Parallel coupling: problems arising in the context of magnetic fusion John R. Cary Professor, University of Colorado CEO, Tech-X Corporation.

Slides:



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

Ion Heating and Velocity Fluctuation Measurements in MST Sanjay Gangadhara, Darren Craig, David Ennis, Gennady Fiskel and the MST team University of Wisconsin-Madison.
Reconnection: Theory and Computation Programs and Plans C. C. Hegna Presented for E. Zweibel University of Wisconsin CMSO Meeting Madison, WI August 4,
Glenn Bateman Lehigh University Physics Department
EXTENDED MHD SIMULATIONS: VISION AND STATUS D. D. Schnack and the NIMROD and M3D Teams Center for Extended Magnetohydrodynamic Modeling PSACI/SciDAC.
Physics of fusion power
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
Particle acceleration in a turbulent electric field produced by 3D reconnection Marco Onofri University of Thessaloniki.
Simulations of the core/SOL transition of a tokamak plasma Frederic Schwander,Ph. Ghendrih, Y. Sarazin IRFM/CEA Cadarache G. Ciraolo, E. Serre, L. Isoardi,
Algorithm Development for the Full Two-Fluid Plasma System
Physics of fusion power Lecture 6: Conserved quantities / Mirror device / tokamak.
INTRODUCTION OF WAVE-PARTICLE RESONANCE IN TOKAMAKS J.Q. Dong Southwestern Institute of Physics Chengdu, China International School on Plasma Turbulence.
1 A component mode synthesis method for 3D cell by cell calculation using the mixed dual finite element solver MINOS P. Guérin, A.M. Baudron, J.J. Lautard.
Measurement of magnetic island width by using multi-channel ECE radiometer on HT-7 tokamak Han Xiang( 韩翔 ), Ling Bili( 凌必利 ), Gao Xiang( 高翔 ), Liu Yong(
Effect of sheared flows on neoclassical tearing modes A.Sen 1, D. Chandra 1, P. K. Kaw 1 M.P. Bora 2, S. Kruger 3, J. Ramos 4 1 Institute for Plasma Research,
Physics of fusion power Lecture 8: Conserved quantities / mirror / tokamak.
Physics of fusion power
Examples of using Langevin equation to solve FP equation.
Physics of fusion power Lecture 7: particle motion.
Presented by High-Performance Computing in Magnetic Fusion Energy Research Donald B. Batchelor RF Theory Plasma Theory Group Fusion Energy Division.
Turbulent transport in collisionless plasmas: eddy mixing or wave-particle decorrelation? Z. Lin Y. Nishimura, I. Holod, W. L. Zhang, Y. Xiao, L. Chen.
T. Hellsten IEA Burning Plasma Workshop, July 2005 Tarragona Spain Integrated Modelling of ICRH and AE Dynamics T. Hellsten, T. Bergkvist, T. Johnson and.
Computer simulations of fast frequency sweeping mode in JT-60U and fishbone instability Y. Todo (NIFS) Y. Shiozaki (Graduate Univ. Advanced Studies) K.
Nils P. Basse Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge, MA USA ABB seminar November 7th, 2005 Measurements.
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,
Massively Parallel Magnetohydrodynamics on the Cray XT3 Joshua Breslau and Jin Chen Princeton Plasma Physics Laboratory Cray XT3 Technical Workshop Nashville,
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.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
D. McCune 1 Plasma State Representation XPLASMA – Tool for Representation of Equilibrium, Fields and Profiles Available at:
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.
THE PROBLEM; THE SUCCESSES; THE CHALLENGES HPC Users Forum Houston, TX April 6, 2011 Lee A. Berry Colleagues and Collaborators special thanks.
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
Introduction to the Particle In Cell Scheme for Gyrokinetic Plasma Simulation in Tokamak a Korea National Fusion Research Institute b Courant Institute,
Challenging problems in kinetic simulation of turbulence and transport in tokamaks Yang Chen Center for Integrated Plasma Studies University of Colorado.
Physics of fusion power Lecture 10: tokamak – continued.
PLASMA HEATING AND HOT ION SUSTAINING IN MIRROR BASED HYBRIDS
Nonlinear Extended MHD Simulation Using High-Order Finite Elements C. Sovinec, C. Kim, H. Tian, Univ. of WI-Madison D. Schnack, A. Pankin, Science Apps.
