 0 dx (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

39 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) 0 x' x v f n (x,v) = x 0 dx ν cx (x )n n (x )Φ i (x,v) v (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

40 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) 0 x' x v f n (x,v) = x 0 dx ν cx (x )n n (x )Φ i (x,v) e 1 x v x dx (ν cx (x )+ν iz (x )) v (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

41 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) 0 x' x v f n (x,v) = x 0 dx ν cx (x )n n (x )Φ i (x,v) v + f w (v)e 1 v x0 dx (ν cx (x )+ν iz (x )) e v 1 x x dx (ν cx (x )+ν iz (x )) (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

42 Solution of neutral eq. with method of characteristics Example in 1D, no recombination, v > 0 and a wall at x = 0 v f n x = ν cxn n Φ i (ν iz + ν cx )f n (11) 0 x' x v f n (x,v) = x 0 dx ν cx (x )n n (x )Φ i (x,v) v + f w (v)e 1 v x0 dx (ν cx (x )+ν iz (x )) e v 1 x x dx (ν cx (x )+ν iz (x )) (12) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 13 / 37

43 An equation for the density distribution By imposing f n dv = n n (13) we get a linear integral equation for n n (x) n n (x) = x dx n n (x ) contribution by v < 0 + n w (x) dv ν cx(x )Φ i (x,v) v e d eff ν eff (x x ) v (14) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 14 / 37

44 The GBS code, a tool to simulate SOL turbulence Evolves scalar fields in 3D geometry n,ω,v e,v,i,t e,t i Kinetic neutral physics Limiter geometry Open and closed field-line region Sources S n and S T mimic plasma outflow from the core (Divertor geometry) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 15 / 37

45 Questions that we can address How is the temperature at the limiter related to main plasma parameters? How is the plasma fueled? How do neutrals affect plasma turbulence? SOL width? Heat flux? How do diagnostic gas puffs affect the SOL? Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 16 / 37

46 Questions that we can address How is the temperature at the limiter related to main plasma parameters? How is the plasma fueled? How do neutrals affect plasma turbulence? SOL width? Heat flux? How do diagnostic gas puffs affect the SOL? Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 16 / 37

47 1. Modeling the periphery 2. A refined two-point model with neutrals 3. Gas puff fueling simulations Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 17 / 37

48 The two-point model Relation between upstream and target plasma properties Limiter Target Widely used experimentally for a quick estimate Derived from 1D model along field lines Core Edge SOL Upstream Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 18 / 37

49 The SOL unrolled SOL Main Plasma Main Plasma Limiter Limiter SOL LCFS Limiter Wall Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 19 / 37

50 The SOL unrolled SOL Main Plasma Limiter Main Plasma Limiter Target Upstream SOL LCFS Target Limiter Wall Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 19 / 37

51 The SOL unrolled SOL Main Plasma Limiter Main Plasma Limiter Target s Upstream SOL LCFS Target Limiter Wall Parallel plasma dynamics projected along poloidal coordinate Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 19 / 37

52 The SOL unrolled SOL Main Plasma Main Plasma Limiter Limiter s SOL LCFS Limiter Wall Parallel plasma dynamics projected along poloidal coordinate Plasma and energy outflowing from the core are modeled with prescribed S n and S Q Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 19 / 37

53 The basic two-point model Q = S Q ds = Q cond + Q conv (15) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 20 / 37

54 The basic two-point model Q = S Q ds = Q cond + Q conv (15) Q cond = χ e0 T 5/2 dt e e dz (16) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 20 / 37

55 The basic two-point model Q = S Q ds = Q cond + Q conv (15) Q cond = χ e0 T 5/2 dt e e dz (16) Q conv = c e0 ΓT e (17) Γ = nv = S n ds (18) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 20 / 37

56 The basic two-point model Q = S Q ds = Q cond + Q conv (15) Q cond = χ e0 T 5/2 dt e e dz (16) Q conv = c e0 ΓT e (17) Γ = nv = S n ds (18) Boundary conditions Upstream: dt e /ds = 0 At the limiter: Q L = γ e Γ L T el, γ e 5 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 20 / 37

