Overview of PPPL Field Work Proposal Opportunities in Macroscopic Stability J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005 Supported.

Slides:



Advertisements
Similar presentations
EXTENDED MHD SIMULATIONS: VISION AND STATUS D. D. Schnack and the NIMROD and M3D Teams Center for Extended Magnetohydrodynamic Modeling PSACI/SciDAC.
Advertisements

Physics Basis of FIRE Next Step Burning Plasma Experiment Charles Kessel Princeton Plasma Physics Laboratory U.S.-Japan Workshop on Fusion Power Plant.
YQ Liu, Peking University, Feb 16-20, 2009 Resonant Field Amplification Yueqiang Liu UKAEA Culham Science Centre Abingdon, Oxon OX14 3DB, UK.
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Session II MHD Stability and Fast Particle Confinement General scope.
YQ Liu, Peking University, Feb 16-20, 2009 Active Control of RWM Yueqiang Liu UKAEA Culham Science Centre Abingdon, Oxon OX14 3DB, UK.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
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.
NSTX The Resistive Wall Mode and Beta Limits in NSTX S. A. Sabbagh 1, J. Bialek 1, R. E. Bell 2, A. H. Glasser 3, B. LeBlanc 2, J.E. Menard 2, F. Paoletti.
M.E. Fenstermacher - Summary of Progress and Outlook for Work Plan in PEP ITPA WG on RMP ELM Control 4/23/09 11:15 PM 1 PEP ITPA Working Group on RMP ELM.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
NSTX S. A. Sabbagh XP501: MHD spectroscopy of wall stabilized high  plasmas  Motivation  Resonant field amplification (RFA) observed in high  NSTX.
TOTAL Simulation of ITER Plasmas Kozo YAMAZAKI Nagoya Univ., Chikusa-ku, Nagoya , Japan 1.
High priority MHD research coordination in preparation for the 2008 FWP D. A. Gates, MHD SFG Leader MHD Science Focus Group Meeting B318 PPPL December.
Overview of MHD and extended MHD simulations of fusion plasmas Guo-Yong Fu Princeton Plasma Physics Laboratory Princeton, New Jersey, USA Workshop on ITER.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
TH/7-2 Radial Localization of Alfven Eigenmodes and Zonal Field Generation Z. Lin University of California, Irvine Fusion Simulation Center, Peking University.
S.A. Sabbagh for NSTX Macrostability TSG Macrostability TSG Suggested FY-12 Milestones – Address key ReNeW issues for ST development 1) Assess sustained.
Challenging problems in kinetic simulation of turbulence and transport in tokamaks Yang Chen Center for Integrated Plasma Studies University of Colorado.
US ITER UFA Meeting APS-DPP Savannah, GA Ned Sauthoff (presented by Dale Meade) November 15, 2004 US In-kind Contributions and Starting Burning Plasma.
Discussions and Summary for Session 1 ‘Transport and Confinement in Burning Plasmas’ Yukitoshi MIURA JAERI Naka IEA Large Tokamak Workshop (W60) Burning.
MHD Limits to Tokamak Operation and their Control Hartmut Zohm ASDEX Upgrade credits: G. Gantenbein (Stuttgart U), A. Keller, M. Maraschek, A. Mück DIII-D.
Resonant magnetic perturbation effect on the tearing mode dynamics in EXTRAP T2R: experimental results and modeling L. Frassinetti, K.E.J. Olofsson, P.R.
G.Huysmansworkshop : Principles of MHD 21-24/3/2005 MHD in Tokamak Plasmas Guido Huysmans Association Euratom/CEA Cadarache, France with contributions.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
Global Stability Issues for a Next Step Burning Plasma Experiment UFA Burning Plasma Workshop Austin, Texas December 11, 2000 S. C. Jardin with input from.
Integrated Modeling for Burning Plasmas Workshop (W60) on “Burning Plasma Physics and Simulation 4-5 July 2005, University Campus, Tarragona, Spain Under.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
1 13 th ITPA Transport Physics Group Meeting Naka, 1-3 October 2007 V. Mukhovatov ITER Rotation Issues.
