Flux-surface closure DRAFT Bick Hooper July 11, 2012.

Slides:



Advertisements
Similar presentations
Exploring reconnection physics in SSPX and NIMROD Lawrence Livermore National Laboratory Livermore, CA Center for Magnetic Self Organization La Jolla,
Advertisements

Control of Magnetic Chaos & Self-Organization John Sarff for MST Group CMSO General Meeting Madison, WI August 4-6, 2004.
Comparing classical and lab plasma dynamos S. Prager University of Wisconsin useful discussions with D. Craig, H. Ji, J. Sarff, E. Zweibel.
ASC XP-823 Error Field Correction and Long Pulse J.E. Menard, S.P. Gerhardt Part 1 Determine the source of, and optimal correction for, the observed n=3.
1 Edge Electrode Biasing Experiments on NSTX S. Zweben, C. Bush, R. Maqueda, L. Roquemore, R. Marasla M. Bell, J. Boedo, R. Kaita, Y. Ratises, B. Stratton.
Solenoid-free Plasma Start-up in NSTX using Transient CHI R. Raman 1, M.G. Bell 2, T.R. Jarboe 1, B.A. Nelson 1, D.Mueller 2, R. Maqueda 3, R. Kaita 2,
The Earth’s magnetic field resembles that of a bar magnet. North magnetic is close to south geographic South magnetic is close to north geographic What.
Physics of fusion power Lecture 6: Conserved quantities / Mirror device / tokamak.
Lesson 14 – Capacitors & Inductors. Learning Objectives Define capacitance and state its symbol and unit of measurement. Predict the capacitance of a.
Density gradient at the ends of plasma cell The goal: assess different techniques for optimization density gradient at the ends of plasma cell.
November 2004 IAEA Improved operation and modeling of the Sustained Spheromak Physics eXperiment R.D. Wood, B.I. Cohen, D.N. Hill, R.H. Cohen, S.
Physics of fusion power
Magnetism The density of a magnetic field (number of magnetic lines passing through a given surface) is the magnetic flux: Units of flux are Webers. Tesla/m.
Physics of fusion power Lecture 8: Conserved quantities / mirror / tokamak.
Physics of fusion power
Physics of fusion power Lecture 8 : The tokamak continued.
Faraday’s Law. Area Change  The sliding bar creates an emf by changing the area in the magnetic field. Constant magnetic field  The potential was due.
A coil is wrapped with 340 turns of wire on the perimeter of a circular frame (radius = 8.1 cm). Each turn has the same area, equal to that of the frame.
Physics of Fusion power Lecture 7: Stellarator / Tokamak.
Magnetic Diagnostics for GLAST-III Tokamak M. A. Naveed, Aqib javeed and GLAST Team National Tokamak Fusion Programme Islamabad Pakistan IAEA First Technical.
Interlude: The Hardest Part of this Course Faraday’s Law We will do this twice, today and in about a month (discovered Aug 29,1831)
Magnetic configurations responsible for the coronal heating and the solar wind Hwanhee Lee 1, Tetsuya Magara 1 1 School of Space research, Kyung Hee University.
AP Physics C Montwood High School R. Casao
Superconductivity and Superfluidity The London penetration depth but also F and H London suggested that not only To which the solution is L is known as.
Induction and Inductance Chapter 30 Magnetic Flux.
Chapter 32 Inductance. Joseph Henry 1797 – 1878 American physicist First director of the Smithsonian Improved design of electromagnet Constructed one.
Unit 14 Magnetic Induction. Objectives: Discuss magnetic induction. List factors that determine the amount and polarity of an induced voltage. Discuss.
9/20/04NSTX RESULTS REVIEW NSTX rtEFIT implementation progress results NSTX 2004 RESULTS REVIEW September 20&21, 2004 REAL-TIME EQUILIBRIUM RECONSTRUCTION.
Bias Magnet for the Booster’s 2-nd Harmonic Cavity An attempt to evaluate the scope of work based of the existing RF design of the cavity 9/10/2015I. T.
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
June 2-3, 2004 HAPL meeting, UCLA 1 Progress on Target Survival Presented by A.R. Raffray Other Contributors: B. Christensen, M. S. Tillack UCSD D. Goodin.
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.
1 CHI Summary Transient CHI (XP606) –All systems operated reliably without any faults Edge Current drive (XP533)
Steps toward MTOR Experimental Investigations for ALIST Project Where we stand? This Step: Investigation of Conducting Wall Effects on MHD Film Flow:in.
Physics of fusion power Lecture 10: tokamak – continued.
Summary of Rb loss simulations The goal: assess different techniques for optimization density gradient at the ends of plasma cell.
L P X dL r Biot-Savard Law L P X dL r Biot-Savard Law.
Demonstration of 200 kA CHI Startup Current Coupling to Transformer Drive on NSTX B.A. Nelson, R. Raman, T.R. Jarboe, University of Washington D. Mueller,
Physics of fusion power Lecture 9 : The tokamak continued.
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.
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
What is the direction of the induced current?
CHI Run Summary for March 10-12, 31 & April 9, 2008 Flux savings from inductive drive of a Transient CHI started plasma (XP817) R. Raman, B.A. Nelson,
Faraday’s Law of Induction.  = -N  B /  t –  : induced potential (V) – N: # loops –  B : magnetic flux (Webers, Wb) – t: time (s)
S. Kahn 5 June 2003NuFact03 Tetra Cooling RingPage 1 Tetra Cooling Ring Steve Kahn For V. Balbekov, R. Fernow, S. Kahn, R. Raja, Z. Usubov.
1) Disruption heat loading 2) Progress on time-dependent modeling C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD, 4/4/2011.
Physics 106 Lesson #21 Magnetism: Motors and Generators Dr. Andrew Tomasch 2405 Randall Lab
Team Report on integration of FSAM to SWMF and on FSAM simulations of convective dynamo and emerging flux in the solar convective envelope Yuhong Fan and.
Monday, Apr. 16, 2012PHYS , Spring 2012 Dr. Jaehoon Yu 1 PHYS 1444 – Section 004 Lecture #20 Monday, April 16, 2012 Dr. Jaehoon Yu Today’s homework.
Cheng Zhang, Deng Zhou, Sizheng Zhu, J. E. Menard* Institute of Plasma Physics, Chinese Academy of Science, P.O. Box 1126, Hefei , P. R. China *
An inductor is a wire coil usually wrapped around an iron core
Monday, April 23, PHYS , Spring 2007 Dr. Andrew Brandt PHYS 1444 – Section 004 Lecture #19 Monday, April 23, 2007 Dr. Andrew Brandt Inductance.
1 JE 2.3 : X2 breakdown assist in presence of E tor Toroidal dynamics is expected to be important for breakdown process, especially if ionization avalanche.
Solenoid Free Plasma Start-up Mid-Run Summary (FY 2008) R. Raman and D. Mueller Univ. of Wash. / PPPL 16 April 2008, PPPL 1 Supported by Office of Science.
1Field-Aligned SOL Losses of HHFW Power and RF Rectification in the Divertor of NSTX, R. Perkins, 11/05/2015 R. J. Perkins 1, J. C. Hosea 1, M. A. Jaworski.
Biased Electrode Experiment S.J. Zweben, R.J. Maqueda, L. Roquemore, R.J. Marsala, Y. Raitses, R. Kaita, C. Bush R.H. Cohen, D.D. Ryutov, M. Umansky (LLNL)
NSTX Supported by NSTX Centerstack Upgrade Project Meeting P. Titus Sept 1, 2010 Status of Disruption Simulations.
Self Inductance and RL Circuits
Development and Assessment of “X-point limiter” Plasmas M. Bell, R. Maingi, K-C. Lee Coping with both steady-state and transient (ELM) heat loads is a.
Thursday August 2, PHYS 1444 Ian Howley PHYS 1444 Lecture #15 Thursday August 2, 2012 Ian Howley Dr. B will assign final (?) HW today(?) It is due.
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
Finally! Flux! Electromagnetic Induction. Objectives.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
                                                                  Electro Magnets.
2D Free Jet Simulations (FLUENT)
Energy in a capacitor is stored
Finite difference code for 3D edge modelling
Deviations from the Ideal I-V Behavior
Flux density produced by a long coil (solenoid)
Presentation transcript:

