Principal Attributes of FRCs Sustained by

Slides:



Advertisements
Similar presentations
Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Advertisements

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.
Ion-Induced Instability of Diocotron Modes In Magnetized Electron Columns Andrey Kabantsev University of California at San Diego Physics Department Nonneutral.
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
17. April 2015 Mitglied der Helmholtz-Gemeinschaft Application of a multiscale transport model for magnetized plasmas in cylindrical configuration Workshop.
ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
Physics of fusion power Lecture 4: Cylindrical concepts.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
EE20A - Electromechanical Energy Conversion Induction Machine
F. Cheung, A. Samarian, B. James School of Physics, University of Sydney, NSW 2006, Australia.
Electro Mechanical System
Physics of fusion power Lecture 4: Cylindrical concepts.
Physics of fusion power
Physics of fusion power Lecture 8 : The tokamak continued.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
Recent Results of Configuration Studies L. P. Ku Princeton Plasma Physics Laboratory ARIES-CS Project Meeting, November 17, 2005 UCSD, San Diego, CA.
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
F. Cheung, A. Samarian, W. Tsang, B. James School of Physics, University of Sydney, NSW 2006, Australia.
Physics of fusion power Lecture 7: particle motion.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
F.M.H. Cheung School of Physics, University of Sydney, NSW 2006, Australia.
Chapter 5 Diffusion and resistivity
N EOCLASSICAL T OROIDAL A NGULAR M OMENTUM T RANSPORT IN A R OTATING I MPURE P LASMA S. Newton & P. Helander This work was funded jointly by EURATOM and.
Physics of fusion power
1 ST workshop 2005 Numerical modeling and experimental study of ICR heating in the spherical tokamak Globus-M O.N.Shcherbinin, F.V.Chernyshev, V.V.Dyachenko,
H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team Japan Atomic Energy Agency JT-60U Tokamak: p.
1 Model of filaments in plasma Nobuhiro Nishino Graduate school of Engineering Hiroshima University 3rd IAEA TM and 11th IWS on ST Place: St.Petersburg.
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
Profile Measurement of HSX Plasma Using Thomson Scattering K. Zhai, F.S.B. Anderson, J. Canik, K. Likin, K. J. Willis, D.T. Anderson, HSX Plasma Laboratory,
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
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.
Anharmonic Effects. Any real crystal resists compression to a smaller volume than its equilibrium value more strongly than expansion to a larger volume.
Physics of fusion power Lecture 10: tokamak – continued.
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
PLASMA HEATING AND HOT ION SUSTAINING IN MIRROR BASED HYBRIDS
第16回 若手科学者によるプラズマ研究会 JAEA
Stability Properties of Field-Reversed Configurations (FRC) E. V. Belova PPPL 2003 International Sherwood Fusion Theory Conference Corpus Christi, TX,
Physics of fusion power Lecture 9 : The tokamak continued.
Comparison of Ion Thermal Transport From GLF23 and Weiland Models Under ITER Conditions A. H. Kritz 1 Christopher M. Wolfe 1 F. Halpern 1, G. Bateman 1,
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.
HT-7 ASIPP The Influence of Neutral Particles on Edge Turbulence and Confinement in the HT-7 Tokamak Mei Song, B. N. Wan, G. S. Xu, B. L. Ling, C. F. Li.
Physics of fusion power Lecture 12: Diagnostics / heating.
Chalmers University of Technology Simulations of the formation of transport barriers including the generation of poloidal spinup due to turbulence J. Weiland.
Radial Electric Field Formation by Charge Exchange Reaction at Boundary of Fusion Device* K.C. Lee U.C. Davis *submitted to Physics of Plasmas.
Work with TSC Yong Guo. Introduction Non-inductive current for NSTX TSC model for EAST Simulation for EAST experiment Voltage second consumption for different.
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.
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,
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.
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
Alex Samarian Complex Plasma Laboratory School of Physics, University of Sydney, NSW 2006, Australia
ZHENG Guo-yao, FENG Kai-ming, SHENG Guang-zhao 1) Southwestern Institute of Physics, Chengdu Simulation of plasma parameters for HCSB-DEMO by 1.5D plasma.
LI et al. 1 G.Q. Li 1, X.Z. Gong 1, A.M. Garofalo 2, L.L. Lao 2, O. Meneghini 2, P.B. Snyder 2, Q.L. Ren 1, S.Y. Ding 1, W.F. Guo 1, J.P. Qian 1, B.N.
53rd Annual Meeting of the Division of Plasma Physics, November , 2010, Salt Lake City, Utah 5-pin Langmuir probe configured to measure the Reynolds.
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
= Boozer g= 2*1e -7 *48*14*5361 =.7205 =0 in net current free stellarator, but not a tokamak. QHS Mirror Predicted Separatrix Position Measurements and.
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
1 V.A. Soukhanovskii/IAEA-FEC/Oct Developing Physics Basis for the Radiative Snowflake Divertor at DIII-D by V.A. Soukhanovskii 1, with S.L. Allen.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
48th Annual Meeting of the Division of Plasma Physics, October 30 – November 3, 2006, Philadelphia, Pennsylvania Energetic-Electron-Driven Alfvénic Modes.
Neoclassical Predictions of ‘Electron Root’ Plasmas at HSX
First Experiments Testing the Working Hypothesis in HSX:
Influence of energetic ions on neoclassical tearing modes
New Results for Plasma and Coil Configuration Studies
20th IAEA Fusion Energy Conference,
New Development in Plasma and Coil Configurations
Presentation transcript:

