Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

EXTENDED MHD SIMULATIONS: VISION AND STATUS D. D. Schnack and the NIMROD and M3D Teams Center for Extended Magnetohydrodynamic Modeling PSACI/SciDAC.
Where are we in Integrated modeling? S. Jardin Mature 1½ D evolution code packages exist with reduced modules for most processes –Japan: BPSI: (TASK, TOPICS)
Physics Basis of FIRE Next Step Burning Plasma Experiment Charles Kessel Princeton Plasma Physics Laboratory U.S.-Japan Workshop on Fusion Power Plant.
ASSOCIATION EURATOM HELLENIC REPUBLIC (and CYPRUS) (HELLAS) FOUNDATION FOR RESEARCH AND TECHNOLOGY-HELLAS NATIONAL CENTRE FOR SCIENTIFIC RESEARCH “DEMOKRITOS”
Stability, Transport, and Conrol for the discussion Y. Miura IEA/LT Workshop (W59) combined with DOE/JAERI Technical Planning of Tokamak Experiments (FP1-2)
FES International Collaboration Program: Vision and Budget Steve Eckstrand International Program Manager Office of Fusion Energy Sciences U.S. Department.
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.
ELECTRON CYCLOTRON SYSTEM FOR KSTAR US-Korea Workshop Opportunities for Expanded Fusion Science and Technology Collaborations with the KSTAR Project Presented.
Introduction to Spherical Tokamak
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
Exploration of Fusion Plasmas Using Integrated Simulations Jill Dahlburg, Naval Research Laboratory Presented by Dale Meade, Princeton University With.
C. Kessel Princeton Plasma Physics Laboratory For the NSTX National Team DOE Review of NSTX Five-Year Research Program Proposal June 30 – July 2, 2003.
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.
The SWIM Fast MHD Campaign Presented by S. C. Jardin Princeton Plasma Physics Laboratory P.O. Box 451 Princeton, NJ Simulation of Wave Interaction.
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.
Analysis and Simulations of the ITER Hybrid Scenario C. Kessel, R. Budny, K. Indireshkumar Princeton Plasma Physics Laboratory, USA ITPA Topical Group.
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.
Integrated Modeling and Simulations of ITER Burning Plasma Scenarios C. E. Kessel, R. V. Budny, K. Indireshkumar, D. Meade Princeton Plasma Physics Laboratory.
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.
ITER Standard H-mode, Hybrid and Steady State WDB Submissions R. Budny, C. Kessel PPPL ITPA Modeling Topical Working Group Session on ITER Simulations.
Current Drive for FIRE AT-Mode T.K. Mau University of California, San Diego Workshop on Physics Issues for FIRE May 1-3, 2000 Princeton Plasma Physics.
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.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
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.
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.
D. Moreau, ITPA-IOS Meeting, Kyoto, October 18-21, 2011 LEHIGH U N I V E R S I T Y First Integrated Magnetic and Kinetic Control for AT Scenarios on DIII-D.
Simulation and Analysis of the Hybrid Operating Mode in ITER C. Kessel, R. Budny, and K. Indireshkumar Princeton Plasma Physics Laboratory Symposium On.
Integrated Modeling for Burning Plasmas Workshop (W60) on “Burning Plasma Physics and Simulation 4-5 July 2005, University Campus, Tarragona, Spain Under.
PPPL International Collaboration Activities J. R. Wilson Head Off-site Research Department Princeton Plasma Physics Laboratory 4th US-PRC Magnetic Fusion.
Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu
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.
MHD Suppression with Modulated LHW on HT-7 Superconducting Tokamak* Support by National Natural Science Fund of China No J.S.Mao, J.R.Luo, B.Shen,
1 13 th ITPA Transport Physics Group Meeting Naka, 1-3 October 2007 V. Mukhovatov ITER Rotation Issues.
D. McCune 1 PTRANSP Predictive Upgrades for TRANSP.
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*
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,
ITER STEADY-STATE OPERATIONAL SCENARIOS A.R. Polevoi for ITER IT and HT contributors ITER-SS 1.
B WEYSSOW 2009 Coordinated research activities under European Fusion Development Agreement (addressing fuelling) Boris Weyssow EFDA-CSU Garching ITPA 2009.
Summary CDBM IMAGE meeting, 07 IMAGE SUMMARY IMAGE set up to provide a venue for discussion between the different Integrated Modelling (IM) activities.
Comprehensive ITER Approach to Burn L. P. Ku, S. Jardin, C. Kessel, D. McCune Princeton Plasma Physics Laboratory SWIM Project Meeting Oct , 2007.
RFX workshop / /Valentin Igochine Page 1 Control of MHD instabilities. Similarities and differences between tokamak and RFP V. Igochine, T. Bolzonella,
L. Zanotto – 10 February 2011 – RFX-mod programme workshop TF2: Active control of RFP and tokamak plasmas Report on experimental proposals L. Zanotto,
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.
Dependence of Pedestal Structure on Ip and Bt A. Diallo, R. Maingi, S. Zweben, B.P. LeBlanc, B. Stratton, J. Menard, S. Gerhardt, J. Canick, A. McClean,
Advanced Tokamak Modeling for FIRE C. Kessel, PPPL NSO/PAC Meeting, University of Wisconsin, July 10-11, 2001.
Integrated Modeling for Burning Plasmas Workshop (W60) on “Burning Plasma Physics and Simulation 4-5 July 2005, University Campus, Tarragona, Spain Under.
FY WEP TSG Goals & WEP-Relevant Diagnostic Upgrades NSTX Supported by WEP TSG Meeting September 14,
ITPA CDB&M and TP Topical Group Meetings, Lausanne, 7-10 May D Campbell ITER International Organization Acknowledgements: W Houlberg, V Mukhovatov,
1PAC-37, Plasma control algorithm development on NSTX-U using TRANSP, M.D. Boyer, 1/26/2016 Dan Boyer for the Integrated Scenarios science group Plasma.
Simulation of Non-Solenoidal Current Rampup in NSTX C. E. Kessel and NSTX Team Princeton Plasma Physics Laboratory APS-DPP Annual Meeting, Savannah, Georgia,
NSTX Meeting name – abbreviated presentation title, abbreviated author name (??/??/20??) Goals of NSTX Advanced Scenario and Control TSG Study, implement,
Integrated Plasma Simulations C. E. Kessel Princeton Plasma Physics Laboratory Workshop Toward an Integrated Plasma Simulation Oak Ridge, TN November 7-9,
1 ASTRA simulations of ITER long pulse scenarios V. Leonov ASTRA simulations of ITER long pulse scenarios V. Leonov Kurchatov Institute, Moscow, Russia.
NSTX-U Waves & Energetic Particles Theory/Experiment Joint Research Topics Supported by Gary Taylor Mario Podestà Nikolai Gorelenkov NSTX-U NSTX-U Theory.
AES, ANL, Boeing, Columbia U., CTD, GA, GIT, LLNL, INEEL, MIT, ORNL, PPPL, SNL, SRS, UCLA, UCSD, UIIC, UWisc FIRE Collaboration FIRE.
NSTX S. A. Sabbagh XP452: RWM physics with initial global mode stabilization coil operation  Goals  Alter toroidal rotation / examine critical rotation.
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.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
Overview of PPPL Field Work Proposal Opportunities in Macroscopic Stability J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005 Supported.
J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005
Lower Ip Long Pulse H+ITB Advanced Scenarios
Lower Ip Long Pulse L-mode and H-mode Advanced Scenarios
C. Kessel, PPPL Standard breakdown is done at 5.4 T
Integrated Modeling for Burning Plasmas
Presentation transcript:

Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004

Integrated Simulations Combined with Stand-alone Analysis for KSTAR Develop steady state advanced scenario simulations –Magnetics/position, shape, current reconstruction and control –Auxiliary heating/CD systems ---> models and control –MHD stability and control –Profile evolution ----> setup and control –Perturbations simulations to examine energy, particle, current transport responses and control –Utilize sophisticated physics models for benchmarks –Determine response to installed powers, and help plan upgrade sequences ??

KSTAR Can Benefit From and Provide Feedback for Fusion Simulation Efforts Experiments (constraints on theory, and practical constraints on assumptions, B.C.s, includes expansion of interpretation tools) Sophisticated Physics Modeling (stand alone, physics topical specific, algorithms judged against versatility and comp. speed) Integrated Simulation (fast enough for parametrics) Standardized integrated modeling tool(s) for predictive and interpretive simulations

Several Aspects to Integrated Simulations -- What is most critical for KSTAR? More physics models in the integrated simulations More sophisticated (more accurate/detailed) models in the integrated simulations More experimental benchmarks/verifications of individual physics models and integrated simulations which use those models More benchmarks between integrated simulations physics models and stand-alone sophisticated physics models Development of faster or more versatile physics models Improvement of integrated simulation core/interface/data tools Establish simultaneous Near term goals Mid term goals Long term goals

KSTAR Has Unique Capabilities That Make for a Complex Research Plan 4 sources (NBI, LH, EC, ICRF) Strong shaping Long pulse Divertor/pumping Present-day diagnostics DIII-D like, C-Mod like, and ITER like AT-modes NTM & RWM onset and stabilization or avoidance Impurity control for power handling Non-solenoidal current rampup Global control strategies for shape, density, stored energy, current profile, transport, and disruption avoidance Impact of nonlinear n, T, and j transport profile responses

Proposal Free-boundary integrated discharge simulations of KSTAR advanced tokamak operating scenarios 0D systems analysis to identify viable power-CD-stored energy solutions ---> including engineering constraints (power handling, etc.) Tokamak simulation code coupled with required modules Stand-alone analyses as required (more sophisticated physics models) Examine Phase I (20 s) operating space Examine Phase II (300 s) operating space ---> Identify CD limitations, auxiliary system power requirements and plasma operating parameters (n, Ip, B T, etc.) of self-consistent configurations ---> Examine controllability of current profile, plasma shape, and stored energy simultaneously ---> Identify best auxiliary system upgrade choices and impact of uncertainties on performance (transport, density control, etc.) Modest funding -----> analysis with existing computational tools Increased funding -----> more extensive integrated modeling tool development KSTAR’s near term operation can serve as guide and test bed for SciDAC and FSP efforts, as well as NSTX, DIII-D and C-Mod modeling

Proposal s 1st plasma upgrade start initial operationbaseline operation Integrated modeling effort for 20 s baseline operation, with some modeling for 300 s Extensive interpretive modeling and predictive model (300s) development/correction from expts results  high performance  Long pulse, high f NI  AT modes  Advanced control What should we be doing now??