Modelling of prompt deposition of tungsten under fusion relevant conditions

Similar documents
Modelling of Carbon Erosion and Deposition in the Divertor of JET

Temporal Evolution of Temperature and Argon Impurity Density Profiles Observed by X-ray Imaging Spectrometer Measurements at Wendelstein 7-X

Multiscale modelling of sheath physics in edge transport codes

Magnetic Flux Surface Measurements at Wendelstein 7-X

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

Electron energy distribution function in the divertor region of the COMPASS tokamak during neutral beam injection heating

EUROFUSION WPJET1-PR(16) CG Albert et al.

The emissivity of W coatings deposited on carbon materials for fusion applications

Modelling and Analysis of the JET EP2 Neutral Beam Full Energy Ion Dump Curved End Plate

Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics

In situ wavelength calibration of the edge CXS spectrometers on JET

Evidence for enhanced main chamber wall plasma loads in JET ITER-like Wall at high radiated fraction

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

Turbulent Transport Analysis of JET H-mode and Hybrid Plasmas using QuaLiKiz, TGLF and GLF23

Central Solenoid Winding Pack Design

Hydrocarbon transport in the MkIIa divertor of JET

Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Deposition and re-erosion studies by means of local impurity injection in TEXTOR

Divertor configuration with two nearby poloidal field nulls: modelling and experiments for EAST and JET tokamaks

1 EX/3-5. Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign

Power loads to misaligned edges in COMPASS

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography

3D analysis of impurity transport and radiation for ITER limiter start-up configurations

Evaluation of First Wall Heat Fluxes Due to Magnetic Perturbations for a Range of ITER Scenarios

Development of miniaturized, spectroscopically assisted Penning gauges for fractional helium and hydrogen neutral pressure measurements

ERO modelling of local deposition of injected 13 C tracer at the outer divertor of JET

Deuterium Balmer/Stark spectroscopy and impurity profiles: first results from mirror-link divertor spectroscopy system on the JET ITER-like wall

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Comparative Transport Analysis of JET and JT-60U Discharges

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

Multi-Machine Experiments to Study the Parametric Dependences of Momentum Transport

The role of statistical noise in edge plasma transport codes based on kinetic Monte Carlo solvers for neutrals: an analogy with turbulent fluctuations

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade

Improved EDGE2D-EIRENE Simulations of JET ITER-like Wall L-mode Discharges Utilising Poloidal VUV/visible Spectral Emission Profiles

On Benchmarking of Particle Transport Simulations in ITER

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges

Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of. ASDEX Upgrade

Mitigation of ELMs and Disruptions by Pellet Injection

The physics of the heat flux narrow decay length in the TCV scrape-off layer: experiments and simulations

Recent progress towards a functional model for filamentary SOL transport

Integrated Core-SOL-Divertor Modelling for ITER Including Impurity: Effect of Tungsten on Fusion Performance in H-mode and Hybrid Scenario

Preliminary system modeling for the EUROfusion Water Cooled Lithium Lead blanket

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

Flux-driven multi-channel simulations with the quasilinear gyrokinetic tokamak transport model QuaLiKiz

Application of the ECRH radiation for plasma diagnostics in Wendelstein 7-X

Isotope Exchange in High Heat-flux Components of the JET Tritium Neutral Beam Injector

Erosion and Confinement of Tungsten in ASDEX Upgrade

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

Divertor Power Handling Assessment for Baseline Scenario Operation in JET in Preparation for the ILW

Power Exhaust on JET: An Overview of Dedicated Experiments

Tailoring the charged particle fluxes across the target surface of Magnum-PSI

Divertor Heat Load in ITER-Like Advanced Tokamak Scenarios on JET

Neutron Emission Spectroscopy Measurements with a Single Crystal Diamond Detector at JET

Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices

Modelling of the ICRF induced ExB convection in the scrape off layer of ASDEX Upgrade

II: The role of hydrogen chemistry in present experiments and in ITER edge plasmas. D. Reiter