57 The basic two-point model Q = S Q ds = Q cond + Q conv (15) Q cond = χ e0 T 5/2 dt e e dz (16) Q conv = c e0 ΓT e (17) Γ = nv = S n ds (18) Boundary conditions Upstream: dt e /ds = 0 At the limiter: Q L = γ e Γ L T el, γ e 5 S Q,S n T e,u T e,t Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 20 / 37

58 Simulations with different densities n 0 = cm 3 n 0 = cm 3 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 21 / 37

59 Simulations with different densities n 0 = cm 3 n 0 = cm 3 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 22 / 37

60 Simulations with different densities n 0 = cm 3 n 0 = cm 3 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 22 / 37

61 Poloidal profiles of electron temperature n 0 = cm 3 n 0 = cm 3 Te L 0 L s Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 23 / 37

62 Poloidal profiles of electron temperature n 0 = cm 3 n 0 = cm 3 Te L 0 L s Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 23 / 37

63 Temperature ratio upstream to target 2 basic model 1.8 Te,u/Te,t (tpm) , no n n , no n n x , E iz = T e,u /T e,t (GBS) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 24 / 37

64 A more refined two-point model Obtain an electron heat equation in quasi-steady state 3 2 T n e t n T e 0 (19) t Assume v e, v i, and neglect small terms (e.g., D Te ) Combine perpendicular transport terms into S Q ( 5 2 nv T e ) χ e0 ( T 5/2 e T e ) v (nt e ) (20) = S Q + S neutrals with S neutrals = n n ν iz (T e )E iz and χ e0 = 3/2 nκ e Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 25 / 37

65 Further assumptions and relations v is linear from c s to c s c s = T e,t + T i,t 2T e,t nv = [S n + n n ν iz (T e )]ds n n is decaying exponentially from limiter with λ mfp Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 26 / 37

66 Three external input quantities Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 27 / 37

67 Three external input quantities Perpendicular heat source, S Q GBS cos fit SQ L 0 L s Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 27 / 37

68 Three external input quantities Perpendicular heat source, S Q Perpendicular particle source, S n GBS cos fit Sn L 0 L s Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 27 / 37

69 Three external input quantities Perpendicular heat source, S Q Perpendicular particle source, S n Ionization particle source, S iz Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 27 / 37

70 Three external input quantities Perpendicular heat source, S Q Perpendicular particle source, S n Ionization particle source, S iz S Q,S n,s iz T e,u T e,t Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 27 / 37

71 Temperature ratio upstream to target 2 basic model 2 full model Te,u/Te,t (tpm) , no n n , no n n x , E iz = T e,u /T e,t (GBS) Te,u/Te,t (tpm) , no n n , no n n x , E iz = T e,u /T e,t (GBS) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 28 / 37

72 Questions that we can address How is the temperature at the limiter related to main plasma parameters? How is the plasma fueled? How do neutrals affect plasma turbulence? SOL width? Heat flux? How do diagnostic gas puffs affect the SOL? Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 29 / 37

73 1. Modeling the periphery 2. A refined two-point model with neutrals 3. Gas puff fueling simulations Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 30 / 37

74 Gas puff/fueling simulations Open and closed field lines Various gas puff locations (hfs, bot, lfs, top) Small constant main wall recycling n 0 = cm 3, T 0 = 20eV, q = 3.87, ρ 1 = 500, a 0 = 200ρ s Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 31 / 37

75 Neutral density Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 32 / 37

76 Ionization Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 33 / 37

77 Radial ExB flow outward/inward flow Ballooning outward transport at the low field side Inward fueling at the high field side Robust feature independent of gas puff location Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 34 / 37

78 Questions that we can address How is the temperature at the limiter related to main plasma parameters? How is the plasma fueled? How do neutrals affect plasma turbulence? SOL width? Heat flux? How do diagnostic gas puffs affect the SOL? Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 35 / 37

