L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European.

Slides:



Advertisements
Similar presentations
TEC Trilateral Euregio Cluster Institut für PlasmaphysikAssoziation EURATOM-Forschungszentrum Jülich IEA Large Tokamak IA Workshop on Edge Transport in.
Advertisements

ASSOCIATION EURATOM HELLENIC REPUBLIC (and CYPRUS) (HELLAS) FOUNDATION FOR RESEARCH AND TECHNOLOGY-HELLAS NATIONAL CENTRE FOR SCIENTIFIC RESEARCH “DEMOKRITOS”
Chalkidikhi Summer School Plasma turbulence in tokamaks: some basic facts… W.Fundamenski UKAEA/JET.
Institute of Interfacial Process Engineering and Plasma Technology Gas-puff imaging of blob filaments at ASDEX Upgrade TTF Workshop.
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
Jul LRB L.R. Baylor, T.C. Jernigan, N. Commaux, P.Parks, M. Fenstermacher, T. Osborne, S. K. Combs, C. R. Foust, M. Hansink, B. Williams 14 th ITPA.
A. Kirk, 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, 2004 The structure of ELMS and the distribution of transient power loads in MAST Presented.
1 st ITPA T&C Meeting, Milan, October WAHPage 1 ITER R&D Needs for Transport & Confinement W.A. Houlberg ITER Organization 1st ITPA Transport.
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.
Physics of fusion power
Energy loss for grassy ELMs and effects of plasma rotation on the ELM characteristics in JT-60U N. Oyama 1), Y. Sakamoto 1), M. Takechi 1), A. Isayama.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
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.
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.
H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team Japan Atomic Energy Agency JT-60U Tokamak: p.
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
RFX Programme Meeting Feb-2010 Influences of main gas choice on RFP plasmas RFX-mod Programme Planning Workshop, 9 Feb 2011 M Valisa with contributions.
ELM Control Using External Perturbation Fields on JET Y Liang, JET-EFDA contributors Joint Pedestal/SOL ITPA Meeting Garching (7-10 May), Germany.
H-mode characteristics close to L-H threshold power ITPA T&C and Pedestal meeting, October 09, Princeton Yves Martin 1, M.Greenwald, A.Hubbard, J.Hughes,
Edge Localized Modes propagation and fluctuations in the JET SOL region presented by Bruno Gonçalves EURATOM/IST, Portugal.
Excitation of ion temperature gradient and trapped electron modes in HL-2A tokamak The 3 th Annual Workshop on Fusion Simulation and Theory, Hefei, March.
M.E. Fenstermacher - Status of Progress on Work Plan in PEP ITPA WG on RMP ELM Control 12/5/07 11:15 PM 1 PEP ITPA Working Group on RMP ELM Control: 1.
High  p experiments in JET and access to Type II/grassy ELMs G Saibene and JET TF S1 and TF S2 contributors Special thanks to to Drs Y Kamada and N Oyama.
ITPA DSOL meeting, Toronto W. Fundamenski9/11/2006 TF-E Introduction to ELM power exhaust: Overview of experimental observations W.Fundamenski Euratom/UKAEA.
M.E. Fenstermacher - 2nd Inter-Mtg Conf Call, PEP ITPA WG on RMP ELM Control 8/31/09 18:05 1 PEP ITPA Working Group on RMP ELM Control: 2 nd Inter-Meeting.
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.
Recent Results of KSTAR
1 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu
FOM - Institute for Plasma Physics Rijnhuizen Association Euratom-FOM Diagnostics and Control for Burning Plasmas Discussion All of you.