On the locality of parallel transport of heat carrying electrons in the SOL

EX/4-2: Active Control of Type-I Edge Localized Modes with n = 1 and n = 2 fields on JET

Recent results on high-triangularity H-mode studies in JET-ILW

EROSION AND DEPOSITION MECHANISMS IN FUSION PLASMAS. A. Kirschner

Characterization of Tungsten Sputtering in the JET divertor

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor

Assessment of Erosion, deposition and fuel retention in the JET-ILW divertor from Ion Beam Analysis data

Microanalysis of deposited layers in the divertor of JET with ITER-like wall

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Tokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011

Comparison of plasma breakdown with a carbon and ITER-like wall

Measurements of Deuterium Retention and Surface Elemental Composition with Double Pulse Laser Induced Breakdown Spectroscopy

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Chemical Sputtering of Carbon Materials due to Combined Bombardment by Ions and Atomic Hydrogen

Report A+M/PSI Data Centre NRC Kurchatov Institute

Erosion and Confinement of Tungsten in ASDEX Upgrade

On the Design Aspects Affecting Performance of GEM based Detector Development for Plasma Diagnostics

Progress in Turbulence Modeling JET SOL and edge phenomena

Full Wave Propagation Modelling in View to Integrated ICRH Wave Coupling/RF Sheaths Modelling

Neutral beam plasma heating

Scaling of divertor heat flux profile widths in DIII-D

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET

Introduction to Fusion Physics

Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor

L-mode filament characteristics on MAST as a function of plasma current measured using visible imaging

Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads

DT Fusion Power Production in ELM-free H-modes in JET

Towards powerful negative ion beams at the test facility ELISE for the ITER and DEMO NBI systems

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Benchmarking Tokamak Edge Modelling Codes

Global migration of impurities in tokamaks: what have we learnt?

ITER A/M/PMI Data Requirements and Management Strategy

Simulation of PHA Soft X-Ray Spectra Expected from W7-X

Implications of JET-ILW L-H Transition Studies for ITER

Modeling and analysis of surface roughness effects on sputtering, reflection and sputtered particle transport *

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK

Ion Cyclotron Resonance Heating for tungsten control in various JET H-mode scenarios

Molecular Dynamics Study of Plasma Surface Interactions for Mixed Materials

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Transcription:

EUROFUSION WPPFC-CP(16) 1532 A Kirschner et al. Modelling of prompt deposition of tungsten under fusion relevant conditions Preprint of Paper to be submitted for publication in Proceedings of 26th IAEA Fusion Energy Conference This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 214-218 under grant agreement No 63353. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

This document is intended for publication in the open literature. It is made available on the clear understanding that it may not be further circulated and extracts or references may not be published prior to publication of the original when applicable, or without the consent of the Publications Officer, EUROfusion Programme Management Unit, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK or e-mail Publications.Officer@euro-fusion.org Enquiries about Copyright and reproduction should be addressed to the Publications Officer, EUROfusion Programme Management Unit, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK or e-mail Publications.Officer@euro-fusion.org The contents of this preprint and all other EUROfusion Preprints, Reports and Conference Papers are available to view online free at http://www.euro-fusionscipub.org. This site has full search facilities and e-mail alert options. In the JET specific papers the diagrams contained within the PDFs on this site are hyperlinked