Principal Attributes of FRCs Sustained by Rotating Magnetic Field Current Drive Alan Hoffman, H.Y. Guo, K.E. Miller, R.D. Milroy Redmond Plasma Physics Laboratory University of Washington APS Plasma Physics Conference October 24-28, 2005 Denver, CO

Abstract Field Reversed Configurations (FRC) sustained by Rotating Magnetic Fields (RMF) are distinctly different from the decaying FRCs formed in theta-pinches. The RMF drive reverses particle diffusion, producing very long particle lifetimes, low separatrix densities, and complete reversal of the external confinement field. The density is set by torque balance between the RMF drive and resistive drag on the electrons. An FRC will increase in poloidal flux and expand radially inside a flux conserver until the compressed external field pressure balances the product of density times temperature. Higher temperatures, which are determined by a balance between RMF produced heating and various loss mechanisms, will automatically result in higher diamagnetic currents and poloidal magnetic fields, without requiring any increase in RMF parameters, and with very little increase in absorbed RMF power. Current drive performance thus increases dramatically with increasing plasma temperature. Temperatures in present TCS experiments are limited primarily by radiation and conduction/convection. Recent experiments show that conduction/convection losses can be greatly reduced using anti-symmetric RMF drive, and extensive modifications are being made to TCS to reduce impurities and radiation losses, so large increases in overall performance can be expected.

Flux is Major Determinate of Compact Toroid (CT) Lifetime Prolate FRC inside Flux Conserver rc rs Bo Be External flux e = rc2Bo Internal flux p  0.31xsrs2Be xs  rs/rc Flux conservation: Be = Bo/(1-xs2) FRC radius xs = xs(p/e) set by ratio of internal and external fluxes: Peak plasma pressure set by compressed bias field: Average beta governed by axial equilibrium:

Rotating Magnetic Fields (RMF) Applied to Flux Confined FRC RMF antenna Iz = Iosinwt Iz = Iocoswt Bz field coils driven electron current rotating field Bw ‘Rotating Radial Field ‘Drags’ Electrons Must have wci < w << wce for electrons, but not ions, to follow rotation. Electrons Magnetized on Rotating Field Lines (wcet >> 1) Necessary for efficient current drive. Absolutely necessary for rotating field penetration. Resultant RMF Torque Increases FRC Flux and Pressure Process continues until RMF torque is balanced by resistive electron-ion frictional torque.

Flux Build-Up is Key to FRC Formation & Sustainment by RMF { for */rs < 0.5 The balance of TRMF with T determines the maximum possible electron density: (*/rs ~ e/) Flux build-up will continue and Be will increase until ne equals ne*. Be  (neTt)1/2, so higher temperatures will result in higher magnetic fields, currents, and FRC fluxes as long as Idia < Isync. Higher Tt produce higher diamagnetic currents (for a given ne) and requires higher RMF frequency.

RMF Partial Penetration is Rugged, Natural Phenomenon Diamagnetic line current: * Synchronous line current: Key current drive parameter: Near synchronous edge rotation with small  =  - e allows deep RMF penetration: Partial penetration is desirable to maximize torque and minimize Br. It is ci = eBr/mi which must be kept small to avoid ion drive. Br component of RMF tends to open up field lines. Larger B aids radial confinement and stabilizes interchange modes. As long as  ~< 0.5, edge and penetration adjust naturally so that */rs  .