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
Hysteresis in the L-H-L transition, D C McDonald, ITPA, Princeton 20091/22 Hysterics in the L-H transition D C McDonald.
Measurements of plasma turbulence by laser scattering in the Wendelstein 7-AS stellarator Nils P. Basse 1,2, S. Zoletnik, M. Saffman, P. K. Michelsen and.
R. Wenninger 1 (35) Sat. Workshop to EPS on Fuelling 16 th June 2008 Status of ELM trigger investigations on JET and AUG R. Wenninger IPP Garching, EFDA.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION International Plan for ELM Control Studies Presented by M.R. Wade (for A. Leonard)
L. Zanotto – 10 February 2011 – RFX-mod programme workshop TF2: Active control of RFP and tokamak plasmas Report on experimental proposals L. Zanotto,
MCZ Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2,
Confinement & Transport Plan Classical theory of confinement and transport. o Diffusion equation Particle diffusion in a magnetic field.
Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama JAEA Naka TH/4-2.
Role of thermal instabilities and anomalous transport in the density limit M.Z.Tokar, F.A.Kelly, Y.Liang, X.Loozen Institut für Plasmaphysik, Forschungszentrum.
18th International Spherical Torus Workshop, Princeton, November 2015 Magnetic Configurations  Three comparative configurations:  Standard Divertor (+QF)
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
Member of the Helmholtz Association Meike Clever | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ Graduiertenkolleg 1203 Dynamics.
Mechanisms for losses during Edge Localised modes (ELMs)
Carlos Hidalgo Laboratorio Nacional de Fusión CIEMAT Madrid, Spain
Non-linear MHD simulations for ITER
T. Markovič1,2, P. Cahyna1, R. Panek1, M. Peterka1,2, P. C
Magnetic Ripple as a Tool for ELMs Mitigation
ELM Control in Application of Non-Axisymmetric Magnetic Perturbations
J. Menard for the MHD Science Focus Group Tuesday, November 22, 2005
Andrew Kirk on behalf of
Pellet injection in ITER Model description Model validation
First Experiments Testing the Working Hypothesis in HSX:
Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation Alberto Loarte G. Huijsmans, S. Futatani,
TC-2 – Power ratio April 2011, San Diego
ITER consequences of JET 13C migration experiments Jim Strachan, PPPL Jan. 7, 2008 Modeled JET 13C migration for last 2 years- EPS 07 and NF paper in prep.
Methane Screening on C-MOD EDA ELM-mitigated Plasmas Jim Strachan, PPPL Nov. 30, 2004 Goal: compare impurity behavior in ELM mitigated plasmas – ergodic.
49th Annual Meeting of APS - DPP Orlando, 11/14/2007
The effect of ELM pacing by vertical kicks on the access to stationary H-mode with H98~1 on JET E. de la Luna 24th.
IOS-6.3: Control of experimentally simulated burning state
[EX / P7-8] 27th IAEA Fusion Energy Conference – J. Jang, et. al
Max-Planck Institut für Plasmaphysik Garching
Ioffe Institute, St. Petersburg, Russian Federation
Continued exploration of pedestal structure and edge relaxation mechanisms at lower edge collisionality  J.W. Hughes, A. Hubbard, B. LaBombard, J. Terry,
EX/P3-47: Influence of magnetic perturbations on particle transport in magnetic fusion devices (ITPA T&C 24) L-mode H-mode The particle transport increase.
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

