Flow, current, & electric field in omnigenous stellarators
|
|
- Loren Miller
- 5 years ago
- Views:
Transcription
1 Flow, current, & electric field in omnigenous stellarators Supported by U.S. D.o.E. Matt Landreman with Peter J Catto MIT Plasma Science & Fusion Center Oral 2O4 Sherwood Fusion Theory Meeting Tuesday May 3, 2011
2 Preview W7-X can be and any reactor must be nearly omnigenous. Omnigenous stellarators: More general than quasisymmetric devices. B has nice properties. Formulae for current & flow simplify dramatically. Universal radial electric field. Landreman and Catto, PPCF 53, (2011).
3 Omnigenity = no unconfined orbits. Tokamak Stellarator Flux surface B B Trapped particle Unconfined α particles can damage plasma-facing components.
4 Omnigenity = no unconfined orbits. Tokamak Stellarator Flux surface B B Trapped particle For a reactor, then, a stellarator must be nearly omnigenous: 0 =Δψ per bounce = ( v ) d ψ dt for all μ. bounce Unconfined α particles can damage plasma-facing components.
5 Omnigenity = no unconfined orbits. Tokamak Stellarator Flux surface For a reactor, then, a stellarator must be nearly omnigenous: 0 =Δψ per bounce = ( v ) d ψ dt for all μ. Equivalent definition: J is a flux function, where J B B Trapped particle = υ d is the longitudinal invariant. bounce Unconfined α particles can damage plasma-facing components.
6 Omnigenity = no unconfined orbits. Tokamak Stellarator Flux surface B B Trapped particle For a reactor, then, a stellarator must be nearly omnigenous: 0 =Δψ per bounce = ( v ) d ψ dt for all μ. bounce Unconfined α particles can damage plasma-facing components. Equivalent definition: J is a flux function, where J = υ d is the longitudinal invariant. J contours for W7-X ( ψ θ) in, polar coordinates
7 If Omnigenity places strong constraints on B. ( d ψ ) v dt = 0, then All B contours link the torus toroidally, poloidally, or both. 2π 2π poloidal angle θ poloidal angle θ θ B 0 0 toroidal angle ζ 2π/ π/5 2π/N ζ toroidal angle ζ 0.9
8 If Omnigenity places strong constraints on B. ( d ψ ) v dt = 0, then All B contours link the torus toroidally, poloidally, or both. 2π 2π poloidal angle θ poloidal angle θ θ Field line B 0 0 toroidal angle ζ 2π/ π/5 2π/N ζ toroidal angle ζ 0.9 Each maximum & minimum of B along a field line is the same: B max B min
9 One way to achieve omnigenity is quasisymmetry. Quasisymmetry: B = B(ψ, Mθ -Nζ). Ignorable coordinate in the guiding-center Lagrangian Tokamak-like trajectories.
10 One way to achieve omnigenity is quasisymmetry. Quasisymmetry: B = B(ψ, Mθ -Nζ). Ignorable coordinate in the guiding-center Lagrangian Tokamak-like trajectories. Neoclassical formulae simplify dramatically. Explicit non-numerical forms possible: i e e i Quasisymmetry: jb 4.8 q dp dp 0.74n dt e 1.17 dt MG+ NI = ε + ne dψ dψ dψ dψ M qn Pytte & Boozer PoF (1981), Boozer PoF (1983) i e e i Tokamak: jb 4.8 q dp dp 0.74n dt e 1.17 dt = ε + ne G dψ dψ dψ dψ where ( ) G ψ = poloidal current outside the flux surface, G ( ψ ) ( ) toroidal current I ψ = inside the flux surface I ( ψ )
11 Omnigenity is more general than quasisymmetry. Cary & Shasharina, PoP (1997), PRL (1997) All toroidal fields Omnigenous Quasisymmetric Axisymmetric LHD TJ-II W7-X HSX NCSX tokamaks Omnigenity: B contours may be curved 2π Quasisymmetry: B contours must be straight 2π 2π poloidal angle θ θ B poloidal angle θ θ θ B π/5 2π/N ζ toroidal angle ζ π/N 0 ζ 2π/5 toroidal angle ζ 0.9
12 Omnigenity is more general than quasisymmetry. Cary & Shasharina, PoP (1997), PRL (1997) All toroidal fields Omnigenous Quasisymmetric Axisymmetric LHD TJ-II W7-X HSX NCSX tokamaks Quasisymmetry is more restrictive than omnigenity and does no more to reduce α-particle loss or neoclassical transport.
