-3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 n o rm alised in ten sity [a.u .] d istan ce d to L C FS [cm ] ap ex p o sitio n #113112 phase I #113112 phase II #113112 phase III T e =85eV, n e =3.0x10 18 m -3 T e =60eV, n e =4.3x10 18 m -3 T e =45eV , n e =5.3x10 18 m -3 -4.5 -4.0 -3.5 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 -4.5 -4.0 -3.5 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 -4.5 -4.0 -3.5 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 -4.5 -4.0 -3.5 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.5 1.0 d istan ce d to L C FS [cm ] efl n o rm a lised in te n s ity [a .u .] #115837 r =48.0cm T e =47eV, n e =5.5x10 18 m -3 #115836 r =48.5cm T e =47eV, n e =3.8x10 18 m -3 #115834 r =49.0cm T e =41eV, n e =3.2x10 18 m -3 #115831 r =50.0cm T e =38eV , n e =2.5x10 18 m -3 n o zzle p o sitio n gas inlet position References 0 10 20 30 40 50 60 70 80 90 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 0 10 20 30 40 50 60 70 80 90 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 0 10 20 30 40 50 60 70 80 90 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 400.88 nm /505 nm 498.26 nm /505 nm line ratio in jectio n 429.46 nm /505 nm line ratio T e,edge [eV ] line ratio sp u tterin g -4.5 -4.0 -3.5 -3.0 -2.5 -2.0 -1.5 -1.0 -0.5 0.0 0.5 0.0 0.2 0.4 0.6 0.8 1.0 d istan ce d to L C FS [cm ] in jectio n W I(400.88 nm ) in jectio n W I(505 nm ) relative intensity [a.u.] sp u tterin g W I(400.88 nm ) sp u tterin g W I(505 nm ) 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 efo ld in g len g th e fl [cm ] in verse io n isatio n rate 1/ S [10 -7 s] in jectio n lin ear fit in jectio n sp u tterin g lin ear fit sp u tterin g GKU v W = 700 m /s GKU v W = 2100 m /s G K U 6 x v W = 700 m /s G K U 6 x v W = 2100 m /s Experiment 1) W sputtering experiment Aim: • study of W erosion for different plasma conditions by aim of spectroscopy • reference experiment to compare to W injection Experimental realisation: • spherical limiter with W- and C- half • inserting limiter in scrape of layer (SOL), limiter apex 0.5 cm behind last closed flux surface (LCFS) • variation of edge plasma parameters by changing central plasma density and temperature by deuterium fuelling within one discharge (T e, edge = 45 – 85 eV) 2) W injection experiment Aim: • simulate W source by calibrated WF 6 injection • realisation of controlled W source in a tokamak experiment • determine proportionality factor between tungsten particle flux Γ W and photon flux ϕ W : inverse photon efficiency S/XB (S: ioniSation rate, X: eXcitation rate, B: Branching ratio) • in-situ calibration of spectroscopic method Experimental realisation: • inserting gas inlet in scrape-off layer 2 - 4 cm behind last closed flux surface • variation of edge plasma parameters by changing radial gas inlet position from discharge to discharge (T e, edge = 38 – 47 eV) General experimental data: • large radius R = 1.75 m • small radius a = 0.46 m • plasma current I p = 0.35 MA • toroidal magnetic field B t = 2.25 T • auxiliary heating power P aux = 1.2 MW • deuterium fuelling • spectroscopic observation via: 2D cameras equipped with interference filters setup of high resolution and overview spectrometers W sputtering W injection 1 ) 2 ) input for modeling with GKU code [3] (collisional-radiative model) 2D camera recording with narrowband interference filter measured / fitted W I (400.88 nm) lines Comparison of W I line ratios • similar line ratios for different lines for injected and sputtered W • level population independent from W release process, mainly determined by plasma parameters line ratios vs. T e, edge line ratios sputtering / injection injection Comparison with GKU modeling [3]: • by modifying modeling by a factor of 6 both experimental results can be approximated • possible reasons for uncertainties: overestimation of ionisation rate coefficients for W I no velocity distribution in modeling included • broader profiles for lower n e and T e • maximum moves away from injection hole for lower n e and T e Radial profiles for W I (400.88 nm) line i e e efl v n v S v • efl: e-folding length • v: W velocity • S: ionisation rate (including n e and T e ) • <v e i >: W I ionisation rate coefficient (ATOM code [4]) Velocity of injected W: • slope ratio of linear fits velocity ratio R v = <v sput >/v inj = 3 • with <v sput > = 2122 m/s (assuming Thompson distribution) v inj = 707 m/s • v inj too high to be understood from dissociation energy release dissociation path length must be taken into account v inj has to be considered as effective parameter with dimensions of velocity plasma center plasma center sputtering n e, edge and T e, edge behave