10th ITPA conference, Avila, 7-10 Jan Effects of High Energy Ions Accelerated in front of ICRF Antennas in LHD S. Masuzaki on behalf of the LHD Experimental.
Dynamics of ITG driven turbulence in the presence of a large spatial scale vortex flow Zheng-Xiong Wang, 1 J. Q. Li, 1 J. Q. Dong, 2 and Y. Kishimoto 1.
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued.
11 Association Euratom-Cea The PION code L.-G. Eriksson Association EURATOM-CEA, CEA/DSM/IRFM, CEA-Cadarache, St. Paul lez Durance, France T. Hellsten.
(National Institute for Fusion Science, Japan)
FCC electron cloud study plan K. Ohmi (KEK) Mar FCC electron cloud study meeting CERN.
M. Onofri, F. Malara, P. Veltri Compressible magnetohydrodynamics simulations of the RFP with anisotropic thermal conductivity Dipartimento di Fisica,
Hybrid MHD-Gyrokinetic Simulations for Fusion Reseach G. Vlad, S. Briguglio, G. Fogaccia Associazione EURATOM-ENEA, Frascati, (Rome) Italy Introduction.
DIFFER is part ofand Modelling of ECCD applied for NTM stabilization E. Westerhof FOM Institute DIFFER Dutch Institute for Fundamental Energy Research.
Jungpyo Lee Plasma Science & Fusion Center(PSFC), MIT Parallelization for a Block-Tridiagonal System with MPI 2009 Spring Term Project.
Comprehensive ITER Approach to Burn L. P. Ku, S. Jardin, C. Kessel, D. McCune Princeton Plasma Physics Laboratory SWIM Project Meeting Oct , 2007.
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.
Work with TSC Yong Guo. Introduction Non-inductive current for NSTX TSC model for EAST Simulation for EAST experiment Voltage second consumption for different.
Partially-relaxed, topologically-constrained MHD equilibria with chaotic fields. Stuart Hudson Princeton Plasma Physics Laboratory R.L. Dewar, M.J. Hole.
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:
Discussion Slides S.E. Kruger, J.D. Callen, J. Carlson, C.C. Hegna, E.D. Held, T. Jenkins, J. Ramos, D.D. Schnack, C.R. Sovinec, D.A. Spong ORNL SWIM Meet.
Presented by High Performance Computing in Magnetic Fusion Energy Research Donald B. Batchelor RF Theory Plasma Theory Group Fusion Energy Division.
Ergodic heat transport analysis in non-aligned coordinate systems S. Günter, K. Lackner, Q. Yu IPP Garching Problems with non-aligned coordinates? Description.
21st IAEA Fusion Energy Conf. Chengdu, China, Oct.16-21, /17 Gyrokinetic Theory and Simulation of Zonal Flows and Turbulence in Helical Systems T.-H.
Center for Extended MHD Modeling (PI: S. Jardin, PPPL) –Two extensively developed fully 3-D nonlinear MHD codes, NIMROD and M3D formed the basis for further.
The mass of the nuclei produced is less than the mass of the original two nuclei The mass deficit is changed into energy We can calculate the energy released.
Nonlinear Simulations of Energetic Particle-driven Modes in Tokamaks Guoyong Fu Princeton Plasma Physics Laboratory Princeton, NJ, USA In collaboration.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
Presented by Yuji NAKAMURA at US-Japan JIFT Workshop “Theory-Based Modeling and Integrated Simulation of Burning Plasmas” and 21COE Workshop “Plasma Theory”
Interaction between vortex flow and microturbulence Zheng-Xiong Wang (王正汹) Dalian University of Technology, Dalian, China West Lake International Symposium.
Resistive Modes in CDX-U J. Breslau, W. Park. S. Jardin, R. Kaita – PPPL D. Schnack, S. Kruger – SAIC APS-DPP Annual Meeting Albuquerque, NM October 30,
APS DPP 2006 October Dependence of NTM Stabilization on Location of Current Drive Relative to Island J. Woodby 1 L. Luo 1, E. Schuster 1 F. D.
Nonlinear plasma-wave interactions in ion cyclotron range of frequency N Xiang, C. Y Gan, J. L. Chen, D. Zhou Institute of plasma phsycis, CAS, Hefei J.
Energetic ion excited long-lasting “sword” modes in tokamak plasmas with low magnetic shear Speaker:RuiBin Zhang Advisor:Xiaogang Wang School of Physics,
54 th APS-DPP Annual Meeting, October 29 - November 2, 2012, Providence, RI Study of ICRH and Ion Confinement in the HSX Stellarator K. M. Likin, S. Murakami.
An overview of turbulent transport in tokamaks
Studies of Bias Induced Plasma Flows in HSX
Mikhail Z. Tokar and Mikhail Koltunov
Presentation transcript:

Parallel coupling: problems arising in the context of magnetic fusion John R. Cary Professor, University of Colorado CEO, Tech-X Corporation

2 The nuclear fusion produces energy: D + T  (He MeV) + (n MeV) Neutron energy (14 MeV) collected at walls Courtesy of Don Batchelor, ORNL Alpha energy (3.5 MeV) deposited in plasma

3 Heat (to overcome repulsion) and hold particles in magnetic traps Heat the particles so that the average energy is ~ 100,000,000F (plasma) Contain plasma for many reactions to happen Not overheat, which can lead to instability or confinement reduction B Figures from Don Batchelor

4 MHD codes compute growth of harmful structures Particles move rapidly along field lines Topology change means hot particle near inside can reach outside Temperature flattens over width of island

5 ICRF fast waves and mode converted ion Bernstein and ion cyclotron waves in Alcator C-Mod and ASDEX Upgrade. RF codes used to predict deposition of wave energy and momentum TORIC: Solves both the ICRF and LHRF wave equation Uses a mixed finite element - spectral basis representation. Solves block tri-diagonal with Scalapack. Scalable solver allows millimeter resolution Full-wave LHRF field solutions at millimeter wavelengths over the entire tokamak cross-section.

6 Coupling RF and MHD can eliminate the harmful structures Localized momentum deposition differential on the particles Currents can be induced –Local: counteract current spike near island –Global: counteract island drive (  ′, q) Not much current required (I RF /I plasma ~ 3%) Center island current out of plane

7 Prediction of process requires coupling of very different parallel codes TORIC: RF code computing –Toroidally fourier –Poloidally fourier –Finite element in minor radius –1D decomposition NIMROD: MHD evolution –Toroidally fourier –Finite elements radially and poloidally –2D decomposition

8 Spatial Domain Transformations All needed transformations are linear, and can be implemented as matrix-vector multiplication v g B (t) = F B C B v B (t) v g A (t) = GT AB v g B (t) v A (t) = C A (M A ) -1 F A v g A (t) Code B representation Transformation to cylindrical coordinate system Possible Fourier synthesis MxN coupler Evaluation at Gauss quadrature points Possible Fourier analysis Mass matrix inversion to find representation for code B Transformation from cylindrical coordinate system Code A representation

9 Questions Should we be generic? –Is the performance hit of being generic excessive? –Should we do a particular problem first? –How will we overlap communication and computation? How do we get there? –Is retrofitting old codes the way to go –Do we need a new framework for component management?