13 Omnigenity is more general than quasisymmetry. Cary & Shasharina, PoP (1997), PRL (1997) All toroidal fields Omnigenous Quasisymmetric Axisymmetric LHD TJ-II W7-X HSX NCSX tokamaks Quasisymmetry is more restrictive than omnigenity and does no more to reduce α-particle loss or neoclassical transport. Quasisymmetric fields may have reduced instability & turbulent transport: Flow speeds comparable to υ th,i are only permitted in quasisymmetric fields. (Helander, PoP 2007) Flows are clamped to a weakly sheared neoclassical value except in quasisymmetry, so quasisymmetric fields permit larger flow shear. (Helander & Simakov, PRL 2008)
14 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both.
15 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both. Define M and N: B contours close after linking the torus M times toroidally and N times poloidally.
16 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both. Define M and N: B contours close after linking the torus M times toroidally and N times poloidally. In the quasisymmetric limit, then B = B(ψ, Mθ Nζ).
17 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both. Define M and N: B contours close after linking the torus M times toroidally and N times poloidally. In the quasisymmetric limit, then B = B(ψ, Mθ Nζ). e.g. HSX: M = 1, N = 4 2π θ B (T) 0 0 ζ 2π 0.9
18 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both. Define M and N: B contours close after linking the torus M times toroidally and N times poloidally. In the quasisymmetric limit, then B = B(ψ, Mθ Nζ). e.g. HSX: M = 1, N = 4 2π θ B (T) New geometric consequence of omnigenity: By applying Ampère s Law to a B contour on a flux surface, 0 0 ζ 2π 4π B d r = c MG+ NI ( enclosed current) 0.9
19 The quasisymmetry helicity (M, N ) can be generalized to omnigenity. Recall: all B contours encircle the torus poloidally, toroidally, or both. Define M and N: B contours close after linking the torus M times toroidally and N times poloidally. In the quasisymmetric limit, then B = B(ψ, Mθ Nζ). e.g. HSX: M = 1, N = 4 2π θ B (T) New geometric consequence of omnigenity: 4π d = ( enclosed current) By applying Ampère s Law to a B contour on a flux surface, 0 0 ζ 2π B r c MG+ NI B ψ B 2q MG+ NI + H = where H = 0. B B c M qn 0.9
20 Current in an omnigenous plasma is described by a concise, explicit, analytical formula. fqb t NI + MG dpe dpi dte dti j = ne ne B qn M dψ dψ dψ dψ 2 2q dpe dpi B + 1 ( NI MG) + W + + B( qn M) dψ dψ 2 B ( ) ( ) Tokamak result with G NI + MG / qn M W 2 2B = qg + I q ( ) ζ dζ B B N M B θ ζ I ( ψ ) G( ψ ) and are the toroidal & poloidal currents. G ( ψ ) W = 0 I ( ψ )
21 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009).
22 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current inside a flux surface ψ 2 ( ψ ) = d = I j r.
23 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B jb
24 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( NI MG) From last page: j B +. jb
25 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). So if B contours close poloidally ( M = 0) rather than toroidally or helically, di = dψ Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( )... I. ( NI MG) From last page: j B +. jb
26 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( NI MG) From last page: j B +. So if B contours close poloidally ( M di = (...) I. dψ = jb 0) rather than toroidally or helically, Boundary condition: I ( ψ = 0) = 0.
27 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( NI MG) From last page: j B +. So if B contours close poloidally ( M di = (...) I. dψ = jb 0) rather than toroidally or helically, Boundary condition: I ( ψ = 0) = 0. ( ψ ) Self-consistent current profile is I = 0 with j B = 0.
28 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( NI MG) From last page: j B +. So if B contours close poloidally ( M di = (...) I. dψ = jb 0) rather than toroidally or helically, Boundary condition: I ( ψ = 0) = 0. ( ψ ) Self-consistent current profile is I = 0 with j B = 0. If bootstrap current isn t needed to make rotational transform, minimize it: Reduce drive for instabilities Maintain optimization as pressure is varied.
29 Bootstrap j can vanish if M = 0. Subbotin et al, NF 46, 921 (2006), Helander & Nührenberg, PPCF 51, (2009). Toroidal current ψ 2 = I( ψ ) =. inside a flux surface j d r di 4π I dp 2π dψ = 2 d 2 B ψ + B ( NI MG) From last page: j B +. So if B contours close poloidally ( M di = (...) I. dψ = jb 0) rather than toroidally or helically, Boundary condition: I ( ψ = 0) = 0. ( ψ ) Self-consistent current profile is I = 0 with j B = 0. If bootstrap current isn t needed to make rotational transform, minimize it: Reduce drive for instabilities Maintain optimization as pressure is varied. ( = ) B contours should close poloidally M 0 to minimize j B.
