Model validation on EAST and DIII-D experiments highlight the roles of the Low-Z background impurities and the sheath potential in determining high-Z materials.

Slides:

Advertisements

Similar presentations

Report on SEWG mixed materials EU PWI TF meeting Madrid 2007 V. Philipps on behalf of SEWG members Mixed material formation is a among the critical ITER.

Advertisements

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.

PWI questions of ITER review working groups WG1 and WG8 : Materials Introduction EU PWI TF V. Philipps, EU PWI TF meeting, Oct 2007, Madrid V. Philipps,

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.

© Olga Ogorodnikova, 2008, Salamanka, Spain Current status of assessment of Tritium inventory in all-W device O.V. Ogorodnikova and E. d’Agata.

The Kavli FoundationThe National Science Foundation Guaranteed Unresolved Point Source Emission and the Gamma-ray Background Vasiliki Pavlidou University.

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.

1 ITPA - DSOL - TorontoS. Brezinsek TEC Hydrocarbon spectroscopy on EU tokamaks S. Brezinsek on behalf of the EU task force for Plasma-Wall Interaction.

1 EFFECTS OF CARBON REDEPOSITION ON TUNGSTEN UNDER HIGH-FLUX, LOW ENERGY Ar ION IRRADITAION AT ELEVATED TEMPERATURE Lithuanian Energy Institute, Lithuania.

Semiconductor pn junctions. semiconductor pn junction context Figure pn junction representations.

Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)

Plasma Dynamics Lab HIBP Abstract Measurements of the radial equilibrium potential profiles have been successfully obtained with a Heavy Ion Beam Probe.

Iain D. Boyd University of Michigan Modeling of Ion Sputtering and Product Transport.

THE WAFER- FOCUS RING GAP*

WAFER EDGE EFFECTS CONSIDERING ION INERTIA IN CAPACITIVELY COUPLED DISCHARGES* Natalia Yu. Babaeva and Mark J. Kushner Iowa State University Department.

EDGE EFFECTS IN REACTIVE ION ETCHING: THE WAFER- FOCUS RING GAP* Natalia Yu. Babaeva and Mark J. Kushner Iowa State University Department of Electrical.

INVESTIGATIONS OF MAGNETICALLY ENHANCED RIE REACTORS WITH ROTATING (NON-UNIFORM) MAGNETIC FIELDS Natalia Yu. Babaeva and Mark J. Kushner University of.

Erosion Characterization via Ion Power Deposition Measurements in a 6-kW Hall Thruster Rohit Shastry, Professor Alec D. Gallimore, and Dr. Richard R. Hofer.

Aspect Ratio Dependent Twisting and Mask Effects During Plasma Etching of SiO2 in Fluorocarbon Gas Mixture* Mingmei Wang1 and Mark J. Kushner2 1Iowa State.

Physics and Applications of Plasma-Based Ion Implantation Jason Olejarz May 4, 2009.

ITPA-9, Avila, Spain, Impact of ICRF on impurity production in TEXTOR Presented by Marek Rubel Alfvén Laboratory, Royal Institute of Technology,

Nam-Sik Yoon (Chungbuk National University of Korea) A Dust Charging Model under Tokamak Discharge Conditions 6 th Japan-Korea Workshop on Theory and Simulation.

ASIPP Development of a new liquid lithium limiter with a re-filling system in HT-7 G. Z. Zuo, J. S. Hu, Z.S, J. G. Li,HT-7 team July 19-20, 2011 Institute.

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.

R. P. Doerner, 2 nd PMIF Meeting, Juelich, Sept , 2011 Plasma interactions with Be surfaces R. P. Doerner, D. Nishijima, T. Schwarz-Selinger and.

VDU/LEI project in FUSION: background, goals, methods and expected results (PhD student Birutė Bobrovaitė, D r. Liudas Pranevičius)

Semion System Retarding Field Ion Energy Analyzer “

Introduction to Plasma- Surface Interactions Lecture 3 Atomic and Molecular Processes.