79 Poloidal ExB flow Poloidal rotation due to radial electric field Shearing of the turbulent eddies Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 36 / 37

80 Conclusions Plasma turbulence at the periphery and interaction with neutrals are crucial issues on the way to fusion electricity GBS is now able to simulate this complex interplay self-consistently Development of a more refined two-point model, in agreement with GBS Initial study of plasma fueling due to ionization and radial flows, and of plasma poloidal rotation. Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 37 / 37

81 Reaction rates - Stangeby Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 1 / 4

82 Reaction rates - openadas σv (m 3 s 1 ) CX ion, n 0 =1e+18 rec, n 0 =1e+18 ion, n 0 =1e+20 rec, n 0 =1e T e,t i (ev) Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 2 / 4

83 Timescales T 0 (ev) n 0 (m 3 ) τ turbulence (s) τ nnloss (s) λ mfp (m) 1 1e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e e-05 Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 3 / 4

84 The model in steady state Steady state, f n t = 0, first approach Valid if τ neutral losses < τ turbulence e.g. T e = 20eV, n 0 = m 3 τ neutral losses ν 1 eff s τ turbulence R 0 L p /c s s Otherwise: time dependent model Christoph Wersal - SPC Neutrals in the turbulent tokamak edge 4 / 4

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

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

More information

A comparison between a refined two-point model for the limited tokamak SOL and self-consistent plasma turbulence simulations

A comparison between a refined two-point model for the limited tokamak SOL and self-consistent plasma turbulence simulations EUROFUSION WP15ER-PR(16) 16618 C. Wersal et al. A comparison between a refined two-point model for the limited tokamak SOL and self-consistent plasma turbulence simulations Preprint of Paper to be submitted

More information

Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations*

Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations* Modeling neutral-plasma interactions in scrape-off layer (SOLT) simulations* D. A. Russell and J. R. Myra Research Corporation Boulder CO USA Presented at the US Transport Task Force Workshop Williamsburg

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

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

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

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

More information

Verification & Validation: application to the TORPEX basic plasma physics experiment

Verification & Validation: application to the TORPEX basic plasma physics experiment Verification & Validation: application to the TORPEX basic plasma physics experiment Paolo Ricci F. Avino, A. Bovet, A. Fasoli, I. Furno, S. Jolliet, F. Halpern, J. Loizu, A. Mosetto, F. Riva, C. Theiler,

More information

Modelling of plasma edge turbulence with neutrals

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

More information

L-H transitions driven by ion heating in scrape-off layer turbulence (SOLT) model simulations

L-H transitions driven by ion heating in scrape-off layer turbulence (SOLT) model simulations L-H transitions driven by ion heating in scrape-off layer turbulence (SOLT) model simulations D.A. Russell, D.A. D Ippolito and J.R. Myra Research Corporation, Boulder, CO, USA Presented at the 015 Joint

More information

A first-principles self-consistent model of plasma turbulence and kinetic neutral dynamics in the tokamak scrape-off layer

A first-principles self-consistent model of plasma turbulence and kinetic neutral dynamics in the tokamak scrape-off layer A first-principles self-consistent model of plasma turbulence and kinetic neutral dynamics in the tokamak scrape-off layer C Wersal and P Ricci Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma

More information

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

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

More information

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

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

More information

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas Lei Qi a, Jaemin Kwon a, T. S. Hahm a,b and Sumin Yi a a National Fusion Research Institute (NFRI), Daejeon,

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

The Levitated Dipole Experiment: Towards Fusion Without Tritium

The Levitated Dipole Experiment: Towards Fusion Without Tritium The Levitated Dipole Experiment: Towards Fusion Without Tritium Jay Kesner MIT M.S. Davis, J.E. Ellsworth, D.T. Garnier, M.E. Mauel, P.C. Michael, P.P. Woskov MCP I3.110 Presented at the EPS Meeting, Dublin,

More information

TURBULENT TRANSPORT THEORY

TURBULENT TRANSPORT THEORY ASDEX Upgrade Max-Planck-Institut für Plasmaphysik TURBULENT TRANSPORT THEORY C. Angioni GYRO, J. Candy and R.E. Waltz, GA The problem of Transport Transport is the physics subject which studies the physical