30 Flow in an omnigenous plasma is described by a concise, explicit, analytical formula. V i 2 ( ) ( ) ( + W ) ( ) 2qB dti NI + MG 2q dφ 1 dpi NI + MG = e B dψ qn M B dψ en dψ qn M ( ) ( ) Tokamak result with G NI + MG / qn M W 2 2B = qg + I q ( ) ζ dζ B B N M B θ ζ I ( ψ ) G( ψ ) and are the toroidal & poloidal currents. G ( ψ ) W = 0 I ( ψ )
31 E r is determined by ambipolarity. Non-quasisymmetric stellarators: Neoclassical radial current depends on E r. j neoclassical ψ j turbulence ψ. (Helander & Simakov, Contrib. Plasma Phys. 2010) You can solve for E r using j neoclassical ψ = 0.
32 E r is determined by ambipolarity. Non-quasisymmetric stellarators: Neoclassical radial current depends on E r. j neoclassical ψ j turbulence ψ. (Helander & Simakov, Contrib. Plasma Phys. 2010) You can solve for E r using j neoclassical ψ = 0. Tokamaks & quasisymmetric stellarators: Radial fluxes of ions and electrons are always equal, regardless of E r ( intrinsic ambipolarity ) (Helander & Simakov, PRL 2008) You cannot solve for E r.
33 E r is determined by ambipolarity. Non-quasisymmetric stellarators: Neoclassical radial current depends on E r. j neoclassical ψ j turbulence ψ. (Helander & Simakov, Contrib. Plasma Phys. 2010) You can solve for E r using j neoclassical ψ = 0. Omnigenous stellarators: dφ dni dti j ψ = Zeni + Ti 0.17ni departure from quasisymmetry dψ dψ dψ ( ) 2
34 E r is determined by ambipolarity. Non-quasisymmetric stellarators: Neoclassical radial current depends on E r. j neoclassical ψ j turbulence ψ. (Helander & Simakov, Contrib. Plasma Phys. 2010) You can solve for E r using j neoclassical ψ = 0. Omnigenous stellarators: dφ dni dti j ψ = Zeni + Ti 0.17ni departure from quasisymmetry dψ dψ dψ Universal result: dφ 1 Ti dni dti = dψ Ze ni dψ dψ ( ) 2 Totally independent of the details of B.
35 Summary: omnigenity is a useful limit. More general than quasisymmetry. Relevant (at least for insight and code benchmarking) to W7-X and to any reactor. Concise, explicit, analytical formulae for j, V, and E r. Poloidally closed B contours zero bootstrap current. For non-quasisymmetric B, E r is determined explicitly: dφ 1 Ti dni dti = independent of the B geometry. dψ Ze ni dψ dψ Landreman and Catto, PPCF 53, (2011).
Per Helander. Contributions from: R. Kleiber, A. Mishchenko, J. Nührenberg, P. Xanthopoulos. Wendelsteinstraße 1, Greifswald
Rotation and zonal flows in stellarators Per Helander Wendelsteinstraße 1, 17491 Greifswald Contributions from: R. Kleiber, A. Mishchenko, J. Nührenberg, P. Xanthopoulos What is a stellarator? In a tokamak
More informationStellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK
Stellarators Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 6 th February 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously... Toroidal devices
More informationImpurities in stellarators
Impurities in stellarators Matt Landreman, University of Maryland The problem HDH mode & impurity hole Some recent developments Strawman research program: What can we do? In stellarators, like in tokamaks,
More informationInnovative Concepts Workshop Austin, Texas February 13-15, 2006
Don Spong Oak Ridge National Laboratory Acknowledgements: Jeff Harris, Hideo Sugama, Shin Nishimura, Andrew Ware, Steve Hirshman, Wayne Houlberg, Jim Lyon Innovative Concepts Workshop Austin, Texas February
More informationAdvances in stellarator gyrokinetics
Advances in stellarator gyrokinetics Per Helander and T. Bird, F. Jenko, R. Kleiber, G.G. Plunk, J.H.E. Proll, J. Riemann, P. Xanthopoulos 1 Background Wendelstein 7-X will start experiments in 2015 optimised
More information22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer)
22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer) 1. In todays lecture we discuss the basic ideas behind the main alternate concepts to the tokamak.