inversely for comparison of both experiments ionisation rates must be considered T e, edge , n e, edge T e, edge n e, edge Introduction Penetration Depths of Injected/Sputtered W in the Plasma Edge Layer of TEXTOR M. Laengner a* , S. Brezinsek a , J.W. Coenen a , A. Pospieszczyk a , D. Kondratyev a , D. Borodin a , H. Stoschus b , O. Schmitz a , V. Philipps a , U. Samm a and the TEXTOR team a Institute of Energy and Climate Research - Plasma Physics, Forschungszentrum Jülich GmbH, Association EURATOM-FZJ, Partner In the Trilateral Euregio Cluster, Jülich, Germany b Oak Ridge Institute for Science Education, Oak Ridge, Tennessee 37830, USA Summary and Conclusions Tungsten (W) is foreseen as the plasma-facing material in the ITER divertor due to its beneficial properties like high melting temperature, low physical sputtering yield and small fuel retention. However, only a small amount of W (~10 -5 W/D) can be tolerated in the core plasma as it can cause strong radiation losses and hamper the fusion burn. Thus, it is of high importance to understand W as an impurity source and to determine the W source distribution. In this context two aspects are essential: • in-situ determination of the W source strength by spectroscopy means • characterisation of the interaction of W with the plasma by the penetration depths. To address these aspects two experiments have been set up at the tokamak TEXTOR: 1)The first experiment was performed to study the erosion of W under different plasma conditions. 2)A WF 6 injection experiment was performed with the aim to • realise a controllable W source • determine the inverse photon efficiencies, the so-called S/XB values [2] for different W I and W II lines to finally convert photon fluxes into W particle fluxes. By the comparison of both experiments with respect to • W particle velocities • energy level population a conclusion can be drawn in which way injected W bears similarities to sputtered W and how far it can be applied to simulate a source of sputtered W. 1) W velocities and e-folding lengths: • velocity ratio for injected / sputtered W about a factor of 3 • v inj = 707 m/s dissociation path must be taken into account • measured e-folding lengths approximated by GKU by assuming a modification of a factor of 6: ionisation rate coefficients used in GKU might be overestimated no velocity distribution of particles included in modeling 2) Energy level population: similar line ratios for W I for injected and sputtered W • indication for same energy level population • level population independent from W release process, mainly determined by plasma parameters • effective S/XB values from WF 6 injection can be applied for sputtered W 3) Modeled S/XB values: GKU can reproduce curve shape for (S/XB) eff vs.T e but measured values are systematically lower 4) Measured effective S/XB values: values from multimachine fit including weight loss, W(CO) 6 and WF 6 calibration applied for first erosion measurements at JET (see G.v. Rooij I3) 20th International Conference on Plasma Surface Interactions 2012 | Mai 21 — 25, 2012 | Eurogress Aachen, Germa *m.laengner@fz- juelich.de [1] S. Brezinsek et al 2011 Phys. Scr. T145 (2011) 014016 [2] Pospieszczyk A et al 2010 J. Phys. B: At. Mol. Opt. Phys. 43 144017 [3] Vainshtein L et al 2007 Plasma Phys. Control. Fusion 49 1833 [4] Vainshtein L et al 2011 J. Phys. B: Atom. Mol. Opt. Phys. 44 125201 [5] http://physics.nist.gov/PhysRefData/ASD/lines_form.htm Penetration depth of W: analysis for W I at 400.88 nm Measured effective S/XB values for W I lines multimachine fit W I (400.88 nm) [6,7,8] • effective S/XB values systematically lower than modeled by GKU • consistent with assumption of overestimated ionisation rates • values from multimachine fit including WF 6 calibration with density scan applied for first erosion measurements at JET (see G.v. Rooij I3) W I (400.88 nm) and (522.47 nm) NIST W I energy level diagram [5] [6] Geier A et al 2002 Plasma Phys. Control. Fusion 44 2091 [7] Nishijima D et al 2011 Phys. Plasmas 18 019901 [8] Steinbring J, Spektroskopische Untersuchung von zerstäubtem Wolfram in einer linearen Plasmaanlage, diploma thesis, 1997, university of Berlin P2-070 NIST tables version 3 energy level configuration wave number [cm -1 ] [nm] tokamak experiment TEXTOR position of gas inlet / limiter limiter / gas inlet design side view top view WF 6 injection 0 20 40 60 80 100 0 10 20 30 40 50 60 70 80 90 100 0 250 500 750 1000 1250 1500 TEXTOR,W I(400.88 nm ) effective S /X B W I(400.88 nm ) T e,edge [eV ] GKU,W I(400.88 n m ) , T W = 0.3 eV 522.47 nm effective S /X B W I(522.47 nm ) TEXTOR,W I(522.47 nm ) 400.88 nm GKU,W I(522.47 n m ) , T W = 1.0 eV Results