The Role of MHD in 3D Aspects of Massive Gas Injection

Slides:



Advertisements
Similar presentations
Institute for Plasma Physics Rijnhuizen Heat load asymmetries in MAST G. De Temmerman a,b, A. Kirk a, E, Nardon a, P. Tamain a, A. Thornton a a Present.
Advertisements

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
Analysis of disruption and RE proposals for MST Piero Martin on behalf of MST1 TFLs.
9th TTF Spain September 11, 2002 B. J. Peterson, NIFS, Japan page 1 Radiative Collapse and Density Limit in the Large Helical Device.
Thermal Load Specifications from ITER C. Kessel ARIES Project Meeting, May 19, 2010 UCSD.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
Halo Current and Resistive Wall Simulations of ITER H.R. Strauss 1, Linjin Zheng 2, M. Kotschenreuther 2, W.Park 3, S. Jardin 3, J. Breslau 3, A.Pletzer.
A. Kirk, 21 st IAEA Fusion Energy Conference, Chengdu, China, October 2006 Evolution of the pedestal on MAST and the implications for ELM power loadings.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
1/14 In/Out balance and time scales of ELM divertor heat load in JET and ASDEX Upgrade T.Eich 1, A.Kallenbach 1, W.Fundamenski 2, A.Herrmann 1, R.A. Pitts.
A. Kirk, 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, 2004 The structure of ELMS and the distribution of transient power loads in MAST Presented.
Nonlinear Simulations of ELMs with NIMROD D.P. Brennan Massachussetts Institute of Technology Cambridge, MA S.E. Kruger Tech-X Corp, Boulder, CO A. Pankin,
Introduction to the disruption JET/MST program E. Joffrin & P. Martin Presented by P. Martin.
Alberto Loarte 10 th ITPA Divertor and SOL Physics Group Avila – Spain 7/10 – 1 – Update on Thermal Loads during disruptions and VDEs A. Loarte.
R Sartori - page 1 20 th IAEA Conference – Vilamoura Scaling Studies of ELMy H-modes global and pedestal confinement at high triangularity in JET R Sartori.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
1 st IAEA Meeting on Fusion Data Processing, Validation and Analysis, June 2015, Nice, France Peter de Vries – © 2015, ITER Organization Page 1 IDM UID:
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.
Divertor/SOL contribution IEA/ITPA meeting Naka Nov. 23, 2003 Status and proposals of IEA-LT/ITPA collaboration Multi-machine Experiments Presented by.
Hybrid Simulations of Energetic Particle-driven Instabilities in Toroidal Plasmas Guo-Yong Fu In collaboration with J. Breslau, J. Chen, E. Fredrickson,
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.
12/03/2013, Praga 1 Plasma MHD Activity Observations via Magnetics Diagnostics: Magnetic island Analysis Magnetic island Analysis Frederik Ostyn (UGent)
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,
14 Oct. 2009, S. Masuzaki 1/18 Edge Heat Transport in the Helical Divertor Configuration in LHD S. Masuzaki, M. Kobayashi, T. Murase, T. Morisaki, N. Ohyabu,
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.
1 R D Pillsbury Sherbrooke Consulting, Inc. OPERA Analyses of the In-vessel Coils for the IDR In-Vessel Coil System Intermediate Design Review –
1) Disruption heat loading 2) Progress on time-dependent modeling C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD, 4/4/2011.
M. Onofri, F. Malara, P. Veltri Compressible magnetohydrodynamics simulations of the RFP with anisotropic thermal conductivity Dipartimento di Fisica,
SLM 2/29/2000 WAH 13 Mar NBI Driven Neoclassical Effects W. A. Houlberg ORNL K.C. Shaing, J.D. Callen U. Wis-Madison NSTX Meeting 25 March 2002.
Behaviour of Runaway Electrons during Injection of High Z Impurities/Gas Puffing in HT-7 S.Sajjad INSTITUTE OF PLASMA PHYSICS,HEFEI CHINA.
R. A. Pitts et al. 1 (12) IAEA, Chengdu Oct ELM transport in the JET scrape-off layer R. A. Pitts, P. Andrew, G. Arnoux, T.Eich, W. Fundamenski,
U NIVERSITY OF S CIENCE AND T ECHNOLOGY OF C HINA CAS K EY L ABORATORY OF B ASIC P LASMA P HYSICS Recent experimental results of zonal flows in edge tokamak.
J. Boedo, UCSD Fast Probe Results and Plans By J. Boedo For the UCSD and NSTX Teams.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
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*
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.
Gas Jet Disruption Mitigation Studies on Alcator C-Mod and DIII-D R.S. Granetz 1, E.M. Hollmann 2, D.G. Whyte 1, V.A. Izzo 1, G.Y. Antar 2, A. Bader 1,
NIMROD Simulations of a DIII-D Plasma Disruption
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
Disruption Mitigation System Developments and Design for ITER L.R. Baylor, C. Barbier, N.D. Bull, J.R. Carmichael, M.N. Ericson, M.S. Lyttle, S.J. Meitner,
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.
TH/7-1Multi-phase Simulation of Alfvén Eigenmodes and Fast Ion Distribution Flattening in DIII-D Experiment Y. Todo (NIFS, SOKENDAI) M. A. Van Zeeland.
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
L.R. Baylor 1, N. Commaux 1, T.C. Jernigan 1, S.J. Meitner 1, N. H. Brooks 2, S. K. Combs 1, T.E. Evans 2, M. E. Fenstermacher 3, R. C. Isler 1, C. J.
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.
Reconnection Process in Sawtooth Crash in the Core of Tokamak Plasmas Hyeon K. Park Ulsan National Institute of Science and Technology, Ulsan, Korea National.
Effects of external non-axisymmetric perturbations on plasma rotation L. Frassinetti, P.R. Brunsell, J.R. Drake, M.W.M. Khan, K.E.J. Olofsson Alfvén Laboratory,
Zhouqian, Wan baonian and spectroscopy team
Disruption Specification in ARIES
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik1, D.L. Brower2, C. Deng2,
Features of Divertor Plasmas in W7-AS
Similarities and differences in SOL physics
T. Markovič1,2, P. Cahyna1, R. Panek1, M. Peterka1,2, P. C
15TH WORKSHOP ON MHD STABILITY CONTROL
Pellet injection in ITER Model description Model validation
Center for Plasma Edge Simulation
R. Granetz1, S. Wolfe1, D. Whyte1, V. Izzo1, M. Reinke1, J. Terry1, A
L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.
Toroidal asymmetry of impurity seeding
First Experiments Testing the Working Hypothesis in HSX:
Dynamics of transient divertor re-attachment
TH/P4-1 27th IAEA FEC, Ahmedabad October 2018
Stabilization of m/n=1/1 fishbone by ECRH
Density Peaking in JET (NBI fueling dominant) and DIII-D (transport dominant) Originates from Different Sources at Low υ* For the first time electron particle.
TPF = max(Prad(fn=1)) /Prad(fn=1)
Disruption rate during whole JET-ILW campaign
Presentation transcript:

The Role of MHD in 3D Aspects of Massive Gas Injection V.A. Izzo,1 N. Commaux,2 N.W. Eidietis,3 R.S. Granetz,4 E. Hollmann,1 G. Huijsmans,7 D.A. Humphreys,3 C.J. Lasnier,3 M. Lehnen,7 A. Loarte,7 R.A. Moyer,1 P.B. Parks,3 C. Paz-Soldan,5 R. Raman,6 D. Shiraki,2 E.J. Strait3 1UCSD, 2ORNL, 3GA, 4MIT, 5ORISE, 6UW, 7ITER IO 25th IAEA Fusion Energy Conference 16 October 2014 TH/4-1

Massive Gas Injection is a leading candidate for disruption mitigation on ITER In the event that a disruption is unavoidable, the goal of massive gas injection (MGI) shutdown is to radiate plasma stored energy in order to: Avoid conduction of large heat loads to the divertor during the thermal quench (TQ), and … Appropriately tailor the current quench (CQ) time to avoid large vessel forces

# of valves & location(s) Radiation toroidal peaking factor (TPF) Goal of massive gas injection is to isotropically radiate plasma stored energy # of valves & location(s) MGI valve Radiation toroidal peaking factor (TPF)

# of valves & location(s) Radiation toroidal peaking factor (TPF) NIMROD modeling finds a more complicated relationship # of valves & location(s) ? MGI valve ? MHD Impurity transport Heat flux Radiation toroidal peaking factor (TPF)

# of valves & location(s) Radiation toroidal peaking factor (TPF) Outline PART I. Key 3D Physics of Massive Gas Injection PART II. DIII-D TPF Predictions & Comparison with Measurements PART III. ITER TPF Predictions # of valves & location(s) ? MGI valve ? MHD Impurity transport Heat flux Radiation toroidal peaking factor (TPF)

Ne plume expansion || to B PART I. Key 3D Physics of Massive Gas Injection NIMROD 4-stage MGI shutdown Pre-TQ Early TQ Late TQ CQ Ne MGI at t=0 MHD None m/n >1 m=1/n=1 Particle Transport Ne plume expansion || to B Radial mixing Heat Transport Slow  conduction Fast || Br conduction V·T convection