More informationMHD. Jeff Freidberg MIT
MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium
More informationNumerical calculation of the Hamada basis vectors for three-dimensional toroidal magnetic configurations
PHYSICS OF PLASMAS 12, 072513 2005 Numerical calculation of the Hamada basis vectors for three-dimensional toroidal magnetic configurations J. N. Talmadge and S. P. Gerhardt a HSX Plasma Laboratory, University
More informationTheory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus. K. C. Shaing
Theory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus K. C. Shaing Plasma and Space Science Center, and ISAPS, National Cheng Kung University, Tainan, Taiwan 70101, Republic
More informationMicroturbulence in optimised stellarators
Q Josefine H. E. Proll, Benjamin J. Faber, Per Helander, Samuel A. Lazerson, Harry Mynick, and Pavlos Xanthopoulos Many thanks to: T. M. Bird, J. W. Connor, T. Go rler, W. Guttenfelder, G.W. Hammett, F.
More informationFinite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena
1 TH/P2-18 Finite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena S. Satake 1), M. Okamoto 1), N. Nakajima 1), H. Sugama 1), M. Yokoyama 1), and C. D. Beidler 2) 1)
More informationShear Flow Generation in Stellarators - Configurational Variations
Shear Flow Generation in Stellarators - Configurational Variations D. A. Spong 1), A. S. Ware 2), S. P. Hirshman 1), J. H. Harris 1), L. A. Berry 1) 1) Oak Ridge National Laboratory, Oak Ridge, Tennessee
More informationNew Schemes for Confinement of Fusion Products in Stellarators
New Schemes for Confinement of Fusion Products in Stellarators W.A. Cooper ), M.Yu. Isaev 1), M.F. Heyn 5), V.N. Kalyuzhnyj 3), S.V. Kasilov 3), W. Kernbichler 5), A.Yu. Kuyanov 1), M.I. Mikhailov 1),
More informationIntroduction to Nuclear Fusion. Prof. Dr. Yong-Su Na
Introduction to Nuclear Fusion Prof. Dr. Yong-Su Na What is a stellarator? M. Otthe, Stellarator: Experiments, IPP Summer School (2008) 2 Closed Magnetic System ion +++ ExB drift Electric field, E - -
More informationFrom tokamaks to stellarators: understanding the role of 3D shaping
Under consideration for publication in J. Plasma Phys. From tokamaks to stellarators: understanding the role of 3D shaping Samuel A. Lazerson and John C. Schmitt 2 Princeton Plasma Physics Laboratory,
More informationEdge 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 informationIon plateau transport near the tokamak magnetic axis. Abstract
Ion plateau transport near the tokamak magnetic axis K.C. Shaing and R.D. Hazeltine Institute for Fusion Studies, The University of Texas at Austin, Austin, Texas 78712 (December 2, 1997) Abstract Conventional
More informationConfiguration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift )
Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift ) Shoichi OKAMURA 1,2) 1) National Institute for Fusion Science, Toki 509-5292, Japan 2) Department of Fusion Science,
More informationW.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA
INTRINSICALLY STEADY STATE TOKAMAKS K.C. SHAING, A.Y. AYDEMIR, R.D. HAZELTINE Institute for Fusion Studies, The University of Texas at Austin, Austin TX 78712 USA W.A. HOULBERG Oak Ridge National Lab.,
More informationToroidal 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 informationNeoclassical 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 informationBounce-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 informationBRIEF COMMUNICATION. Near-magnetic-axis Geometry of a Closely Quasi-Isodynamic Stellarator. Greifswald, Wendelsteinstr. 1, Greifswald, Germany
BRIEF COMMUNICATION Near-magnetic-axis Geometry of a Closely Quasi-Isodynamic Stellarator M.I. Mikhailov a, J. Nührenberg b, R. Zille b a Russian Research Centre Kurchatov Institute, Moscow,Russia b Max-Planck-Institut
More informationThe RFP: Plasma Confinement with a Reversed Twist
The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of Wisconsin-Madison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed
More informationPhysics Considerations in the Design of NCSX *
1 IAEA-CN-94/IC-1 Physics Considerations in the Design of NCSX * G. H. Neilson 1, M. C. Zarnstorff 1, L. P. Ku 1, E. A. Lazarus 2, P. K. Mioduszewski 2, W. A. Cooper 3, M. Fenstermacher 4, E. Fredrickson
More informationStellarators and the path from ITER to DEMO
Stellarators and the path from ITER to DEMO Allen H. Boozer Department of Applied Physics and Applied Mathematics Columbia University, New York, NY 10027 (Dated: May 26, 2008) A demonstration of fusion
More information3D toroidal physics: testing the boundaries of symmetry breaking
3D toroidal physics: testing the boundaries of symmetry breaking Donald A. Spong Oak Ridge National Laboratory Abstract - Toroidal symmetry is an important concept for plasma confinement; it allows the
More informationExploration of Configurational Space for Quasi-isodynamic Stellarators with Poloidally Closed Contours of the Magnetic Field Strength
Exploration of Configurational Space for Quasi-isodynamic Stellarators with Poloidally Closed Contours of the Magnetic Field Strength V.R. Bovshuk 1, W.A. Cooper 2, M.I. Mikhailov 1, J. Nührenberg 3, V.D.
