1 Max-Planck-Institut für Plasmaphysik 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila ELM resolved measurements of W sputtering MPI für Plasmaphysik.

Slides:



Advertisements
Similar presentations
Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.
Advertisements

Progress with PWI activities at UKAEA Fusion GF Counsell, A Kirk, E Delchambre, S Lisgo, M Forrest, M Price, J Dowling, F Lott, B Dudson, A Foster,
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation Interaction of nitrogen plasmas with tungsten Klaus Schmid, A. Manhard, Ch. Linsmeier, A. Wiltner,
K. Krieger, SEWG Meeting on Material Migration and ITER Material Mix, JET, Max-Planck-Institut für Plasmaphysik Carbon local transport and redeposition.
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SEWG meeting on mixed materials Parameter studies for the Be-W interaction Klaus Schmid.
Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.
ITPA Avilla January 2008 © Matej Mayer Surface modifications and blistering of tungsten exposed in ASDEX Upgrade M. Mayer, M. Balden, S. Lindig, J. Roth,
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
ASIPP HT-7 belt limiter Houyang Guo, Sizhen Zhu and Jiangang Li Investigation of EAST Divertor Asymmetry in Plasma Detachment & Target Power Loading Using.
ASIPP Characteristics of edge localized modes in the superconducting tokamak EAST M. Jiang Institute of Plasma Physics Chinese Academy of Sciences The.
Institute of Interfacial Process Engineering and Plasma Technology Gas-puff imaging of blob filaments at ASDEX Upgrade TTF Workshop.
Spectroscopy of hydrocarbon in low temperature plasmas : Results from JT-60U T. Nakano J apan A tomic E nergy A gency, Ibaraki, Japan. 6-9/11/2006 ITPA.
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.
1 ITPA - DSOL - TorontoS. Brezinsek TEC Hydrocarbon spectroscopy on EU tokamaks S. Brezinsek on behalf of the EU task force for Plasma-Wall Interaction.
George Sips ITPA, active control, 14 July Real-time Control ( and development of control systems ) at ASDEX Upgrade George Sips Max-Planck-Institut.
Toroidally resolved measurements of ELMs in RMP and non-RMP H-mode discharges on DIII-D M.W. Jakubowski 1, T.E. Evans 3, C.J. Lasnier 4, O. Schmitz 2,
A. Kirk, 20th IAEA Fusion Energy Conference, Vilamoura, Portugal, 2004 The structure of ELMS and the distribution of transient power loads in MAST Presented.
IAEA - FEC2004 // Vilamoura // // EX/4-5 // A. Staebler – 1 – A. Staebler, A.C.C Sips, M. Brambilla, R. Bilato, R. Dux, O. Gruber, J. Hobirk,
Physics of fusion power
Progress on Determining Heat Loads on Divertors and First Walls T.K. Mau UC-San Diego ARIES Pathways Project Meeting December 12-13, 2007 Atlanta, Georgia.
Physics of fusion power Lecture 8 : The tokamak continued.
European Joint PhD Programme, Lisboa, Diagnostics of Fusion Plasmas Spectroscopy Ralph Dux.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
H. D. Pacher 1, A. S. Kukushkin 2, G. W. Pacher 3, V. Kotov 4, G. Janeschitz 5, D. Reiter 4, D. Coster 6 1 INRS-EMT, Varennes, Canada; 2 ITER Organization,
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
10th ITPA meeting on SOL & divertor physics, Avila, Spain, Jan 7-10, 2008 Arne Kallenbach 1/15 Prediction of wall fluxes and implications for ITER limiters.
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.
Divertor/SOL contribution IEA/ITPA meeting Naka Nov. 23, 2003 Status and proposals of IEA-LT/ITPA collaboration Multi-machine Experiments Presented by.
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.
1 Modeling of EAST Divertor S. Zhu Institute of Plasma Physics, Chinese Academy of Sciences.
K. Sugiyama, 9th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials, Salamanca, June 2-3, Max-Planck-Institut für Plasmaphysik.
On the use of LIBS to determine the fractional abundances of carbon ions in the laser plasma plume M. Naiim Habib 1, Y. Marandet 2, L. Mercadier 3, Ph.
R. P. Doerner, 2 nd PMIF Meeting, Juelich, Sept , 2011 Plasma interactions with Be surfaces R. P. Doerner, D. Nishijima, T. Schwarz-Selinger and.