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.

2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.

Sulfate Ion Wet Deposition

Ammonium Ion Wet Deposition

Edge-SOL Plasma Transport Simulation for the KSTAR

R. Doerner, ITPA SOL/DIV meeting, Avila, Jan. 7-10, Be deposition on ITER first mirrors: layer morphology and influence on mirror reflectivity G.

HT-7 ASIPP The Influence of Neutral Particles on Edge Turbulence and Confinement in the HT-7 Tokamak Mei Song, B. N. Wan, G. S. Xu, B. L. Ling, C. F. Li.

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.

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor J.N. Brooks, J.P. Allain Purdue University PFC Meeting MIT,

CONTROL OF ELECTRON ENERGY DISTRIBUTIONS THROUGH INTERACTION OF ELECTRON BEAMS AND THE BULK IN CAPACITIVELY COUPLED PLASMAS* Sang-Heon Song a) and Mark.

10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.

Lab. Results. Differential Photoelectric Charging and Super-charging near the Lunar Terminator UV Radiation Differential photoelectric charging near the.

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.

PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION FDF: PWI issues and research opportunities Peter Stangeby University of Toronto.

PLASMA DIAGNOSTIC BY ELECTRIC PROBE NITIN MINOCHA M.Tech. N.S.T., Delhi University 1.

Study of the Plasma-Wall Interface – Measurement and Simulation of Sheath Potential Profiles Samuel J. Langendorf, Mitchell L.R. Walker High-Power Electric.

1Field-Aligned SOL Losses of HHFW Power and RF Rectification in the Divertor of NSTX, R. Perkins, 11/05/2015 R. J. Perkins 1, J. C. Hosea 1, M. A. Jaworski.

Electrolysis Splitting Materials via Energy. What is electrolysis? Process of forcing current through a cell to produce a chemical change Results in negative.

March 27, 2014 Notes: Real versus Nominal Interest Rates HW: Activity 4-9.

1 The IBEX-HI SensorVoyagers in the Heliosheath Conference, January 12, 2009 January 12, 2009 Voyagers in the Heliosheath Kauai, Hawaii. The IBEX Hi Sensor:

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.

Voltaic Cells Notes A.) Spontaneous reaction 1.) In Voltaic Cells (Batteries), when the circuit is closed (turned on) electrons will move from anode.

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,

Impurity Transport Research at the HSX Stellarator

DOE Plasma Science Center Control of Plasma Kinetics

Characteristics of Edge Turbulence in HSX

Pellet injection in ITER Model description Model validation

2012 סיכום מפגש 2 שלב המשכי תהליך חזוני-אסטרטגי של המועצה העליונה של הפיזיותרפיה בישראל.

An Overview of Erosion-Deposition Pattern in JET with ITER-Like Wall

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

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.

Studies of impurity migration in TEXTOR by local tracer injection

Divertor & SOL Characterisation with Visible Imaging

Lunar dust transport investigation in laboratory plasmas

I-mode regime has many attractive features for fusion:

Electrical Energy & Capacitance Pgs

[EX / P7-8] 27th IAEA Fusion Energy Conference – J. Jang, et. al

Quasi-steady-state conditions in JET-ILW:

Deuterium retention for sample temperature of 500 K

Benchmarking of chemical mechanisms

Presentation transcript:

Model validation on EAST and DIII-D experiments highlight the roles of the Low-Z background impurities and the sheath potential in determining high-Z materials erosion WI emission for W divertor in EAST W ersoion rate for metal ring in DIII-D High-Z material erosion and migration strongly depends on the transport and deposition of low-Z impurities Good agreement between measured W gross erosion rate and the ERO modeling taking into account re- erosion processes Local sheath potential perturbation leads to more than an order of magnitude reduction of erosion rate due to lower ion incident energy and flux ( cm-2s-1sr-1) (1015 cm-2s-1) WI ERO Ion streamlines and the potential distribution Floating Biased