More informationDer Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk
Max-Planck-Institut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator
More informationDT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )
DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) Tsuguhiro WATANABE National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan (Received
More informationGyrokinetic Turbulence in Tokamaks and Stellarators
Gyrokinetic Turbulence in Tokamaks and Stellarators Frank Jenko IPP, Germany Acknowledgements: P. Xanthopoulos, F. Merz, T. Görler, M. Pueschel, D. Told; A. Boozer, G. Hammett, D. Mikkelsen, M. Zarnstorff,
More informationMechanisms of intrinsic toroidal rotation tested against ASDEX Upgrade observations
Mechanisms of intrinsic toroidal rotation tested against ASDEX Upgrade observations William A. Hornsby C. Angioni, E. Fable, P. Manas, R. McDermott, Z.X. Lu, S. Grosshauser 2, A. G. Peeters 2 and the ASDEX
More informationReduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX
1 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1), D.L. Brower 2), C. Deng 2), D.T. Anderson 1), F.S.B. Anderson 1), A.F.
More informationStudy of neoclassical transport and bootstrap current for W7-X in the 1/ν regime, using results from the PIES code
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 46 (2004) 179 191 PLASMA PHYSICS AND CONTROLLED FUSION PII: S0741-3335(04)65723-X Study of neoclassical transport and bootstrap current for
More informationFormation 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 informationRotation and Neoclassical Ripple Transport in ITER
Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics
More informationQuasi-Symmetric Stellarators as a Strategic Element in the US Fusion Energy Research Plan
Quasi-Symmetric Stellarators as a Strategic Element in the US Fusion Energy Research Plan Quasi-Symmetric Stellarator Research The stellarator offers ready solutions to critical challenges for toroidal
More informationIssues 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 informationThe effect of the radial electric field on neoclassical flows in a tokamak pedestal
PSFC/JA-1-4 The effect of the radial electric field on neoclassical flows in a tokamak pedestal Grigory Kagan 1, Kenneth D. Marr, Peter J. Catto, Matt Landreman, Bruce Lipschultz and Rachael McDermott
More informationInitial Experimental Program Plan for HSX
Initial Experimental Program Plan for HSX D.T. Anderson, A F. Almagri, F.S.B. Anderson, J. Chen, S. Gerhardt, V. Sakaguchi, J. Shafii and J.N. Talmadge, UW-Madison HSX Plasma Laboratory Team The Helically
More informationMHD Simulation of High Wavenumber Ballooning-like Modes in LHD
1 TH/P9-16 MHD Simulation of High Wavenumber Ballooning-like Modes in LHD H. Miura and N. Nakajima National Institute for Fusion Science, 322-6 Oroshi, Toki, Gifu 509-5292, JAPAN e-mail contact of main
More informationSMR/ Summer College on Plasma Physics. 30 July - 24 August, Introduction to Magnetic Island Theory.
SMR/1856-1 2007 Summer College on Plasma Physics 30 July - 24 August, 2007 Introduction to Magnetic Island Theory. R. Fitzpatrick Inst. for Fusion Studies University of Texas at Austin USA Introduction
More informationThe Linear Theory of Tearing Modes in periodic, cyindrical plasmas. Cary Forest University of Wisconsin
The Linear Theory of Tearing Modes in periodic, cyindrical plasmas Cary Forest University of Wisconsin 1 Resistive MHD E + v B = ηj (no energy principle) Role of resistivity No frozen flux, B can tear
More informationInfluence of Beta, Shape and Rotation on the H-mode Pedestal Height
Influence of Beta, Shape and Rotation on the H-mode Pedestal Height by A.W. Leonard with R.J. Groebner, T.H. Osborne, and P.B. Snyder Presented at Forty-Ninth APS Meeting of the Division of Plasma Physics
More informationEffect of rotational transform and magnetic shear on confinement of stellarators
Effect of rotational transform and magnetic shear on confinement of stellarators E. Ascasíbar(1), D. López-Bruna(1), F. Castejón(1), V.I. Vargas(1), V. Tribaldos(1), H. Maassberg(2), C.D. Beidler(2) R.