More information

On the locality of parallel transport of heat carrying electrons in the SOL

On the locality of parallel transport of heat carrying electrons in the SOL P1-068 On the locality of parallel transport of heat carrying electrons in the SOL A.V. Chankin* and D.P. Coster Max-Planck-Institut für Pasmaphysik, 85748 Garching, Germany Abstract A continuum Vlasov-Fokker-Planck

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

Kinetic theory of ions in the magnetic presheath

Kinetic theory of ions in the magnetic presheath Kinetic theory of ions in the magnetic presheath Alessandro Geraldini 1,2, Felix I. Parra 1,2, Fulvio Militello 2 1. Rudolf Peierls Centre for Theoretical Physics, University of Oxford, Oxford, Oxford

More information

Predicting the Rotation Profile in ITER

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

More information

Fluid Neutral Momentum Transport Reference Problem D. P. Stotler, PPPL S. I. Krasheninnikov, UCSD

Fluid Neutral Momentum Transport Reference Problem D. P. Stotler, PPPL S. I. Krasheninnikov, UCSD Fluid Neutral Momentum Transport Reference Problem D. P. Stotler, PPPL S. I. Krasheninnikov, UCSD 1 Summary Type of problem: kinetic or fluid neutral transport Physics or algorithm stressed: thermal force

More information

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

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

More information

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

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

More information

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

Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod

Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod I. Cziegler J.L. Terry, B. LaBombard, J.W. Hughes MIT - Plasma Science and Fusion Center th 19 Plasma

More information

Intrinsic rotation due to non- Maxwellian equilibria in tokamak plasmas. Jungpyo (J.P.) Lee (Part 1) Michael Barnes (Part 2) Felix I.

Intrinsic rotation due to non- Maxwellian equilibria in tokamak plasmas. Jungpyo (J.P.) Lee (Part 1) Michael Barnes (Part 2) Felix I. Intrinsic rotation due to non- Maxwellian equilibria in tokamak plasmas Jungpyo (J.P.) Lee (Part 1) Michael Barnes (Part 2) Felix I. Parra MIT Plasma Science & Fusion Center. 1 Outlines Introduction to

More information

Simple examples of MHD equilibria

Simple examples of MHD equilibria Department of Physics Seminar. grade: Nuclear engineering Simple examples of MHD equilibria Author: Ingrid Vavtar Mentor: prof. ddr. Tomaž Gyergyek Ljubljana, 017 Summary: In this seminar paper I will

More information

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma 1 Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma D. Galassi, P. Tamain, H. Bufferand, C. Baudoin, G. Ciraolo, N. Fedorczak, Ph.

More information

Gyrokinetic Theory and Dynamics of the Tokamak Edge

Gyrokinetic Theory and Dynamics of the Tokamak Edge ASDEX Upgrade Gyrokinetic Theory and Dynamics of the Tokamak Edge B. Scott Max Planck Institut für Plasmaphysik D-85748 Garching, Germany PET-15, Sep 2015 these slides: basic processes in the dynamics

More information

Inter-linkage of transports and its bridging mechanism

Inter-linkage of transports and its bridging mechanism Interlinkage of transports and its bridging mechanism Katsumi Ida National Institute for Fusion Science 17 th International Toki Conference 1519 October 27, Toki OUTLINE 1 Introduction 2 particle pinch

More information

Effect of Neutrals on Scrape-Off-Layer and Divertor Stability in Tokamaks

Effect of Neutrals on Scrape-Off-Layer and Divertor Stability in Tokamaks Effect of Neutrals on Scrape-Off-Layer and Divertor Stability in Tokamaks D. A. D Ippolito and J. R. Myra Lodestar Research Corporation, 2400 Central Avenue, Boulder, Colorado 80301 Abstract The influence

More information

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

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

More information

The physics of the heat flux narrow decay length in the TCV scrape-off layer: experiments and simulations