TCS Experiment (1/4 view) RMF Antenna Main Bias Coils End Coils 0.4 Be Mirror Coils 0.3 Radius (m) rs rc 0.2 0.1 Bo RMF2003.8a - hg2005.alh.f1 0.25 0.50 0.75 1.00 1.25 1.50 Distance to the midplane (m) Main bias and end coils energized in parallel to serve as flux conserver

Temperature Higher Early Before Impurity Ingestion & Radiation -20 -10 10 20 Be Bint BRMF Magnetic Field (mT) 0.4 0.8 1.2 1.6 2.0 40 60 80 100 nd nd (1019 m-2) Temperature (eV) Tt -0.2 0.2 0.6 1 1.4 1.8 0.5 1.0 1.5 2.5 Pabs (MW) Prad (MW/m2) Pabs Prad TIME (msec) early time late time Higher Tt at early time results in higher Be, p, and I with same BRMF and only marginally higher absorbed RMF power. Thus, the average plasma resistivity is lower at the higher temperature.

Typical Double Rigid Rotor (DRR) Profiles 10 20 Radius (cm) B (mT) ne(1018 m-3) 30 hg2005.alh.f4c 40 -20 1.0 1.5 2.0 0.5 -10 RR Profile DRR Profile Shot 9217 f = 152 kHz  = 7 kHz t = 1.0 ms Tt = 28 eV t = 0.35 ms Tt = 41 eV Bz BRMF 10 20 Radius (cm) J (105 A/m2) 30 hg2005.alh.f5 40 0.4 0.6 0.8 1.0 0.2 0.5 DRR Profile  = e/ r/ 2r/ The profiles are approximately rigid rotor, but with lower central electron rotation speed leading to reduced j, shallower dBz/dr, and slightly broader ne(r) near the field null. Higher temperature leads to higher j and e.

Partial penetrations with lower central electron rotation can lead to some trapped RMF rotating at lower speed, which we call ‘edge driven mode’ (edm) Very non-uniform resistivity profile is required in calculations to reproduce edm.  = i + e/(1+e(rs-r)/) with i = 30 -m, e = 1000 -m, and  = 1 cm gives best fit to experiments. Numerically, inner structure decays away at rate determined by i. Inner structure rotates at r and tearing and oscillating torque occurs at d =  - r. Many experimental measurements showing oscillation at d indicate the presence of an oscillating torque. Calculation Experiment 0.65 0.70 1.4 37 38 11 12 0.5 1.0 1.5 13 1.6 0.85 0.80 0.75 Time (msec) 0.90 hg2005.alh.f16 p (mWb) rs (cm) Be (mT) (Nt-m/m) TRMF f fd fr

Calculated Profiles During and After edm During edm After edm 10 30 hg2005.alh.f13a 20 Bz BRMF Radius (cm) 40 ne (1018 m-3) B (mT) 5 15 -5 -10 2 4 6 10 30 hg2005.alh.f14a 20 Bz BRMF Radius (m) 40 ne (1018 m-3) B (mT) 5 15 -5 -10 2 4 6 8 These profiles are more characteristic of experimental profiles. The low central resistivity allows high azimuthal current flow near the field null with only weak edm current drive. A tendency toward these profiles is seen on only a few experiments. The central current must be very low, despite low i, since there is little if any RMF drive there.

DRR Model can be used to Calculate Effective Resistivities from Torque or Power Balance Calculated DRR torque can be set equal to ‘measured’ RMF torque, TRMF = 0.8(2B2rs2/o)(*/rs). For scaling purposes we assume different resistivities in inner and edge regions, with e = 10i. However, we do not have an independent measure of the fraction of the measured Pabs attributable only to the azimuthal currents, P. High edge resistivity affects power more than torque since P = eT.