More informationPresented on the 15th International Stellarator Workshop, Madrid, 3-7 Oct Submitted to Fusion Science and Technology Revised 20 March 2006
Presented on the 15th International Stellarator Workshop, Madrid, 3-7 Oct. 2005 Submitted to Fusion Science and Technology Revised 20 March 2006 VENUS+ffif - A BOOTSTRAP CURRENT CALCULATION MODULE FOR
More informationIssues in Neoclassical Tearing Mode Theory
Issues in Neoclassical Tearing Mode Theory Richard Fitzpatrick Institute for Fusion Studies University of Texas at Austin Austin, TX Tearing Mode Stability in Tokamaks According to standard (single-fluid)
More informationarxiv: v2 [physics.plasm-ph] 24 Jul 2017
Rotation and Neoclassical Ripple Transport in ITER E. J. Paul Department of Physics, University of Maryland, College Park, MD 20742, USA arxiv:1703.06129v2 [physics.plasm-ph] 24 Jul 2017 M. Landreman Institute
More informationDirect 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 informationDOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING
DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING V.S. Chan, S.C. Chiu, Y.A. Omelchenko General Atomics, San Diego, CA, U.S.A. 43rd Annual APS Division of Plasma Physics Meeting
More informationHOW THE DEMO FUSION REACTOR SHOULD LOOK IF ITER FAILS. Paul Garabedian and Geoffrey McFadden
HOW THE DEMO FUSION REACTOR SHOULD LOOK IF ITER FAILS Paul Garabedian and Geoffrey McFadden 1. Summary Runs of the NSTAB equilibrium and stability code show there are many 3D solutions of the advanced
More informationInter-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 informationConfinement of toroidal non-neutral plasma in Proto-RT
Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,
More informationConfinement of toroidal non-neutral plasma in Proto-RT
Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,
More informationParticle-in-cell simulations of electron transport from plasma turbulence: recent progress in gyrokinetic particle simulations of turbulent plasmas
Institute of Physics Publishing Journal of Physics: Conference Series 16 (25 16 24 doi:1.188/1742-6596/16/1/2 SciDAC 25 Particle-in-cell simulations of electron transport from plasma turbulence: recent
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 informationIntrinsic 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 informationDesign of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system
Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system J.M. Ané 1, V. Grandgirard, F. Albajar 1, J.Johner 1 1Euratom-CEA Association, Cadarache, France Euratom-EPFL
More informationThe Virial Theorem, MHD Equilibria, and Force-Free Fields
The Virial Theorem, MHD Equilibria, and Force-Free Fields Nick Murphy Harvard-Smithsonian Center for Astrophysics Astronomy 253: Plasma Astrophysics February 10 12, 2014 These lecture notes are largely
More informationION THERMAL CONDUCTIVITY IN TORSATRONS. R. E. Potok, P. A. Politzer, and L. M. Lidsky. April 1980 PFC/JA-80-10
ION THERMAL CONDUCTIVITY IN TORSATRONS R. E. Potok, P. A. Politzer, and L. M. Lidsky April 1980 PFC/JA-80-10 ION THERMAL CONDUCTIVITY IN TORSATRONS R.E. Potok, P.A. Politzer, and L.M. Lidsky Plasma Fusion
More informationComparison of Plasma Flows and Currents in HSX to Neoclassical Theory
1 EX/P3-30 Comparison of Plasma Flows and Currents in HSX to Neoclassical Theory D.T. Anderson 1, A.R. Briesemeister 1, J.C. Schmitt 2, F.S.B. Anderson 1, K.M. Likin 1, J.N. Talmadge 1, G.M. Weir 1, K.
More informationSimulation Research on disruptions and runaway electrons
第 20 回 NEXT 研究会 Simulation Research on disruptions and runaway electrons A. Matsuyama, M. Yagi, H. Nuga, N. Aiba, and Y. Ishii JAEA, Rokkasho, Japan Acknowledgement: Y. Shibata, A. Ito, M. Furukawa, S.