The physics of the heat flux narrow decay length in the TCV scrape-off layer: experiments and simulations EUROFUSION WPMST1-CP(16) 15302 B Labit et al. The physics of the heat flux narrow decay length in the TCV scrape-off layer: experiments and simulations Preprint of Paper to be submitted for publication

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

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

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

More information

Neoclassical transport

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

More information

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

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

More information

Total Flow Vector in the C-Mod SOL

Total Flow Vector in the C-Mod SOL Total Flow Vector in the SOL N. Smick, B. LaBombard MIT Plasma Science and Fusion Center APS-DPP Annual Meeting Atlanta, GA November 3, 2009 Motivation and Goals Measurements have revealed high parallel

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

Physics of the detached radiative divertor regime in DIII-D

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

More information

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

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

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

More information

0 Magnetically Confined Plasma

0 Magnetically Confined Plasma 0 Magnetically Confined Plasma 0.1 Particle Motion in Prescribed Fields The equation of motion for species s (= e, i) is written as d v ( s m s dt = q s E + vs B). The motion in a constant magnetic field

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

Low Temperature Plasma Technology Laboratory

Low Temperature Plasma Technology Laboratory Low Temperature Plasma Technology Laboratory CENTRAL PEAKING OF MAGNETIZED GAS DISCHARGES Francis F. Chen and Davide Curreli LTP-1210 Oct. 2012 Electrical Engineering Department Los Angeles, California

More information

14. Energy transport.

14. Energy transport. Phys780: Plasma Physics Lecture 14. Energy transport. 1 14. Energy transport. Chapman-Enskog theory. ([8], p.51-75) We derive macroscopic properties of plasma by calculating moments of the kinetic equation

More information

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices Michael Tendler, Alfven Laboratory, Royal Institute of Technology, Stockholm, Sweden Plasma Turbulence Turbulence can be regarded

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

INTRODUCTION TO GYROKINETIC AND FLUID SIMULATIONS OF PLASMA TURBULENCE AND OPPORTUNITES FOR ADVANCED FUSION SIMULATIONS

INTRODUCTION TO GYROKINETIC AND FLUID SIMULATIONS OF PLASMA TURBULENCE AND OPPORTUNITES FOR ADVANCED FUSION SIMULATIONS INTRODUCTION TO GYROKINETIC AND FLUID SIMULATIONS OF PLASMA TURBULENCE AND OPPORTUNITES FOR ADVANCED FUSION SIMULATIONS G.W. Hammett, Princeton Plasma Physics Lab w3.pppl.gov/ hammett Fusion Simulation

More information

Turbulence and Transport The Secrets of Magnetic Confinement

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

More information

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

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

More information

Progress in Turbulence Modeling JET SOL and edge phenomena

Progress in Turbulence Modeling JET SOL and edge phenomena 1 Progress in Turbulence Modeling JET SOL and edge phenomena V. Naulin 1, W. Fundamenski 2, E. Havlíčková 2, Chr. Maszl 3, G. Xu 4, A.H. Nielsen 1, J. Juul Rasmussen 1, R. Schrittwieser 3, J. Horacek 5,

More information

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

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

More information

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

Erosion and Confinement of Tungsten in ASDEX Upgrade

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

More information

Stability of a plasma confined in a dipole field

Stability of a plasma confined in a dipole field PHYSICS OF PLASMAS VOLUME 5, NUMBER 10 OCTOBER 1998 Stability of a plasma confined in a dipole field Plasma Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 Received

More information

Simulation of Plasma Blobs in Realistic Tokamak Geometry

Simulation of Plasma Blobs in Realistic Tokamak Geometry Simulation of Plasma Blobs in Realistic Tokamak Geometry Rogério Jorge rogerio.jorge@tecnico.ulisboa.pt Instituto Superior Técnico, Lisboa, Portugal October 4 Abstract Understanding Scrape-off Layer (SOL)

