The efficient sustainment of a stable, high-β spheromak: modeling By Tom Jarboe, To PSI-Center July 29, 2015.

Slides:



Advertisements
Similar presentations
Dynamo Effects in Laboratory Plasmas S.C. Prager University of Wisconsin October, 2003.
Advertisements

Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Dynamo and Magnetic Helicity Flux Hantao Ji CMSO & PPPL CMSO General Meeting Princeton, October 5-7, 2005 Contributors: Eric Blackman (Rochester) Stewart.
Comparing classical and lab plasma dynamos S. Prager University of Wisconsin useful discussions with D. Craig, H. Ji, J. Sarff, E. Zweibel.
Reconnection: Theory and Computation Programs and Plans C. C. Hegna Presented for E. Zweibel University of Wisconsin CMSO Meeting Madison, WI August 4,
Some New Data From FRC Experiment on Relaxation For discussions at Hall-Dynamo and Related Physics meeting CMSO June 10-11, 2004 at PPPL Guo et al, PRL.
Seminario UT FUSIONE Aula Brunelli, Centro Ricerche Frascati 8 Febbraio 2010 Ideal MHD Stability Boundaries of the PROTO-SPHERA Configuration F. Alladio,
Physics of fusion power Lecture 4: Cylindrical concepts.
Momentum Transport During Reconnection Events in the MST Reversed Field Pinch Alexey Kuritsyn In collaboration with A.F. Almagri, D.L. Brower, W.X. Ding,
ICC2004 Madison, Wisconsin The Multi-Pinch Experiment Outline PROTO-SPHERA purpose & aims Theoretical basis & analysis Multi-Pinch: a step towards PROTO-SPHERA.
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
Runaway Electron Mitigation Collaboration on J-TEXT David Q. Hwang UC Davis Sixth US-PRC Magnetic Fusion Collaboration Workshop Collaborating Institutions:
Physics of fusion power
MHD Behaviour of Low-Aspect-Ratio RFP Plasmas in RELAX S.Masamune, T.Onchi, A.Sanpei, R.Ikezoe, K.Oki, T.Yamashita, H.Shimazu, N.Nishino 1), R.Paccagnella.
Physics of fusion power Lecture 4: Cylindrical concepts.
Physics of fusion power Lecture 8 : The tokamak continued.
Physics of Fusion power Lecture 7: Stellarator / Tokamak.
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
Physics of fusion power
SIMULATION OF A HIGH-  DISRUPTION IN DIII-D SHOT #87009 S. E. Kruger and D. D. Schnack Science Applications International Corp. San Diego, CA USA.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
Numerical Simulation on Flow Generated Resistive Wall Mode Shaoyan Cui (1,2), Xiaogang Wang (1), Yue Liu (1), Bo Yu (2) 1.State Key Laboratory of Materials.
Plasma Dynamics Lab HIBP E ~ 0 V/m in Locked Discharges Average potential ~ 580 V  ~ V less than in standard rotating plasmas Drop in potential.
Physics of fusion power Lecture 10: tokamak – continued.
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
Reconnection rates in Hall MHD and Collisionless plasmas
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
Nonlinear interactions between micro-turbulence and macro-scale MHD A. Ishizawa, N. Nakajima, M. Okamoto, J. Ramos* National Institute for Fusion Science.
Two problems with gas discharges 1.Anomalous skin depth in ICPs 2.Electron diffusion across magnetic fields Problem 1: Density does not peak near the.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
Lecture Series in Energetic Particle Physics of Fusion Plasmas Guoyong Fu Princeton Plasma Physics Laboratory Princeton University Princeton, NJ 08543,
1 Importance of two-fluid in helicity injection current drive.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
EJD IAEA H-mode WS,, September 28, Overview Introduction — steady-state performance requirements -Global DIII-D and NSTX progress Plasma control.
Simulation Study of Magnetic Reconnection in the Magnetotail and Solar Corona Zhi-Wei Ma Zhejiang University & Institute of Plasma Physics Beijing,
EXTENSIONS OF NEOCLASSICAL ROTATION THEORY & COMPARISON WITH EXPERIMENT W.M. Stacey 1 & C. Bae, Georgia Tech Wayne Solomon, Princeton TTF2013, Santa Rosa,
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Challenges for Fusion Theory and Explosive Behaviour in Plasmas Steve Cowley,
1 A Proposal for a SWIM Slow-MHD 3D Coupled Calculation of the Sawtooth Cycle in the Presence of Energetic Particles Josh Breslau Guo-Yong Fu S. C. Jardin.
Weixing Ding University of California, Los Angeles,USA collaborators: D.L. Brower, W. Bergerson, D. Craig, D. Demers, G.Fiksel, D.J. Den Hartog, J. Reusch,
FEC 2006 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
QAS Design of the DEMO Reactor
MCZ Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2,
Simulations of NBI-driven Global Alfven Eigenmodes in NSTX E. V. Belova, N. N. Gorelenkov, C. Z. Cheng (PPPL) NSTX Results Forum, PPPL July 2006 Motivation:
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
Transition to helical RFP state and associated change in magnetic stochasticity in a low-aspect-ratio RFP A.Sanpei, R.Ikezoe, T. Onchi, K.Oki, T.Yamashita,
The Joint Meeting of 4th IAEA Technical Meeting on Spherical Tori and 14th International Workshop on Spherical TorusFrascati, 7 to 10 October Ideal.
Numerical Study on Ideal MHD Stability and RWM in Tokamaks Speaker: Yue Liu Dalian University of Technology, China Co-Authors: Li Li, Xinyang Xu, Chao.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
1 Peter de Vries – ITPA T meeting Culham – March 2010 P.C. de Vries 1,2, T.W. Versloot 1, A. Salmi 3, M-D. Hua 4, D.H. Howell 2, C. Giroud 2, V. Parail.
Nonlinear Simulations of Energetic Particle-driven Modes in Tokamaks Guoyong Fu Princeton Plasma Physics Laboratory Princeton, NJ, USA In collaboration.
Presented by Yuji NAKAMURA at US-Japan JIFT Workshop “Theory-Based Modeling and Integrated Simulation of Burning Plasmas” and 21COE Workshop “Plasma Theory”
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
54th Annual Meeting of the Division of Plasma Physics, October 29 – November 2, 2012, Providence, Rhode Island 5-pin Langmuir probe measures floating potential.
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA Influence of ion orbit width on threshold of neoclassical tearing modes Huishan Cai 1, Ding Li 2, Jintao.
Equilibrium and Stability
THEORY OF MERIDIONAL FLOW AND DIFFERENTIAL ROTATION
24th IAEA Fusion Energy Conference, San Diego, USA October 8-13, 2012
F. Alladio, A. Mancuso, P. Micozzi, F. Rogier*
Influence of energetic ions on neoclassical tearing modes
New Results for Plasma and Coil Configuration Studies
Self-organization to Stable magnetic Plasmas by
Presentation transcript:

The efficient sustainment of a stable, high-β spheromak: modeling By Tom Jarboe, To PSI-Center July 29, 2015

Outline Physics basis of the effect of perturbations The self-organized effect of flattening the j/B profile Impact on large aspect ratio tokamaks HIT-SI results Summary

IDCD is a new relaxation mechanism for making j/B uniform in a stable symmetric equilibrium This mechanism provides an explanation for:* – The level of field error (δB/B = ) that spoils tokamak performance. – The rate of poloidal flux loss in Argon induced disruptions in DIII-D. – The change in plasma rotation direction with LHCD in the edge on C-mod. – The toroidal current versus time, the injector impedance, and the current profile of HIT-SI. *T. R. Jarboe, B. A. Nelson, and D. A. Sutherland, “A mechanism for the dynamo terms to sustain closed-flux current, including helicity balance, by driving current which crosses the magnetic field”, to be published July 15, 2015 in Physics of Plasmas

4 An explanation of effect of perturbations on current starts with symmetric current Electron fluid is frozen to magnetic fields. (Two-fluid MHD) Current flow is also magnetic field flow. For a stable equilibrium the magnetic structure is rigid. It resists deformation. Toroidal current is from electrons frozen in nested solid shells that are rotating at different speeds. Symmetric flux surfaces allow free differential current flow.(Free means unobstructed by magnetic interference.) Toroidal current in a torus with a hollow current profile

Sheared electron flow plus perturbations give current drive across closed flux surfaces Now add a magnetic perturbation (red) and differential flow is no longer free. If the perturbation is large enough the flow locks across flux surfaces (inner flux surfaces). If the perturbations are small enough the differential flow can symmetrize the perturbation and differential flow continues. – A viscosity-like drag force will drive the current inside the symmetrize closed flux surface. Both effects are current self-organizing across closed flux surfaces towards uniform j tor /B tor. HIT-SI data indicate that the viscosity-like force per unit area needed to symmetrize is: Externally driving the edge results in Imposed Dynamo Current Drive (IDCD).* *T. R. Jarboe et al., Nucl. Fusion, 52, (2012)