1 TH/P6-22 Modelling of Prompt Deposition of Tungsten under Fusion Relevant Conditions A. Kirschner 1, D. Tskhakaya 2,3, D. Borodin 1, S. Brezinsek 1, J. Romazanov 1, R. Ding 4, Ch. Linsmeier 1 1 Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), 52425 Jülich, Germany 2 Fusion@ÖAW, Institute of Applied Physics, TU Wien, 14 Vienna, Austria 3 Institute of Theoretical Physics, University of Innsbruck, A-62 Innsbruck, Austria 4 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, 2331, P.R. China E-mail contact of main author: a.kirschner@fz-juelich.de Abstract. The prompt deposition of sputtered tungsten has been simulated with the impurity transport and plasma-wall interaction code ERO. Parameter studies have been carried out for the two electron densities 1E12 cm -3 and 1E15 cm -3 and electron temperatures between 1 ev and 2 ev. Also, the effects of the magnetic field strength (3T or 1T) and the anomalous cross field diffusion (D perp =.5 m 2 /s or zero) have been analysed. The amount of promptly deposited tungsten reaches values of 1% at the highest electron temperature and density. However, at 1 ev and 1E12 cm -3 no prompt deposition occurs at all. The simulations show that the impact energy of promptly deposited tungsten ions can be larger than expected from the energy gain within the sheath potential. This is in particular the case at high electron densities in combination with small electron temperatures, where entrainment of returning ions due to friction with the background plasma ions is very effective. Thus, the self-sputtering by promptly deposited tungsten can become significant, though, under the conditions studied no runaway sputtering takes place. A first estimation of prompt deposition during ELM conditions typically occurring at JET has been done. For this, the so-called streaming model has been applied with a stream velocity of 3.1E7 cm/s, which corresponds to deuterium ion energy of 1 kev, and plasma density of 1E14 cm -3 and temperature of 2 ev. With these assumptions the simulations result in about 95% prompt deposition. 1. Introduction Tungsten will be used in ITER as plasma-facing material for the divertor and is also a candidate material for future fusion devices like DEMO. Alongside its high melting temperature tungsten also shows relatively small physical sputtering due to its high atomic number. Moreover, the penetration of sputtered tungsten atoms into the plasma is limited owing to the large ionisation probability, which in combination with the large gyration radius can lead to significant amounts of deposition and therefore decreases the net-erosion. Usually in this context the term prompt deposition is introduced as deposition during the first gyration after erosion [1], which becomes effective if the ratio of ionisation length to gyration radius is smaller than one. Under certain conditions, e.g. very high electron density and temperature, the tungsten ions trajectories do not describe clear gyration motion anymore as the movement very near to the surface is dominated by the large electric field. Moreover, cross field diffusion can disturb the gyration. Thus the classical definition of prompt deposition as deposition during the first gyration radius becomes imprecise. Therefore, here

2 TH/P6-22 the term prompt deposition is used for ions, which after their ionisation need a time t < t Gyro for returning to the surface, where t Gyro is the time required for the tungsten ion to fulfil one full gyration cycle. The contribution at hand presents modelling results of prompt tungsten deposition carried out with the three-dimensional Monte Carlo code ERO [2]. A parameter study is given for different electron densities and temperatures, magnetic field strength and various assumptions for anomalous cross field diffusion. Also, the prompt deposition during ELM conditions will be addressed. Finally, the possible effect of runaway sputtering by self-sputtering due to returning tungsten ions is discussed. 2. Modelling of prompt deposition of sputtered tungsten atoms 2.1. Modelling assumptions To model the transport of sputtered tungsten atoms a roof like surface with 2 inclination angle relative to the magnetic field is used in ERO, see figure 1. The tungsten atoms are injected at the middle of the surface with cosine angular distribution and Thompson energy distribution around the tungsten surface binding energy (8.8 ev) to simulate physical sputtering. The electron and ion temperature and electron density are input parameters at the stagnation point, which is chosen to be 1 m away from the surface. According to the two point model for the scrape-off layer (SOL), the electron density n e decreases by a factor of two when moving inside the SOL along the magnetic field lines from the stagnation point to the sheath entrance [3] and the plasma flow velocity v Flow increases from zero to sound speed. The electron and ion temperatures (T e, T i ) are assumed to be constant within the whole simulation volume. The plasma parameters within the electrical sheath in front of the surface are not resolved as its thickness in the order of the Debye length D or the deuterium gyration radius r Gyro is rather small. However, first ERO simulations considering Particle In Cell simulations of the sheath characteristics have been done to study the influence on the prompt deposition of tungsten [4]. For the plasma parameters studied therein (2 ev, 5 ev and 6E13 cm -3 at the stagnation point), the modelled amounts of prompt deposition with resolved sheath characteristics were about 5 to 1% smaller than the ones modelled without resolved sheath. B W 9 - B 1 m FIG. 1. Set up for the ERO simulations. For the magnetic field angle B a value of 88 is used. The toroidal length (parallel to the B field) of the surface is 1 m, the poloidal length.1 m. The observation volume above the surface has a height of.1 m. The electrical potential U S in front of the surface is described by the following formula, showing an exponential scaling along the distance z from the surface with the Debye length D if the magnetic field is perpendicular to the surface and with the deuterium gyration radius r Gyro for shallow magnetic field: U S (z) = U f( B ) exp(-z/(2 D )) + U (1-f( B )) exp(-z/r Gyro )