V. A. Soukhanovskii 1 Acknowledgement s: R. Maingi 2, D. A. Gates 3, J. Menard 3, R. Raman 4, R. E. Bell 3, C. E. Bush 2, R. Kaita 3, H. W. Kugel 3, B.
TEC Trilateral Euregio Cluster 1 S. Brezinsek Spectroscopic determination of carbon erosion yields and the composition of chemically eroded molecular carbon.
TIME-RESOLVED OPTICAL SPECTROSCOPY OF HIGH-TEMPERATURE PLASMAS M.J. Sadowski  , K. Malinowski , E. Skladnik-Sadowska , M. Scholtz , A. Tsarenko ¤
第16回 若手科学者によるプラズマ研究会 JAEA
Introduction to Plasma- Surface Interactions Lecture 3 Atomic and Molecular Processes.
ITPA - Meeting, Toronto; Session 3 - High Z studies 3 - High-Z studies (Chair - A. Herrmann) 16:25 (0:10) A. Herrmann - Introduction 16:35.
1 of 22A.V.Chankin & D.P.Coster, 18 th PSI Conference, Toledo, Spain, 29 May 2008 Comparison of 2D Models for the Plasma Edge with Experimental Measurements.
Physics of fusion power Lecture 9 : The tokamak continued.
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,
EAST Data processing of divertor probes on EAST Jun Wang, Jiafeng Chang, Guosheng Xu, Wei Zhang, Tingfeng Ming, Siye Ding Institute of Plasma Physics,
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
PSI 2008 Toledo May 2008 © Matej Mayer Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade M. Mayer a, V. Rohde.
Edge-SOL Plasma Transport Simulation for the KSTAR
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,
Gas inlet position References Experiment 1) W sputtering experiment Aim: study of W erosion for different plasma conditions by aim of spectroscopy reference.
ASIPP HT-7 The effect of alleviating the heat load of the first wall by impurity injection The effect of alleviating the heat load of the first wall by.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
ITPA May 2007 © Matej Mayer Carbon Erosion and Transport in ASDEX Upgrade M. Mayer 1, V. Rohde 1, J.L. Chen 1, X. Gong 1, J. Likonen 3, S. Lindig 1, G.
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
ELM propagation in Low- and High-field-side SOLs on JT-60U Nobuyuki Asakura 1) N.Ohno 2), H.Kawashima 1), H.Miyoshi 3), G.Matsunaga 1), N.Oyama 1), S.Takamura.
1 EAST Recent Progress on Long Pulse Divertor Operation in EAST H.Y. Guo, J. Li, G.-N. Luo Z.W. Wu, X. Gao, S. Zhu and the EAST Team 19 th PSI Conference.
ERO code development A. Kirschner M. Airila, D. Borodin, S. Droste, C. Niehoff  The ERO code  ERO code management  Modelling of CH 4 puffing in ASDEX.
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.
1 Max-Planck-Institut für Plasmaphysik 9th ITPA Meeting on Divertor and SOL Physics, 10/5/07 Initial operation of ASDEX Upgrade with 100 % tungsten PFCs.
1 SIMULATION OF ANOMALOUS PINCH EFFECT ON IMPURITY ACCUMULATION IN ITER.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION FDF: PWI issues and research opportunities Peter Stangeby University of Toronto.
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.
ELM propagation and fluctuations characteristics in H- and L-mode SOL plasmas on JT-60U Nobuyuki Asakura 1) N.Ohno 2), H.Kawashima 1), H.Miyoshi 3), G.Matsunaga.
Fast response of the divertor plasma and PWI at ELMs in JT-60U 1. Temporal evolutions of electron temperature, density and carbon flux at ELMs (outer divertor)
Scaling experiments of perturbative impurity transport in NSTX D. Stutman, M. Finkenthal Johns Hopkins University J. Menard, E. Synakowski, B. Leblanc,R.
J. Roth: ITPA SOL/DIV, Avila, Jan Prediction of ITER T retention levels with W PFCs J. Roth, and the SEWG Fuel retention of the EU Task Force on.
1 Estimating the upper wall loading in ITER Peter Stangeby with help from J Boedo 1, D Rudikov 1, A Leonard 1 and W Fundamenski 2 DIII-D 1 JET 2 10 th.
1 ITC-22, November 2012, Toki, Japan 1 Modelling of impurity transport, erosion and redeposition in fusion devices: applications of the ERO code A. Kirschner.
Member of the Helmholtz Association Meike Clever | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ Graduiertenkolleg 1203 Dynamics.
Temperature Measurements of Limiter Surfaces at High Heat Flux in the HT-7 Tokamak H. Lin, X.Z. Gong, J. Huang, J.Liu, B. Shi, X.D. Zhang, B.N. Wan,
Features of Divertor Plasmas in W7-AS
Presentation transcript:

1 Max-Planck-Institut für Plasmaphysik 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila ELM resolved measurements of W sputtering MPI für Plasmaphysik EURATOM Association, Garching, Germany R. Dux, R. Neu, R. Pugno, T.Pütterich, ASDEX Upgrade Team

2 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Temperature/Energy Dependence of W Sputter Yield

3 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Erosion Yield per Deposited Energy (steady state) Value represents number of eroded W particles per deposited energy scan over T i and T e keeping a fixed ratio for a typical impurity mix a first plateau (~ 3e19 particles/MJ) is eV  at this (high divertor) temperatures erosion flux mainly given by deposited power (weakly depended on detailed plasma parameters)

4 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Erosion Yield per Deposited Energy (ELMs) high temperature ions reach targets only after re-adjusted T e T e fixed T i scan for a typical impurity mix ‘plateau’ extended up to T i ~ 1 keV  erosion flux mainly given by deposited power (weakly depended on detailed plasma parameters) dashed lines: sputtering by D/T only

5 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Influx Measurements in the Full W ASDEX Upgrade Quantify W-influx from various PFCs: visible spectroscopy influx density is a local quantity (often toroidal symmetry) many lines-of-sight needed to have full account of the total influx Caveat: measurements of W 0 * (W I) do not account for prompt redeposition

6 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Set-up for Spectroscopic Influx Measurements

7 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Example of Spectra Evolution Spectrometer for fast measurements in divertor (1 line-of-sight): wide entrance slit (200  m) standard repetition/exposure time =0.2ms (continuous) Balmer-  surrounded by OII multiplet WI line well isolated

8 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu W-Influx Profile at Outer SP (temporally averaged) Map flux densities to outer mid-plane Profile can be described with an exponential decay into the far SOL Interpolation and integration yields total source New in 2008

9 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Highest W Erosion Rates for Hot Divertor Conditions TeTe 19eV 12eV 8eV W-erosion decreases with increasing level of gas puff (recycling) leading to lower temperatures in divertor

10 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Effective Erosion Yield of Tungsten erosion yields can only be explained by sputtering by impurities data from: - H-mode (only between ELMs) - H-L threshold calculations (solid lines)

11 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu ELM Cycle at Low Divertor Density divertor temperature between ELMs: ≈ 20eV Considerable influx also inbetween ELMS ELMs contribute  50% to the W-influx

12 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu ELM Cycle at Higher Divertor Density divertor temperature is low after the ELM (detachment, phase with high recycling) and eventually recovers during the ELM cycle depending on - the distance to the strike point, - the ELM frequency - … Erosion yield is lower inbetween ELMs ELMs contribute > 50% to W-influx

13 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Effect of Ar puff on W erosion in divertor Ar puff at 2.5s During ELMs: power flux density decreases tungsten influx increases

14 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Effect of Ar puff on W erosion in divertor Ar puff at 2.5s Between ELMs: power flux density decreases temperature decreases tungsten influx decreases

15 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu W Influx During ELMs W-influx measurements with time resolution down to 40  s show sub-structure of ELMs (local / temporal?) Langmuir probe data can not be used during ELMs

16 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Erosion by ELMs at different outboard PFCs Fraction of erosion during ELMs increases with distance to the separatrix: higher fractions are observed at outboard limiters/horizontal plate lower fractions at strike point module close to separatrix Note: total erosion flux decreases  R!

17 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Summary largest W erosion flux usually at the divertor SP region dominated by impurity sputtering with strong ELM modulation relative contribution of ELMs to erosion -increases with distance to separatrix to values around 70 % -increases with decreasing divertor temperature (but total erosion decreases strongly in both cases) Ar puffing increases W erosion during ELMs; between ELMs the cooling leads to lower erosion (further investigations envisaged) Note: influence of transport on W content much larger than source rate!  ELM transport important to keep W concentration low

18 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Tools for operation with high-Z: Reduction of W content by increasing ELM frequency ELM frequency depends strongly on gas puffing, distance to H/L threshold and machine conditions  larger heating power or ELM pacemaking keep impurity content low Frequent ELMs necessary to clamp impurity content A. Kallenbach, PPCF 2005

19 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu S/XB for W I (400.9nm) Calculations of S/XB for W I (400.9 nm) I Beigman et al. PPCF 2007 ionisation rate ATOM code calculations (lowest configurations) excitation rate: - semi-empirical v. Regemorter formula (complicated coupling scheme + configuration mixing) - corona approximation: only excitation from ‘ground’ state TEC

20 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Erosion in the Outer Divertor Strongest W erosion found in the outboard divertor: determination of the total W source (temporally averaged - integrating over ELMs) Effect of ELMs Effective Erosion Yield Sputtering by Argon

21 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Sputter-flux / power load strong decrease with higher particle energies at similar power loads high-Z best for D-energies < 300 eV low-Z better at high D-energies Be W C Y C =1% Y C =5%  1nm s -1 / MW m -2

22 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila R.Neu Erosion Yield per Deposited Energy (ICRH) Fixed T e and T i Scan sheath voltage