Torque Based Resistivity Scaling 0.5 1.0 1.5 2.0 2.5 3.0 1 2 3 4 5 6 7 8 9 B(*/rs)1/2/(r/0.15)1/2rs nm (1019m-3) 114 kHz 83 kHz 152 kHz 258 kHz Calc nm = 0.044{Bw(*/rs)1/2/rsr1/2}4/3 44 36 59 25 28 41 24 39 30 60 Tt Experimental torque based density scaling: DRR calculated density scaling : Inferred resistivity scaling : The overall resistivity scales approximately as ne-1/2. All experiments also show a resistivity decreasing with temperature, although there is not enough of a temperature spread to determine an accurate temperature scaling. Whereas calculations at constant resistivity show lower peak density at higher temperature (since TRMF = T  ne3/2Tt1/2 is constant), the experiments display contrary results! (The 60 eV calculation resistivity profile was chosen to reproduce the 59 eV experimental results.)

nm = 0.0073{Pabs1/2/rrs2(1+0.57fi/fr}4/3 Resistivity calculated from total Pabs appears higher due to other contributions to absorbed power besides j2 Experimental power based density scaling: 0.5 1.0 1.5 2.0 2.5 3 2 4 6 8 10 12 0.15Pabs1/2/rrs2(1+0.57fi/fr)1/2 nm (1019m-3) 114 kHz 83 kHz 152 kHz 258 kHz Calc nm = 0.0073{Pabs1/2/rrs2(1+0.57fi/fr}4/3 39 DRR calculated density scaling : 36 41 24 28 Tt 25 Inferred ‘resistivity’ scaling with P assumed equal to Pabs : 30 60 59 36 44 Again, the overall resistivity scales approximately as ne-1/2. ‘ip’ is higher than it by about a factor of 2 since Pabs is about double P. At higher temperatures the density falls above the above scaling line since the ratio of Pabs/ P is lower.

Contributions to Total Absorbed Power Calculated Distributions of Absorbed Power Measurements of Excess Absorbed Power 0.5 0.65 0.70 0.85 0.80 0.75 Time (msec) 0.90 hg2005.alh.f12a 1.0 P (MW/m) 1.5 2.0 2rwSPoyn jtot2 j2 jz2  = 30 + 1000/(1+e(a-r)/) -m (Pabs-Pq)/P 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 0.1 0.2 0.3 0.4 0.6 0.7 0.8 0.9 1 (Bw/Be)2/(d*/rs) 1:1 4:1 114 kHz 83 kHz 152 kHz 258 kHz Calc: 256 kHz P is calculated based on DRR model and resistivities inferred from torque balance Pabs = P + Pz + Pdyn. The ratio of excess absorbed power to that due to j2 appears to scale as (B/Be)2/(*/rs), ranging from 2 (at high densities) to 4 (at low densities) times this value.

Pabs Scaling with B/Be Ratio The ratio of Pabs to Be2, representing the effective resistivity for power absorption, scales as B/Be. At a fixed value of B, Pabs only increases linearly with Be, or driven current, due to both the ratio of excess absorbed power to j2 decreasing, and the actual resistivity  decreasing with increasing density or temperature. Higher temperature operation, at a fixed B, should result in significantly higher magnetic fields and FRC currents without requiring large power increases. The decrease in the Pabs/Be2 ratio with lower RMF frequency is due to the increasing plasma density and decreasing actual resistivity as  decreases. Effective ‘ip’ 0.1 150 100 50 83 kHz 114 kHz 152 kHz 258 kHz 0.2 B/Be 0.3 hg2005.alh.f10 0.4 Pabs/6.8(2Be/o)2 (-m)

Resistivity Scales like Chodura Collision Frequency Previous -pinch flux decay rates well modeled using Cc = 0.1, fc = 3. Near separatrix fe ~ f ~ 150 kHz and for Tt = 50 eV, ve/3vs ~ 2 so that the Chodura resistivity is very large and of the same order as the edge resistivity used in the numerical calculations. The resistivity drops rapidly toward the FRC interior as er decreases sharply, also in agreement with our inferred resistivity profiles. Chodura resistivity will decrease with temperature (seen experimentally in TCS) and also with increased size since ve will decrease for a given B (also seen in comparisons with the smaller 20-cm radius STX experiments).

Summary RMF current drive of FRCs, with partial penetration, is natural and optimal for many reasons. RMF parameters determine the FRC density, but the temperature responds to overall power balance. Current drive performance is seen to improve rapidly with increasing temperature, leading to higher FRC magnetic fields, currents, and fluxes. Detailed behavior with edms is best modeled using a highly non-uniform resistivity profile characteristic of the Chodura formula. A new facility, TCS/upgrade is being built with asymmetric RMF drive and control of recycling impurities to greatly increase plasma temperatures and take advantage of the above results.