3 TH/P6-22 Here U is the sheath potential drop, U 3 T e for T e = T i and neglecting secondary electron emission [5]. The function f( B ) approaches zero for B = 9 and one for B =. For the total potential the pre-sheath potential drop of about.7 T e is added. The tungsten atoms leaving the surface move along straight lines until their ionisation. The ionisation probability of the atoms is calculated by means of rate coefficients from [6]. Further ionisation of the tungsten ions is determined by the Lotz formula [7] as no final data are available at present within the ADAS database. The charged tungsten ions interact with the plasma background ions via Coulomb collisions. In addition, anomalous cross field diffusion can be included in the simulations. The movement due to the Lorentz force within the electromagnetic field is calculated by means of the Boris method, which includes automatically possible drift effects. Finally, thermal forces are considered using formulae of the temperature dependence along the magnetic field and resulting thermal forces from literature [8]. Reflection of tungsten ions returning to the surface is not considered in the studies presented here. 2.2. Prompt deposition of tungsten for steady state plasma conditions The simulations have been performed for two different electron densities, 1E12 cm -3 and 1E15 cm -3, within a plasma temperature range of 1 ev to 2 ev. The ion temperature is assumed to be equal the electron temperature, T i = T e. Two different magnetic field strengths have been assumed, 3 T in comparison to 1 T. The effect of the anomalous cross field diffusion has been studied by assuming D perp =.5 m 2 /s in comparison to no cross field diffusion. Figure 2 shows exemplarily the distribution of W atoms, W + and W 2+ ions above the surface integrated in poloidal direction for (1E12 cm -3, 2 ev) with no cross field diffusion and magnetic field of 3 T. z (mm) max W min W + W 2+ x (mm) FIG. 2. Modelled two-dimensional spatial distribution of tungsten atoms and ions above the surface for n e = 1E12 cm -3 and T e = 2 ev. The colour scaling of each picture (W, W + and W 2+ ) corresponds to the respective maximum intensity wherefore the intensity of the different species cannot be compared with each other.

Amount of prompt deposition (%) 4 TH/P6-22 Prompt deposition of tungsten only occurs at or near to the source location. For the example of figure 2 about 21% of injected W atoms are deposited promptly. In addition, about 13% is deposited non-promptly on the inclined surface. However, this value is somehow arbitrary as it strongly depends on the size of the surface considered. Particles which are not deposited leave the simulation volume for the example discussed, mainly in x direction, which can be seen also in figure 2. The modelled amounts of prompt deposition for the plasma parameter range studied are summarised in figure 3 for magnetic field of 3 T and 1 T and neglecting cross field diffusion (D perp = ). For all conditions, prompt deposition at 1 T is larger than for 3 T, which can be explained with the larger gyration radius of tungsten ions at the smaller magnetic field strength. Also, prompt deposition is significantly larger at the higher electron density due to smaller ionisation length of the sputtered tungsten atoms. At the high density of 1E15 cm -3 prompt deposition of 1% is simulated for high enough electron temperature whereas maximum prompt deposition of only about 47% is reached at 1E12 cm -3 in combination with 2 ev and 1 T. The amount of prompt deposition even goes to zero at the small electron density in combination with small electron temperatures. 1 9 8 7 6 5 4 3 2 1 1E12 3T 1E12 1T 1E15 3T 1E15 1T 5 1 15 2 Electron temperature (ev) FIG. 3. Modelled prompt deposition for two different electron densities (1E12 and 1E15 cm -3 ) and magnetic field strengths (3 T, 1 T) in dependence on the electron temperature. Cross field diffusion is not included in the simulations (D perp = ). The simulations including anomalous cross field diffusion with D perp =.5 m 2 /s lead to slightly larger prompt deposition in particular at the lower electron temperatures ( 5 ev), whereas at the higher electron temperatures no significant differences occur. For the estimation of self-sputtering due to returning tungsten ions the energy and angular distribution of these ions have to be known. The ERO simulations deliver this information taking into account the energy gain due to the sheath potential and friction with the background plasma ions via Coulomb collisions. For the above-presented parameter study, figure 4 shows the resulting mean impact energy (E mean ) and mean impact angle ( mean ) of promptly deposited tungsten ions. The impact angle is given relative to the surface normal, i.e. an impact angle of zero would correspond to normal incidence of the ion.