Compact Stellarator Approach to DEMO J.F. Lyon for the US stellarator community FESAC Subcommittee Aug. 7, 2007.
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.
ITPA Topical Group on MHD, Control, and Disruptions Summary of 5th meeting, Nov. 8-10, 2004 Presented by Ted Strait Workshop on MHD Mode Control Princeton,
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
RFX-mod Programme Workshop, 20-22/01/09, Padova - T. Bolzonella1 Tommaso Bolzonella on behalf of RFX-mod team Consorzio RFX- Associazione Euratom-ENEA.
DISCUSSION OF ISSUES, OPPORTUNITIES AND CONCLUSIONS FOR ROTATION AND MOMENTUM TRANSPORT SESSIONS 10th ITPA Transport Physics and CDBM TG Meetings Princeton.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
MHD Stability Research Program on Alcator C-Mod Presented by R. Granetz Alcator C-Mod PAC Feb 2004.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
SUMMARY OF 4th IPTA TRANSPORT AND ITB PHYSICS TG MEETING St. Petersburg, Russia, April 8-11, 2003 Presented by E.J. Doyle for the TG Note: this summary.
QAS Design of the DEMO Reactor
Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.
Physics Analysis and Flexibility Issues for FIRE NSO PAC-2 Meeting January 17-18, 2001 S. C. Jardin with input from C.Kessel, J.Mandrekas, D.Meade, and.
Comments on Fusion Development Strategy for the US S. Prager Princeton Plasma Physics Laboratory FPA Symposium.
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Taming The Physics For Commercial Fusion Power Plants ARIES Team Meeting.
Princeton Plasma Physics Laboratory Highlights of Theory Accomplishments and Plans Department of Energy Budget Planning Meeting March 13-15, 2001.
MCZ MCZ NCSX Mission Acquire the physics data needed to assess the attractiveness of compact stellarators; advance understanding.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
FY WEP TSG Goals & WEP-Relevant Diagnostic Upgrades NSTX Supported by WEP TSG Meeting September 14,
Nonlinear Simulations of Energetic Particle-driven Modes in Tokamaks Guoyong Fu Princeton Plasma Physics Laboratory Princeton, NJ, USA In collaboration.
SWIM Meeting Madison, WI 12/4/07 A closure scheme for modeling RF modifications to the fluid equations C. C. Hegna and J. D. Callen University of Wisconsin.
NSTX Meeting name – abbreviated presentation title, abbreviated author name (??/??/20??) Goals of NSTX Advanced Scenario and Control TSG Study, implement,
NSTX-U Waves & Energetic Particles Theory/Experiment Joint Research Topics Supported by Gary Taylor Mario Podestà Nikolai Gorelenkov NSTX-U NSTX-U Theory.
NSTX SAS – GMS Mtg. 12/1/04 S. A. Sabbagh and J. E. Menard NSTX RWM Active Feedback System Implementation Plan Discussion NSTX Global Mode Stabilization.
NSTX S. A. Sabbagh XP452: RWM physics with initial global mode stabilization coil operation  Goals  Alter toroidal rotation / examine critical rotation.
Stellarator-Related MHD Research H. Neilson MHD Science Focus Group meeting December 12, 2008 MHD Science Focus Group, Dec. 12, 2008.
6 th ITPA MHD Topical Group Meeting combined with W60 IEA Workshop on Burning Plasmas Summary Session II MHD Stability and Fast Particle Confinement chaired.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
12/15/04Team Meeting Physics Analysis NSTX Team Meeting S.M. Kaye 12/15/04 Publications –Some IAEA papers submitted to Nuc. Fusion –T. Biewer article submitted.
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.
J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
Influence of energetic ions on neoclassical tearing modes
20th IAEA Fusion Energy Conference,
Integrated Modeling for Burning Plasmas
Stellarator Program Update: Status of NCSX & QPS
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