PART I. Key 3D Physics of Massive Gas Injection NIMROD 4-stage MGI shutdown NIMROD predictions concerning the role of the n=1 mode have been tested experimentally Pre-TQ Early TQ Late TQ CQ Ne MGI at t=0 NIMROD finds asymmetric impurity spreading for off-midplane injection MHD None m/n >1 m=1/n=1 Particle Transport Ne plume expansion || to B Radial mixing Heat Transport NIMROD multi-valve MGI simulations reveal implications of both effects for optimum valve positioning Slow  conduction Fast || Br conduction V·T convection

PART I. Key 3D Physics of Massive Gas Injection NIMROD 4-stage MGI shutdown NIMROD predictions concerning the role of the n=1 mode have been tested experimentally Pre-TQ Early TQ Late TQ CQ Ne MGI at t=0 NIMROD finds asymmetric impurity spreading for off-midplane injection MHD None m/n >1 m=1/n=1 Particle Transport Ne plume expansion || to B Radial mixing Heat Transport NIMROD multi-valve MGI simulations reveal implications of both effects for optimum valve positioning Slow  conduction Fast || Br conduction V·T convection

NIMROD simulations produced two predictions regarding the role of the 1/1 in an MGI TQ* 1) 1/1 phase determines location of toroidal radiation peaking due to asymmetric convected heat flux 180º 2) Absent other asymmetries, 1/1 phase is anti-aligned with gas jet m/n=1/1 MGI 0º *IZZO, V.A., Phys. Plasmas 20 (2013) 056107.

NIMROD predicted n=1 phase DIII-D experiments: Initial n=1 phase corresponds to NIMROD prediction NIMROD predicted n=1 phase MGI location

DIII-D experiments: n=1 phase at TQ influenced by rotation, error fields Rotation and error field effects (not in simulations) also determine final mode phase at TQ

TQ Wrad asymmetry vs. applied n=1 phase Experiments verify: the phase of the n=1 mode (relative to the gas jet) affects asymmetry TQ Wrad asymmetry vs. applied n=1 phase 0.1  DIII-D experiments: Changing phase of applied n=1 fields changes measured radiation asymmetry during TQ 0.0 Radiated energy asymmetry -0.1 -0.2 -0.3

PART I. Key 3D Physics of Massive Gas Injection NIMROD 4-stage MGI shutdown NIMROD predictions concerning the role of the n=1 mode have been tested experimentally Pre-TQ Early TQ Late TQ CQ Ne MGI at t=0 NIMROD finds asymmetric impurity spreading for off-midplane injection MHD None m/n >1 m=1/n=1 Particle Transport Ne plume expansion || to B Radial mixing Heat Transport NIMROD multi-valve MGI simulations reveal implications of both effects for optimum valve positioning Slow  conduction Fast || Br conduction V·T convection

Contours/isosurface of ionized Ne density Injected Ne plume spreads along B-field in one direction toroidally  toward HFS poloidally Contours/isosurface of ionized Ne density MGI15U 2.25 ms MGI135L 0.25 ms MGI135L MGI15U MGI15U

Contours/isosurface of ionized Ne density Below midplane jet spreads in the opposite toroidal direction, also toward HFS Contours/isosurface of ionized Ne density MGI135L MGI15U 2.25 ms MGI15U 0.25 ms MGI135L MGI135L

PART I. Key 3D Physics of Massive Gas Injection NIMROD 4-stage MGI shutdown NIMROD predictions concerning the role of the n=1 mode have been tested experimentally Pre-TQ Early TQ Late TQ CQ Ne MGI at t=0 NIMROD finds asymmetric impurity spreading for off-midplane injection MHD None m/n >1 m=1/n=1 Particle Transport Ne plume expansion || to B Radial mixing Heat Transport NIMROD multi-valve MGI simulations reveal implications of both effects for optimum valve positioning Slow  conduction Fast || Br conduction V·T convection

Ionized Ne density contours/isosurface NIMROD: Ip direction affects direction of impurity spreading MGI15U NORMAL HELICITY MGI135L Ionized Ne density contours/isosurface MGI15U REVERSED HELICITY MGI135L

Radiated power and n=1 amplitude Relative spacing of gas valves affects interaction with 1/1 mode 135º 15º MGI15U Temperature contours MGI35L Radiated power and n=1 amplitude Time (ms)

Radiated power and n=1 amplitude MGI15U and MGI135L will tend to drive the same 1/1 mode phase 135º 15º MGI15U Temperature contours Gas jets are separated by 120º poloidally and toroidally MGI35L Radiated power and n=1 amplitude Time (ms)