Flux-surface closure DRAFT Bick Hooper July 11, 2012

2 Flux-surface closure –– new simulation results NSTX–– forms a significant volume of closed flux after the injection voltage is shorted –Flux-surface closure was supported by oPhotographs showing the boundaries of a substantial volume of flux with the geometry of a closed surface oEFIT reconstructions oPersistence of toroidal current for a long time with no current drive oThe ability to transition to an Ohmically-driven plasma –A similar result was observed in HIT-II Simulation –– forms a closed volume with an X-point near the bottom of NSTX –Closure occurs due to resistive effects in axisymmetric simulations –Conditions on the boundary need to be adjusted correctly: oThe injector bias-flux drops to zero on a few ms time scale oThe injector slot is narrow (4 cm as in the experiment) (Small closed flux forms with wide slot.) –Volume is smaller than observed in the experiment and does not persist as long –Transition to an Ohmically-driven plasma has not been attempted

3 Flux-surface closure –– after crowbarring injector voltage Comments The injector current is measured by RB  above the injector slot. Closure verified by field-line tracing X-point in poloidal flux occurs after the (measured) injector current reaches zero X-point does not form if the bias poloidal magnetic field is constant As the toroidal current decays, the closed flux region decouples from the X-point and the closed-flux region shrinks in volume

4 Current flow near bottom plate depends on slot width Current flow in flux bubble Current flow along bottom during injection – plots of RB  Narrow slot (4 cm)Wide slot (11 cm) The narrow slot generates a narrower distribution of current and a stronger flow of return current along the bottom plate to the slot

5 Turning-off the injector bias coils drives flux-surface closure Bias field turned off Narrow slot (4 cm) Constant bias field Narrow slot (4 cm) Almost no current flows at >10 ms if the bias field is held constant