Overview of PPPL Field Work Proposal Opportunities in Macroscopic Stability J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005 Supported by Office of Science

ITPA, ITER, and PPPL research in MHD - overview Overview of near-term high priority MHD research for ITPA/ITER Possible contributions of NSTX, Theory, and off-site research to international MHD efforts Longer-term MHD research opportunities for PPPL beyond ITPA near-term priorities

High Priority Research Areas for 2005/6 proposed by the MHD ITPA Topical Group (1) For NTMs complete 2/1  * scaling studies, validate ECCD control models against data (including modulation), develop sawtooth seed island control to high beta and high fast particle regimes, initiate development of a 3D MHD model (including seeding) and specify diagnostics for NTM detection. For RWMs understand mode damping through cross-machine experiments. Study n≠1 RWMs. Benchmark theory models for RWM feedback and experimentally study feedback control at low rotation. Study coil systems for RWM control in ITER and specify diagnostics. Specify high beta error field criterion. Construct new disruption DB including conventional and advanced scenarios to initially study fast Ip quenches and then runaway electrons.

High Priority Research Areas for 2005/6 proposed by the MHD ITPA Topical Group (2) Develop disruption mitigation techniques particularly at high performance and by noble gas injection and understand influence of MHD on gas penetration. Validate DINA and/or TSC on gas injection. Develop reliable disruption prediction methods. Understand intermediate-n AEs ; redistribution of fast particles from AEs; and perform theory-data comparisons on damping and stability. Specify for ITER the low frequency noise in the diagnostic signals used in feedback loops (for both RWM and vertical control).

Potential contributions of NSTX and Theory to High Priority ITPA Research Areas in MHD NTM –NSTX Use MSE + low-A to test NTM threshold theory - perform NSTX/DIII-D cross machine NTM experiments Utilize PEST-3 and M.R. equation to explore NTM seeding physics – still poorly understood –Theory Development of NC viscosity models in M3D for NTM potentially very useful Sawtooth modeling in M3D important for seeding physics RWM –NSTX Extensive experiments on critical rotation physics and MHD spectroscopy + role of error fields For ITER - Perform RWM feedback experiments in low-rotation plasmas to test feedback control physics/modeling –Theory M3D modeling of RWM needs better dissipation model and control coils + controller MARS-F analysis of n > 1 critical rotation started – will extend to feedback modeling

Potential contributions of NSTX and Theory to High Priority ITPA Research Areas in MHD Disruption database –NSTX to contribute data, but may need help with software interface to database –Theory Extensive M3D modeling of VDE + high-beta disruptions already performed Study gas jet penetration (via MHD modes) physics for disruption mitigation – currently studied with NIMROD AE modes –NSTX Unique ability to study modes at ITER-relevant v fast /v A AND measure q- profile Studying role of q-profile on modes + impact of modes on FI confinement and NBI driven current –Theory Nonlinear treatment of single TAE in reasonable agreement with experiment Working on alpha transport in ITER from multiple AE modes – enhancing damping physics in M3D

Possible burning plasma MHD research opportunities for PPPL beyond ITPA near-term priorities Usage of 3D fields for ELM control –ELM control critical for protecting ITER divertor and PFCs –How 3D externally applied fields impact edge stability and transport is poorly understood –Can we better leverage 3D tools from stellarator to model 3D perturbed tokamaks and test against NSTX and DIII-D? Possible role for M3D also? Error fields – angular momentum transport and island formation –Error field amplification not well understood (leverage same codes above?) How does the 3D field impact toroidal “viscosity”/rotation and transport? How does the amplification scale with beta? What is the structure of the amplified field? –Locked island formation concern during ITER low-density Ip ramp-up phase ITPA performing locked-mode identity experiments to develop scaling law that will supposedly apply ITER First principles 2-fluid theory needed to understand physics of island shielding & formation + predict mode “natural” frequency and therefore locking threshold