Mean impact energy (ev) Mean impact angle ( ) 5 TH/P6-22 14 12 1 8 6 4 2 1E12 3T 1E12 1T 1E15 3T 1E15 1T E_sheath 1E12 E_sheath 1E15 5 1 15 2 Electron temperature (ev) FIG. 4. Modelled mean impact energy (left) and mean impact angle (right) of promptly deposited tungsten ions. Cross field diffusion is not included in the simulations (D perp = ). The dashed lines in the left figure indicate the energy gain 3 Q meean T e within the sheath potential. The simulated mean energies of promptly deposited tungsten ions do not significantly depend on the magnetic field strength. In contrast, the electron density and temperature strongly influence the resulting impact energy. It is seen that the small density of 1E12 cm -3 leads to mean impact energies near or slightly larger than the energy E_sheath = 3 Q mean T e expected from ions passing through the sheath potential. The mean charge state Q mean is taken from the simulations and is equal to one for the low density cases. For the high density of 1E15 cm -3 the picture is different. Now at large electron temperatures the impact energy is smaller than expected from the sheath potential. For instance, at 2 ev the mean charge state of promptly deposited ions is about 2.2 resulting in E_sheath 13 ev compared to the modelled mean impact energy of only about 7 ev. Obviously the ionisation length at (1E15 cm -3, 2 ev) is smaller than the dimension of the sheath potential. At low electron temperatures and high electron density, however, the modelled mean impact energy is significantly larger than E_sheath. This can be explained by an effective entrainment under these conditions between the tungsten ions and the background deuterium plasma flow due to Coulomb collisions. The maximum impact energy of about 125 ev occurs at 2 ev and 1E15 cm -3, which is clearly larger than E_sheath 6 ev with Q mean = 1. The modelled mean impact angle of promptly deposited tungsten ions is rather insensitive on the magnetic field, compare figure 4 (right). Between 1 ev and 2 ev a mean impact angle of 2 3 occurs for both studied electron densities. For 1E12 cm -3 this does not change much when decreasing the electron temperature to 5 ev. For even smaller electron temperatures at this small density, prompt deposition becomes negligible or even zero. For the high electron density of 1E15 cm -3 an increase of the mean impact angle occurs when decreasing the electron temperature reaching a maximum mean value of about 8 at 1 ev. Also here the effect of entrainment becomes significant leading to an impact of tungsten ions, which is oriented along the magnetic field lines. Figure 5 shows the resulting sputtering yield Y of tungsten due to promptly deposited tungsten ions. The sputtering yield has been calculated by means of the so-called Eckstein fit formula with necessary fit parameters taken from [9]. The estimated sputtering yield considers the individual yield of each returning tungsten ion and therefore is not equal to Y(E mean, mean ) using the mean impact energy and angle of promptly deposited ions as input for the fit formula. 9 8 7 6 5 4 3 2 1 1E12 3T 1E12 1T 1E15 3T 1E15 1T 5 1 15 2 Electron temperature (ev)