More informationTheory 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 informationOptimal design of 2-D and 3-D shaping for linear ITG stability*
Optimal design of 2-D and 3-D shaping for linear ITG stability* Mordechai N. Rorvig1, in collaboration with Chris C. Hegna1, Harry E. Mynick2, Pavlos Xanthopoulos3, and M. J. Pueschel1 1 University of
More informationarxiv: v2 [physics.plasm-ph] 8 Mar 2018
Quasi-axisymmetric magnetic fields: weakly non-axisymmetric case in a vacuum G.G. Plunk 1 and P. Helander 1 1 Max-Planck-Institut für Plasmaphysik, EURATOM Association, 17491 Greifswald, Germany arxiv:1801.02990v2
More informationSimulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD
1 Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD Y. Todo 1), N. Nakajima 1), M. Osakabe 1), S. Yamamoto 2), D. A. Spong 3) 1) National Institute for Fusion Science,
More informationMHD Stabilization Analysis in Tokamak with Helical Field
US-Japan Workshop on MHD Control, Magnetic Islands and Rotation the University of Texas, Austin, Texas, USA AT&T Executive Education & Conference Center NOVEMBER 3-5, 8 MHD Stabilization Analysis in Tokamak
More informationMHD equilibrium calculations for stellarators. Antoine Cerfon, MIT PSFC with F. Parra, J. Freidberg (MIT NSE)
MHD equilibrium calculations for stellarators Antoine Cerfon, MIT PSFC with F. Parra, J. Freidberg (MIT NSE) March 20, 2012 MAGNETIC FIELD LINE HAMILTONIAN Consider a general toroidal coordinate system
More informationMagnetically 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 informationToroidal Rotation In Tokamak Plasmas
IAEA-CN-165/TH/P8-36, 2008 Geneva Fusion Energy Conf. UW-CPTC 08-6R 1 Toroidal Rotation In Tokamak Plasmas J.D. Callen, A.J. Cole, C.C. Hegna University of Wisconsin, Madison, WI 53706-1609 USA e-mail
More informationStellarator Research Opportunities
Stellarator Research Opportunities A report of the National Stellarator Coordinating Committee This document is the product of a stellarator community workshop, referred to as Stellcon, that was held in
More informationGuiding Center Orbit Studies in a Tokamak Edge Geometry Employing Boozer and Cartesian Coordinates
Contrib. Plasma Phys. 48, No. -3, 4 8 (8) / DOI./ctpp.839 Guiding Center Orbit Studies in a Tokamak Edge Geometry Employing Boozer and Cartesian Coordinates Y. Nishimura,Y.Xiao,and Z. Lin Department of
More information1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator
Max-Planck-Institut für Plasmaphysik 1) H-mode in Helical Devices M. Hirsch 1, T. Akiyama 2, T.Estrada 3, T. Mizuuchi 4, K. Toi 2, C. Hidalgo 3 1 Max-Planck-Institut für Plasmaphysik, EURATOM-Ass., D-17489
More informationA 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 informationTriggering Mechanisms for Transport Barriers
Triggering Mechanisms for Transport Barriers O. Dumbrajs, J. Heikkinen 1, S. Karttunen 1, T. Kiviniemi, T. Kurki-Suonio, M. Mantsinen, K. Rantamäki 1, S. Saarelma, R. Salomaa, S. Sipilä, T. Tala 1 Euratom-TEKES
More informationFundamentals of Magnetic Island Theory in Tokamaks
Fundamentals of Magnetic Island Theory in Tokamaks Richard Fitzpatrick Institute for Fusion Studies University of Texas at Austin Austin, TX, USA Talk available at http://farside.ph.utexas.edu/talks/talks.html
More informationPRINCETON PLASMA PHYSICS LABORATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY
PREPARED FOR THE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DE-AC02-76CH03073 PPPL-3517 UC-70 PPPL-3517 Physics Issues in the Design of Low Aspect-Ratio, High-Beta, Quasi-Axisymmetric Stellarators by M.C.