Viscous force on the flux surface area = Force require to drive the current throughout that flux surface volume. IDCD effect is simple to estimate

IDCD equation agrees with radiative disruption* perturbations Disruption created by Argon injection. Cold edge peaks the current until it is unstable. Instability cools plasma. The low edge current is maintained by the Argon and drags down the plasma current: 1.5 MA profile is flattened in 1.2 ms IDCD requires δB  of 190G (at s) *P. L. Taylor et al., Phys. Rev. Lett, 76, (1996)

On a reactor and ITER the perturbation levels required to drive the current are a little higher than considered acceptable (confirming the effect). They are small. ParameterPresent tokamaks ARIES-ATITER I tor (MA) Temp. (keV) a (m)  L/R (s)  B  rms /B Current driving perturbations can also flatten the j/B profile which flattens the q-profile leading to poor performance often ending in disruptions.

Solutions 1.Drive the edge current high and impose a perturbation profile that sustains the desired reversed-shear current profile. 2.Select a high performance equilibrium that has a uniform j/B (low aspect ratio) – Rigorously sustain the rock-stable profile by edge current drive and repeated application of non-resonant perturbations of IDCD. – The method has been demonstrated on HIT-SI. Solves the sustainment problem. (IDCD is over two orders of magnitude more power efficient on a reactor than rf) High edge current prevent the edge from using perturbations to drag down the current in disruptions.

HIT-SI uses imposed fluctuations and an externally driven edge current to sustain the equilibrium Current amplification of 3.9, a new spheromak record 90 kA of toroidal current Stable sustained equilibria ohmically heat to the beta limit,*achieving the current drive goal * B. S. Victor et al., Physics of Plasmas, 21, (2014)

HIT-SI produces equilibria stable to current driven modes (a) Internal probes. (b) surface probes Data matches a very flat two step profile First step is at the injector j/B and wide enough to hold injector current. Second step is high enough to hold the toroidal current. Equilibria are stable. The only significant fluctuations observed are imposed. The toroidal current versus time, the injector impedance scaling with j/n of the spheromak, and the current profile data of HIT-SI are predicted by the IDCD model.  o j/B

The only significant fluctuations observed are imposed Mode amplitudes vs time Mode amplitudes minus the imposed perturbations vs time n=1 amplitude and the injector current vs time Toroidal current vs time During sustainment the n=1 is almost entirely imposed and the equilibrium is stable. HIT-SI is capable of testing MHD stability, which had been the problem with sustained spheromaks until now.

Gradients in j/B may inhibit instability Imposed perturbations cause a force that inhibit differential motion of rigid shells. Conversely, differential motion of rigid shells cause a force that inhibits perturbations, including eigenmodes of instabilities, preventing instability growth. The gradient in j/B is maintained at the current separatrix by keeping the injector j/B high. Differential current flow at the separatrix enforces symmetry and stability in the region.

Codes are not capturing the physics of IDCD Simulation has larger fluctuations indicating relaxation by instability Simulation has flatter B pol near magnetic axis with q > 1 Experiment has q < 1 and is stable For poloidally circular flux surfaces at the magnetic axis Experiment uses imposed perturbations that sustain a stable equilibrium. B pol B tor Kyle Morgan

Two possible problems Once it is unstable the flux surfaces are not rigid. Magnetic interference does not drive current. Resorts to instability. (catch 22) Need to find the IDCD steady-state. (start with stable equilibrium) Electron fluid may not be sufficiently frozen in the magnetic field. May need a more accurate Ohm’s law. (Simulation electrons are not as frozen in because of more mass, more dissipation, or divB cleaning?) I think the first one is more likely and we have not worked on it. Initial conditions are very important for non-linear equations.

Conclusions Imposed perturbations allow the sustainment of kink- stable equilibria. Evidence of pressure confinement during sustainment is a spheromak first, with current gains of nearly 4.0, a new spheromak record. XMHD codes have a different profile of lower dB pol /dr at the magnetic axis and higher q (>1) than the experiment. Current probably penetrates by instability not imposed perturbations. May not be rigid enough for the effect because it is unstable? (catch 22) Electron fluid may not be sufficiently frozen in the magnetic field.

Problems getting initial conditions? Start with large Taylor state? Pickup experiment after gain of 2 ?

Doing total Ohm’s law What are we missing? Are we close to being able to do it? Two fluids?

An IDCD injector could be attached to a tokamak 19

Ion Doppler Spectroscopy confirms rigid motion

IDS geometry