Self-sputtering yield 6 TH/P6-22.4.3.2 1E12 3T 1E12 1T 1E15 3T 1E15 1T.1 5 1 15 2 Electron temperature (ev) FIG. 5. Estimated self-sputtering yield of promptly deposited tungsten ions. Cross field diffusion is not included in the simulations (D perp = ). As seen before for the mean energy and angle, the magnetic field strength has no significant effect on the resulting self-sputtering yield. For the parameter studied, largest sputtering yield is obtained for the high electron density of 1E15 cm -3 and an electron temperature of 2 3 ev. However, the maximum yield about.3 is clearly below one wherefore runaway erosion due to self-sputtering does not occur. A more detailed discussion about runaway erosion will follow in section 2.4. The simulations shown so far focused on the assumption of neglecting anomalous cross field diffusion. Further simulations assuming D perp =.5 m 2 /s instead have been performed for the same parameter range of electron density, temperature and magnetic field strength. There is a slight effect on the amount of prompt deposition, see discussion of figure 3. The modelled mean impact energies tend to be smaller when cross field diffusion is considered, which consequently also results in smaller self-sputtering yields. Particularly, the diffusion reduces the efficiency of the entrainment, which clearly reduces the impact energy at the high electron density in combination with small electron temperatures. As for the non-diffusion case the maximum self-sputtering yield appears at 1E15 cm -3 and 2 3 ev. However, considering diffusion leads to clearly reduced maximum yield of about.1 compared to.3 at these conditions but without diffusion. 2.3. Prompt deposition of tungsten for ELM conditions To study the effect of ELMs on the prompt deposition of sputtered tungsten an ERO simulation has been performed with plasma conditions based on observations of high power unseeded H-mode discharges at JET [1]. According to these experiments the deuterium ion impact energy is in the kev range whereas the electron temperature is around 2 ev. The high ion energy can be understood in the frame of the so-called Free Streaming Model in which the electrons transfer most of their parallel energy to the ions, see e.g. [11]. For the ERO modelling the deuterium ion energy is set to 1 kev resulting to a velocity of 3.1E7 cm/s, which is assumed to be the plasma flow velocity along the magnetic field lines. For the electrons a temperature of 2 ev and density of 1E14 cm -3 is assumed. These plasma conditions result in prompt deposition of sputtered tungsten of about 95%. For comparison,

Gross erosion (a.u.) Net erosion (a.u.) 7 TH/P6-22 typical inter-elm conditions (~1 ev, ~1E13 cm -3 ) lead to prompt deposition of about 6%. The mean impact energy of promptly deposited tungsten ions during the ELM is about 7 ev with a mean charge state of about 1.5. Obviously, under the ELM conditions considered here the entrainment effect is not very effective and thus the impact energy of promptly deposited tungsten ions is not very large. Together with rather low impact angles (in average 25 ) this consequently also leads to relatively low self-sputtering yield of about.5. 2.4. Runaway sputtering To study the conditions for runaway sputtering to occur, a simplified examination is done. If the exposure time is divided into time steps one can calculate the gross erosion N n at time step and each succeeding time step n as follows: n = : N = N BG + N BG Ret Y SZ n 1: N n = N n-1 + N BG (Ret Y SZ ) n+1 Here N BG is the number of particles eroded by the background plasma flux per time step, Ret is the ratio of particles promptly returning to the surface relative to the amount of sputtered particles and Y SZ the self-sputtering yield. Reflection of returning ions is not considered. Figure 6 illustrates the resulting time evolution of gross and net erosion for Ret =.8 and three different values of Y SZ. The value for N BG has been set to 1. 14 Gross Ero1 (Ret=.8, Ysz=1.1) 25 Net Ero1 (Ret=.8, Ysz=1.1) 12 Gross Ero2 (Ret=.8, Ysz=1.25) Gross Ero3 (Ret=.8, Ysz=1.255) 2 Net Ero2 (Ret=.8, Ysz=1.25) Net Ero3 (Ret=.8, Ysz=1.255) 1 8 15 6 1 4 2 5 2 4 6 8 1 Time (a.u.) FIG. 6. Illustration of gross (left) and net (right) erosion for different assumptions of the amount of returning species (Ret) and self-sputtering yield (Y SZ ). It is seen that the erosion reaches a steady state value for (Ret Y SZ ) < 1, increases linearly with exposure time for (Ret Y SZ ) = 1 and increases exponentially for (Ret Y SZ ) > 1. The latter two cases thus would lead to runaway sputtering. The product of prompt deposition amount and self-sputtering yield is always well below one for the tungsten sputtering cases studied in the previous sections wherefore no runaway sputtering occurs. According to the Eckstein fit formula, tungsten self-sputtering yields larger than one occur at impact energies larger than about 3 ev and impact angles around 6. For example Y SZ (3 ev, 6 ) 1.1. For runaway sputtering to occur with this yield, the amount of prompt deposition must be larger than 91%. Whereas such large amounts of prompt deposition have been observed within the 2 4 6 8 1 Time (a.u.)