More information

Divertor Plasma Detachment

Divertor Plasma Detachment Divertor Plasma Detachment S. I. Krasheninnikov 1, A. S. Kukushkin 2,3 and A. A. Pshenov 2,3 1 University California San Diego, 9500 Gilman Drive, La Jolla, CA 92093-0411, USA 2 National Research Nuclear

More information

Toroidal confinement devices

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

More information

Theory Work in Support of C-Mod

Theory Work in Support of C-Mod Theory Work in Support of C-Mod 2/23/04 C-Mod PAC Presentation Peter J. Catto for the PSFC theory group MC & LH studies ITB investigations Neutrals & rotation BOUT improvements TORIC ICRF Mode Conversion

More information

Fundamentals of Plasma Physics Transport in weakly ionized plasmas

Fundamentals of Plasma Physics Transport in weakly ionized plasmas Fundamentals of Plasma Physics Transport in weakly ionized plasmas APPLAuSE Instituto Superior Técnico Instituto de Plasmas e Fusão Nuclear Luís L Alves (based on Vasco Guerra s original slides) 1 As perguntas

More information

Plasma Science and Fusion Center

Plasma Science and Fusion Center Plasma Science and Fusion Center Turbulence and transport studies in ALCATOR C Mod using Phase Contrast Imaging (PCI) Diagnos@cs and Comparison with TRANSP and Nonlinear Global GYRO Miklos Porkolab (in

More information

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

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

More information

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

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

More information

Flow and dynamo measurements in the HIST double pulsing CHI experiment

Flow and dynamo measurements in the HIST double pulsing CHI experiment Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.

More information

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS Presented by D.P. SCHISSEL Presented to APS Centennial Meeting March 20 26, 1999 Atlanta, Georgia

More information

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks

ArbiTER studies of filamentary structures in the SOL of spherical tokamaks ArbiTER studies of filamentary structures in the SOL of spherical tokamaks D. A. Baver, J. R. Myra, Research Corporation F. Scotti, Lawrence Livermore National Laboratory S. J. Zweben, Princeton Plasma

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

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

Bursty Transport in Tokamaks with Internal Transport Barriers

Bursty Transport in Tokamaks with Internal Transport Barriers Bursty Transport in Tokamaks with Internal Transport Barriers S. Benkadda 1), O. Agullo 1), P. Beyer 1), N. Bian 1), P. H. Diamond 3), C. Figarella 1), X. Garbet 2), P. Ghendrih 2), V. Grandgirard 1),

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

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

Turbulence in Tokamak Plasmas

Turbulence in Tokamak Plasmas ASDEX Upgrade Turbulence in Tokamak Plasmas basic properties and typical results B. Scott Max Planck Institut für Plasmaphysik Euratom Association D-85748 Garching, Germany Uni Innsbruck, Nov 2011 Basics

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK

More information

Magnetized ion collection by oblique surfaces including self-consistent drifts: Mach-probes of arbitrary shape.

Magnetized ion collection by oblique surfaces including self-consistent drifts: Mach-probes of arbitrary shape. 1 Magnetized ion collection by oblique surfaces including self-consistent drifts: Mach-probes of arbitrary shape I H Hutchinson Plasma Science and Fusion Center and and Engineering Department MIT APS DPP

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

12. MHD Approximation.

12. MHD Approximation. Phys780: Plasma Physics Lecture 12. MHD approximation. 1 12. MHD Approximation. ([3], p. 169-183) The kinetic equation for the distribution function f( v, r, t) provides the most complete and universal

More information

Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma

Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma Transport and drift-driven plasma flow components in the Alcator C-Mod boundary plasma The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters.