More informationA.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 informationTH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings
TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings T. Onjun 1), A.H. Kritz ), G. Bateman ), A. Pankin ) 1) Sirindhorn International Institute of Technology, Klong Luang, Pathumthani,
More informationSTELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT
STELLARATOR REACTOR OPTIMIZATION AND ASSESSMENT J. F. Lyon, ORNL ARIES Meeting October 2-4, 2002 TOPICS Stellarator Reactor Optimization 0-D Spreadsheet Examples 1-D POPCON Examples 1-D Systems Optimization
More information(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time
Studies of Spherical Tori, Stellarators and Anisotropic Pressure with M3D 1 L.E. Sugiyama 1), W. Park 2), H.R. Strauss 3), S.R. Hudson 2), D. Stutman 4), X-Z. Tang 2) 1) Massachusetts Institute of Technology,
More informationCurrent-driven instabilities
Current-driven instabilities Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 21 st February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously In the last
More informationGyrokinetic simulations of magnetic fusion plasmas
Gyrokinetic simulations of magnetic fusion plasmas Tutorial 2 Virginie Grandgirard CEA/DSM/IRFM, Association Euratom-CEA, Cadarache, 13108 St Paul-lez-Durance, France. email: virginie.grandgirard@cea.fr
More informationBlob 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 informationPhysics design of a high-β quasi-axisymmetric stellarator
Plasma Phys. Control. Fusion 41 (1999) B273 B283. Printed in the UK PII: S0741-3335(99)07029-3 Physics design of a high-β quasi-axisymmetric stellarator A Reiman, G Fu, S Hirshman, L Ku, D Monticello,
More information0 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 informationSnakes and similar coherent structures in tokamaks
Snakes and similar coherent structures in tokamaks A. Y. Aydemir 1, K. C. Shaing 2, and F. W. Waelbroeck 1 1 Institute for Fusion Studies, The University of Texas at Austin, Austin, TX 78712 2 Plasma and
More informationSimulation of alpha particle current drive and heating in spherical tokamaks
Simulation of alpha particle current drive and heating in spherical tokamaks R. Farengo 1, M. Zarco 1, H. E. Ferrari 1, 1 Centro Atómico Bariloche and Instituto Balseiro, Argentina. Consejo Nacional de
More informationOn the physics of shear flows in 3D geometry
On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOM-CIEMAT, Madrid, Spain Recent experiments have shown the importance of multi-scale (long-range)
More informationPoloidal Variation of High-Z Impurity Density in ICRF- Heated Alcator C-Mod Plasmas
Poloidal Variation of High-Z Impurity Density in ICRF- Heated Alcator C-Mod Plasmas M.L. Reinke, I.H. Hutchinson, J.E. Rice, N.T. Howard, A. Bader, S. Wukitch, Y. Lin, D.C. Pace, A. Hubbard, J.W. Hughes
More informationEdge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas
Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu
More informationOpportunities and priorities for stellarator theory and computation
Opportunities and priorities for stellarator theory and computation Matt Landreman University of Maryland Allen Boozer Columbia University (Dated: April 30, 2017) There is an art to identifying good research
More informationNonlinear 3D MHD physics of the helical reversed-field pinch
Nonlinear 3D MHD physics of the helical reversed-field pinch Daniele Bonfiglio* Consorzio RFX, Euratom-ENEA Association, Padova, Italy *In collaboration with: S. Cappello, L. Chacón (Oak Ridge National
More informationValidating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas
Validating Simulations of Multi-Scale Plasma Turbulence in ITER-Relevant, Alcator C-Mod Plasmas Nathan Howard 1 with C. Holland 2, A.E. White 1, M. Greenwald 1, J. Candy 3, P. Rodriguez- Fernandez 1, and
More informationOverview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations
Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER
More informationSeptember Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts USA
PFC/JA-95-19 RF WAVE EFFECTS ON THE NEOCLASSICAL ELECTRON DISTRIBUTION FUNCTION IN TOKAMAKS S. D. Schultz, A. Bers, and A. K. Ram September 1995 Plasma Fusion Center Massachusetts Institute of Technology
More informationEffect of the Toroidal Asymmetry on the Structure of TAE Modes in Stellarators
Effect of the Toroidal Asymmetry on the Structure of TAE Modes in Stellarators Yu.V. Yakovenko 1), Ya.I. Kolesnichenko 1), V.V. Lutsenko 1), A. Weller 2), A. Werner 2) 1) Institute for Nuclear Research,
More informationEUROFUSION WPJET1-PR(16) CG Albert et al.
EUROFUSION WPJET1-PR(16) 15331 CG Albert et al. Hamiltonian approach for evaluation of toroidal torque from finite amplitude non-axisymmetric perturbations of a tokamak magnetic field in resonant transport
More informationPOWER DENSITY ABSORPTION PROFILE IN TOKAMAK PLASMA WITH ICRH
Dedicated to Professor Oliviu Gherman s 80 th Anniversary POWER DENSITY ABSORPTION PROFILE IN TOKAMAK PLASMA WITH ICRH N. POMETESCU Association EURATOM-MECTS Romania, University of Craiova, Faculty of
More informationTURBULENT 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