L-H power threshold and ELM control techniques: experiments on MAST and JET Carlos Hidalgo EURATOM-CIEMAT Acknowledgments to: A. Kirk (MAST) European Fusion Physics Workshop (December 2008): Y. Andrew, L. Horton, E. Nardon, W. Suttrop ITPA meeting, April (2009)

L-H power threshold physics and ITER plasma scenarios Large uncertainties are still present in the empirical description of the L-H power transition with impact in the overall research programme of next step magnetic confinement devices (e.g. ITER). This fact is reflecting the lack of basic understanding of the physics of sheared flows and edge transport barriers. ITPA meeting, April (2009)

Pin > 1.5Pth for H98 = 1.0, Type-I ELMS Pin = Pth is insufficient for H98 = 1 access R Sartori et al., PPCF 46 (2004) 723 – 750. Values of total Pin for Type-III and Type-I ELMy phases are plotted along with measured Pth for L-H transition Pin > 1.5Pth for H98 = 1.0, Type-I ELMS In JET Type-III ELMy H-modes H98 is lower than for Type-I ELMy H-modes over the entire density range. Y. Andrew et al., EFPW, December 2008. Pin>1.5Pth is required for H-mode plasma H98=1 access on JET ITPA meeting, April (2009)

Type I ELMs must be drastically reduced in ITER A. Loarte et al., Type-I ELMs are a factor in the order of 10 too large in ITER baseline scenario Development of mechanisms allowing controlling ELM size is a prime target for ITER: Vertical kicks Pellet pace-making Resonant Magnetic Perturbations ITPA meeting, April (2009)

Alternatives to the Type-I ELMy H-mode? Many regimes observed in different machines Feasibility at ITER parameters and without loosing confinement? Alternatives to Type-I ELMy H-mode: No clear solution but some promising paths (e.g. QH) that need to be explored further E. Nardon, EFPW, December 2008 ITPA meeting, April (2009)

Interplay between L-H power threshold and ELMs control techniques: an open issue for ITER (Pin≈ 1.5 x Pth) ITPA meeting, April (2009)

ELM mitigation with magnetic perturbations Edge stochastic magnetic field edge pressure gradient kept below threshold Ex vessel coils (error field correction coils) in JET In-vessel coils in DIII-D and ITER Advantage: large toroidal mode number spectrum of the perturbation . Advantage: External Coils, more relevant for reactor application. Limitation: Internal coils, subject to neutron radiation => reactor relevance? Limitation: low toroidal mode number spectrum of the perturbation ITPA meeting, April (2009)

ELM supression in MAST MAST has new ELM control coils (in-vessel, n=3) Vacuum modelling predicts σChirikov larger than for DIII-D I-coils No ELM suppression so far but experiments are at the beginning. On MAST there is already observation of the delay of the L-H transition time if the n=1 coils are applied before the L-H transition. E. Nardon, European Fusion Physics Workshop, Cork, December 2008 ITPA meeting, April (2009)

n=1 experiments / MAST Pin ≈ 2.5 x Pth Increasing error field B L-H transition effected by size of Error field –need to ramp field only after the transition A.Kirk et al., (MAST) ITPA meeting, April (2009)

n=3 experiments / MAST L-H transition not effected by size of Elm coil –natural jitter in start of L-H makes conclusions difficult A.Kirk et al., (MAST) ITPA meeting, April (2009)

ELM mitigation with external magnetic perturbation field #69564 Ip = 1.5 MA; Bt = 1.78 T; q95 ~ 4.0; dU ~ 0.45 Coil current kAt Density Temperature keV Confinement normalised to H-mode scaling D emission ELM frequency increased form 30Hz to 120Hz and ELM energy loss reduced from 7% to below noise level (~2%). Reduction in ELM peak heat fluxes and carbon erosion Electron density decreases (pump out) Electron and ion temperatures increase (core and edge) Reduction in the thermal energy confinement but no change compared to H-mode scaling Wide range in q95 (4.8 – 3.0) with n = 1, 2 N up to ~2.9 (no locked mode excited by n=1 field) Low collisionality: n*e~ 0.09 Y. Liang PRL, 98, 265004 (2007) ITPA meeting, April (2009)

Conclusions and actions On MAST there is already observation of the delay of the L-H transition time if the n=1 coils are applied before the L-H transition (Pin = 2.5 x Pth) but not with n = 3.. Experiments are planned in JET (2009 experimental campaign). Actions: L-H power threshold with ergodic divertor / resonant magnetic perturbations (RMP) ( e.g. EU: JET / MAST / TEXTOR / AUG-2010,..): Influence of RMP (different n) on L-H power threshold (Pin ≈ 1.5 x Pth) Power minimum at a certain density and Bt dependence (role of RMP) L-H power threshold physics: Tokamak vs Stellarators e.g. Why is it so easy (in terms of heating power) to trigger the L-H transition in low shear / low q stellarators?; Role of magnetic shear / q ? Impact of q on zonal flows / GAMs? ITPA meeting, April (2009)