More information

Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal

Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal W. M. Stacey Fusion Research Center, Georgia Institute of Technology, Atlanta, GA, USA Email: weston.stacey@nre.gatech.edu Abstract

More information

Magnetically Confined Fusion: Transport in the core and in the Scrape- off Layer Bogdan Hnat

Magnetically Confined Fusion: Transport in the core and in the Scrape- off Layer Bogdan Hnat Magnetically Confined Fusion: Transport in the core and in the Scrape- off Layer ogdan Hnat Joe Dewhurst, David Higgins, Steve Gallagher, James Robinson and Paula Copil Fusion Reaction H + 3 H 4 He + n

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

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

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

More information

Neutral gas modelling

Neutral gas modelling Neutral gas modelling Ben Dudson 1 1 York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK BOUT++ Workshop 16 th September 2014 Ben Dudson, University of York

More information

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a)

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 Chang, C.S., 1 Ku, S., 2 Adams M., 3 D Azevedo, G., 4 Chen, Y., 5 Cummings,

More information

Mean-field and turbulent transport in divertor geometry Davide Galassi

Mean-field and turbulent transport in divertor geometry Davide Galassi Mean-field and turbulent transport in divertor geometry Davide Galassi In collaboration with: Ph. Ghendrih, P. Tamain, C. Baudoin, H. Bufferand, G. Ciraolo, C. Colin and E. Serre Our goal: quantify turbulence

More information

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison Heat Transport in a Stochastic Magnetic Field John Sarff Physics Dept, UW-Madison CMPD & CMSO Winter School UCLA Jan 5-10, 2009 Magnetic perturbations can destroy the nested-surface topology desired for

More information

A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows *

A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows * A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows * Bruce I. Cohen, Maxim V. Umansky, Ilon Joseph Lawrence Livermore National Laboratory

More information

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

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

More information

Recent Theoretical Progress in Understanding Coherent Structures in Edge and SOL Turbulence

Recent Theoretical Progress in Understanding Coherent Structures in Edge and SOL Turbulence Recent Theoretical Progress in Understanding Coherent Structures in Edge and SOL Turbulence S. I. Krasheninnikov University of California, San Diego, California D. A. D Ippolito and J. R. Myra Lodestar

More information

Interaction between plasma and neutrals near the divertor : the effect of particle and energy reflection

Interaction between plasma and neutrals near the divertor : the effect of particle and energy reflection Eindhoven University of Technology MASTER Interaction between plasma and neutrals near the divertor : the effect of particle and energy reflection Minea, T. Award date: 23 Link to publication Disclaimer

More information

A.G. PEETERS UNIVERSITY OF BAYREUTH

A.G. PEETERS UNIVERSITY OF BAYREUTH IN MEMORIAM GRIGORY PEREVERZEV A.G. PEETERS UNIVERSITY OF BAYREUTH ESF Workshop (Garching 2013) Research areas Grigory Pereverzev. Current drive in magnetized plasmas Transport (ASTRA transport code) Wave

More information

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University

More information

Non-Solenoidal Plasma Startup in

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

More information

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT PROGRAM C-Mod C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER C-MOD - OPPORTUNITIES AND CHALLENGES Prediction and control are the ultimate goals

More information

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

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

More information

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

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

Blob motion and control. simple magnetized plasmas

Blob motion and control. simple magnetized plasmas Blob motion and control in simple magnetized plasmas Christian Theiler A. Fasoli, I. Furno, D. Iraji, B. Labit, P. Ricci, M. Spolaore 1, N. Vianello 1 Centre de Recherches en Physique des Plasmas (CRPP)

More information

Impurity expulsion in an RFP plasma and the role of temperature screening

Impurity expulsion in an RFP plasma and the role of temperature screening Impurity expulsion in an RFP plasma and the role of temperature screening S. T. A. Kumar, D. J. Den Hartog, R. M. Magee, G. Fiksel, D. Craig Department of Physics, University of Wisconsin-Madison, Madison,Wisconsin,

More information

Blob sizes and velocities in the Alcator C-Mod scrapeoff

Blob sizes and velocities in the Alcator C-Mod scrapeoff P1-59 Blob sizes and velocities in the Alcator C-Mod scrapeoff layer R. Kube a,b,*, O. E. Garcia a,b, B. LaBombard b, J. L. Terry b, S. J. Zweben c a Department of Physics and Technology, University of

More information