MHD SFG input to FWP – discussion (1) NSTX Macroscopic Stability Milestones through 2007 –R2(06-2) Characterize the effectiveness of active feedback control of resonant error fields using closed-loop control of currents in ex- vessel correction coils. –R2(07-2) Characterize the effectiveness of active feedback control of wall-coupled, pressure-limiting global modes, using closed-loop control of currents in ex-vessel correction coils. DIII-D collaboration future accomplishments –2006 research develop realistic VACUUM code model of feedback circuit Establish active feedback in low rotation target plasmas –2007 research Sustained operation above no-wall limit and sustained  N = 4 utilizing active feedback at low rotation + high-delta divertor configuration

MHD SFG input to FWP – discussion (2) Proposed Theory Activities for FY06 –Continue study of Resistive Wall Modes & ELMs in tokamaks. –Develop a predictive model of neoclassical tearing modes in tokamaks/STs. –Identify mechanisms for disruptions in tokamaks, STs, and stellarators. –Perform physics studies involving collisional effects on hybrid model. Proposed Theory Activities for FY07 –Continue study of resistive wall modes and Elms. –Continue to identify mechanisms for disruptions in tokamaks, STs, and stellarators. –Continue to develop a predictive model of neoclassical tearing modes in tokamaks and STs. –Further improvements in the real-time equilibrium reconstruction algorithms towards the goal of real-time forecasting of tokamak discharges. –Begin study of new physics introduced when the majority population is represented kinetically.

MHD SFG input to FWP – discussion (x) Interests in DIII-D, ITER, future modeling –Sawtooth control for ITER Modeling for ECCD near q=1 Understanding of *AE modes Proposed Theory Activities for FY07 –Continue study of resistive wall modes and Elms. –Continue to identify mechanisms for disruptions in tokamaks, STs, and stellarators. –Continue to develop a predictive model of neoclassical tearing modes in tokamaks and STs. –Further improvements in the real-time equilibrium reconstruction algorithms towards the goal of real-time forecasting of tokamak discharges. –Begin study of new physics introduced when the majority population is represented kinetically.

Leverage 3D physics capabilities of stellarator research to contribute to tokamaks, ST, BP 3D equilibrium 3D stability –Suppression of large ELMs critical for ITER –Recent ELM mitigation results not well understood – need Ergodization of near-edge region, increased transport (PIES) 3D shaping may modify peeling-ballooning stability (Terpsichore) 3D shaping may modify turbulent transport and profiles (see below) –Test on DIII-D and NSTX 3D turbulence –Compute linear stability (FULL code) for ITG in weakly 3D system –NC ripple may damp GAM/Zonal flow, allowing higher turbulence levels and transport Can this be tested in simulations and experiments?

NTM research opportunities Presented by D. A. Gates At the MHD SFG meeting August 25, 2005

Motivation Neoclassical tearing modes are recognized as potentially performance limiting for ITER –ITER Physics Basis, Chapter 3.2 Nucl. Fusion 39 (1999) /1 NTMs have can lock and cause disruptions 3/2 NTMs degrade confinement. There is not a demonstrated ability to predict mode onset from first a first principles theory Most existing analysis is based on high aspect ratio circular cross-section theory (even for STs!)

NTM modeling developments Real geometry –Rosenberg, AL, Gates, DA, Pletzer, A, et al. Modeling of neoclassical tearing mode stability for generalized toroidal geometry PHYS PLASMAS 9 (11): NOV 2002 –Also see work by D. Brennan Onset criteria –Calculate  ’ –Evaluate threshold models (e.g. ion polarization current model and   /  || model)

New research opportunities Include effects of rotation (and shear) on stability Non-linear effects –FIR (Frequently interrupted regime) (S. Gunther, et al.) –effect of NTMs on confinement –Effect of island size on rotation –Mode coupling Kinetic models for mode onset

JET-ITER collaboration The arbitrary geometry code developed by Adam Rosenberg would be a useful contribution to JET-ITER This would require ~1 man-year of effort to develop the code as a more robust tool