8 TH/P6-22 presented parameter study, the modelled impact energy of promptly deposited tungsten was always smaller than about 13 ev leading to Y SZ well below one. Therefore, runaway sputtering is not expected for the parameter range studied within the present contribution. 3. Conclusions The prompt deposition of sputtered tungsten has been modelled with the ERO code. For the electron temperature range (1 ev to 2 ev) and magnetic field strengths (1T vs. 3T) studied, the amount of modelled prompt deposition varies between % and 47% for an electron density of 1e12 cm -3 and between 2% and 1% for 1E15 cm -3. Thus, at plasma temperatures and densities not too small prompt deposition in principal significantly can reduce the net erosion and by this increase the life time of plasma facing components. However, selfsputtering by returning tungsten ions has to be considered, which reduces the positive effect of prompt deposition. Tungsten self-sputtering yields calculated with the Eckstein formula for the studied parameter range vary between 1E-5 and.4 with the maximum values obtained at the large electron density and small electron temperatures. It should be noted that these yields could be enhanced for the sputtering of deposited tungsten as reported earlier, see e.g. [12]. As next step the simulation of tungsten erosion and deposition at JET and along the ITER divertor plates is foreseen. Besides the local prompt deposition such simulations then also includes the non-prompt deposition of tungsten ions, which could have larger impact energies (in particular at high electron density and small electron temperature) due to the entrainment after longer travelling paths. These returning tungsten ions could lead to significant erosion at the location of their impact. Acknowledgements This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 214 218 under grant agreement No 63353. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work has been done under WP PFC. It has been supported by the Sino-German Center for Research Promotion under Contract No. GZ769. References [1] NAUJOKS, D., et al., J. Nucl. Mat. 21 (1994) 43 [2] KIRSCHNER, A. et al., Nucl. Fus.4 (2) 989 [3] STANGEBY, P.C., The plasma boundary of magnetic fusion devices, IOP, Bristol and Philadelphia (2), ISBN 753 559 2 [4] KIRSCHNER, A., Contrib. Plasma Phys. 56, No. 6-8, 622 (216) [5] STANGEBY, P.C., McCRACKEN, G.M., Nucl. Fus. 3 (199) 1225 [6] VAINSHTEIN, L.A., et al., J. Phys. B: At. Mol. Opt. Phys. 44 (211) 12521 [7] HIGGINS, M., et al., Atomic and molecular data for fusion, Part III: recommended cross sections and rates for electron ionisation of light atoms and ions: copper to uranium, Tech. Rep. CLM-R294, Culham Laboratory, Abingdon, Oxfordshire, UK (1989) [8] STANGEBY, P.C., ELDER, J.D., Nucl. Fus 35 (1995) 1391 [9] BEHRISCH, R., ECKSTEIN, W., Sputtering by particle bombardment, experiments and computer calculations, from threshold to MeV energies, Springer, 26 [1] GUILLEMAUT, C., et al., Phys. Scripta T167 (216) 145 [11] FUNDAMENSKI, W, et al., Plasma Phys. Control. Fus. 48 (26) 19 [12] KIRSCHNER, A., et al., J. Nucl. Mat. 438 (213) S723