Radiated power and n=1 amplitude Simulation with both gas jets drives same mode phase as single jet 135º 15º Normal Helicity MGI15U Temperature contours MGI35L Radiated power and n=1 amplitude Time (ms)

Radiated power and n=1 amplitude Heat flux due to 1/1 convection is simultaneously away from both jets 135º 15º MGI15U 1/1 convection also mixes impurities inward radially at both locations Temperature contours MGI35L Radiated power and n=1 amplitude Time (ms)

Radiated power and n=1 amplitude In reversed helicity, spacing of two jets no longer coheres with 1/1 symmetry 135º 15º MGI15U Reversed Helicity Temperature contours MGI35L Radiated power and n=1 amplitude Time (ms)

Radiated power and n=1 amplitude Interaction of 1/1 mode with each of the two impurity plumes is very different 135º 15º MGI15U No coherent 1/1 mode can interact with both jets in the same way Temperature contours MGI35L Radiated power and n=1 amplitude Time (ms)

PART II. NIMROD asymmetry predictions and comparison with DIII-D measurements  DIII-D has two fast radiated power measurements Prad210  Both jets are closer to Prad90 MGI15U Diagnostic locations MGI135L Radiated Energy Prad90 TPF = Max(Wrad)/Mean(Wrad) Clearly, asymmetry calculated from 2 measurement locations is an approximation… Toroidal angle

All cases in normal helicity NIMROD predicts improved symmetry when both DIII-D jets are used Pre-TQ TQ BOTH BOTH ONLY MGI135L ONLY MGI135L ONLY MGI15U ONLY MGI15U All cases in normal helicity

All cases in normal helicity NIMROD predicts improved symmetry when both DIII-D jets are used Pre-TQ TQ BOTH BOTH ONLY MGI135L ONLY MGI135L ONLY MGI15U ONLY MGI15U All cases in normal helicity

DIII-D finds little or no variation in the asymmetry for one vs two gas jets DIII-D measured asymmetry Pre-TQ Radiated energy asymmetry TQ CQ Asymmetry calculated from 90 and 210 degree detectors ONLY MGI15U ONLY MGI135L BOTH tMGI135L – t MGI15U (ms)

NIMROD synthetic asymmetry diagnostic largely reproduces missing trend in DIII-D data NIMROD 2-point “TPF” DIII-D measured asymmetry Pre-TQ Radiated energy asymmetry Comparison of asymmetry using only information from 90 and 210 degrees TQ CQ ONLY MGI15U ONLY MGI135L BOTH tMGI135L – t MGI15U (ms)

NIMROD “synthetic 2-point TPF” NIMROD: 2-point “TPF” does not capture real trend in TPF NIMROD real TPF Pre-TQ TQ ONLY MGI15U BOTH BOTH ONLY MGI135L ONLY MGI135L ONLY MGI15U NIMROD “synthetic 2-point TPF”

Reversed Helicity Case NIMROD: reversing helicity increases TQ TPF with 2 jets Pre-TQ ONLY MGI15U TQ BOTH BOTH ONLY MGI135L ONLY MGI135L ONLY MGI15U Reversed Helicity Case

Part III. ITER simulations use three upper ports allocated for TQ mitigation part of DMS Valve Normalized Ne injection rate Fraction of plenum injected Total particle injection rate vs. time based on FLUENT calculations  Assumes 1 m delivery tube: unrealistically short!

3-valves and 1-valve have same TPF, different TQ durations Slight decrease in TPF during pre-TQ with 3 valves Virtually no change in TPF during TQ Single valve has higher maximum Prad Three valve has longer TQ duration TPF Number of valves Time (ms)

NIMROD modeling provides new physics insights into MGI with single or multiple gas valves NIMROD predicts that DIII-D 2-valve configuration reduces TPF, but increased diagnostic resolution is needed to capture trend, validate model On ITER, 3 upper valve configuration is not found to reduce TPF compared to single upper valve during TQ  Single jet TPF during the thermal quench is not very severe in DIII-D or ITER

NIMROD modeling provides new physics insights into MGI with single or multiple gas valves NIMROD predicts that DIII-D 2-valve configuration reduces TPF, but increased diagnostic resolution is needed to capture trend, validate model On ITER, 3 upper valve configuration is not found to reduce TPF compared to single upper valve during TQ  Single jet TPF during the thermal quench is not very severe in DIII-D or ITER THANK YOU!

# of valves  MHD Mode #  TQ duration? 1 valve  n=1 dominant 3 valves n=3 dominant <B/B> - - Prad (a.u.) <B/B> - - Prad (a.u.) n=1 n=3 n=3 n=1