Tungsten: An option for divertor and main chamber PFCs in future fusion devices
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1 ASDEX Upgrade Tungsten: An option for divertor and main chamber PFCs in future fusion devices R. Neu, R. Dux, A. Kallenbach, C.F. Maggi, T. Pütterich, M. Balden, T. Eich, J.C. Fuchs, O. Gruber, A. Herrmann, H. Maier, H.. Müller, M. O Mullane*, R. Pugno, I. Radivojevic, V. Rohde, A.C.C. Sips,. Suttrop, A. hiteford*, M.Y. Ye, ASDEX Upgrade Team MPI für Plasmaphysik, Euratom Association, Garching, Germany *University of Strathclyde, Glasgow, United Kingdom Motivation Status of -Coverage Recent Results: Diagnostic / -Divertor / -limiter / Impurity Control Conclusions & Outlook th IAEA FEC 6/11/ Vilamoura/Portugal iaea_tit
2 Motivation ITER: tungsten baffles in the first operation phase probably full wall in its reactor like operation phase ASDEX Upgrade: transformation into a full tungsten-coated tokamak Several issues are addressed: operation must be compatible to PFCs high performance scenario development along compliant route investigation of sputtering and migration C transport in a mixed material environment (see M. Mayer, EX/P5-) seed impurity scenarios to replace intrinsic C radiation diagnostics (spectroscopy) th IAEA FEC 6/11/ R. Neu iaea_mot1
3 Tungsten plasma facing components in ASDEX Upgrade Full -divertor during 95/96 campaign Step by step increase of -coated plasma facing components (since 1999) towards a full device rationals: - risk minimisation - partitioning of installation time - production capacity 3/ campaign: 65% of total area (.8 m ) of plasma facing surfaces is covered by -coatings: old components: 1 µm PVD (on graphite) new components: µm PVD (on graphite & CFC) th IAEA FEC 6/11/ R. Neu iaea_com1
4 Tungsten plasma facing components in ASDEX Upgrade new components for the campaign: complete upper divertor upper divertor th IAEA FEC 6/11/ R. Neu iaea_com
5 Tungsten plasma facing components in ASDEX Upgrade new components for the campaign: complete upper divertor outer baffle of lower divertor lower divertor th IAEA FEC 6/11/ R. Neu iaea_com3
6 Tungsten plasma facing components in ASDEX Upgrade new components for the campaign: complete upper divertor outer baffle of lower divertor 6 tiles of one guard limiter lower 3 tiles of guard limiter Sec8 tungsten graphite th IAEA FEC 6/11/ R. Neu iaea_com
7 Diagnostic successful simulation of VUV and SXR spectra within ADAS framework VUV # s Measurement + +3 <+ +3 B V 1s-p (.859nm) /3 +5 large number of spectral lines arising from different ionisation states radial reconstruction of c radiance Modelled Spectrum + +3 QC (+7-+35) log(n w /[a.u.]) T e kev +5 + (Cu As) (QC) +6 (Ni). ρ pol 1. SXR 5 6 wavelength [nm] th IAEA FEC 6/11/ R. Neu iaea_diag1 Brightness [1 5 m - sr -1 nm -1 ] #16778 T = 3.9 kev e,cntr 7 - measurement ADAS modelled spectrum wavelength [nm].7.8
8 Diagnostic successful simulation of VUV and SXR spectra within ADAS framework large number of spectral lines arising from different ionisation states radial reconstruction of c consistent treatment of atomic data within ADAS refinement of cooling factor 1 - -peaking 198@.6s average ion model (old) cooling factor L [cm 3 z ] 1-7 ADAS projected ADAS (Cowan/PB) p6 +38 d1 +8 3d1 +6 continuum radiation 3p6 +56 T e [ev] p6 +6 s +7 th IAEA FEC 6/11/ R. Neu iaea_diag
9 Operation with divertor H-mode with P 7.5M heat configuration scan: Upper SN LSN USN inner lim. no remarkable difference of -content between USN () / LSN (C) first USN phase at low density has increased n (hot divertor?) limiter phase uses -coated inner column as limiter strong rise of n similar to Div I experiment: divertor is not a strong tungsten source unless T is too high e M 1 19 m -3 M ka 1 15 m P NBI n e H α USN LSN USN IL P div,up up-div I thermo n (ρ=.7) c (ρ=.7) P div,dn mhd P ICRH # time (s) th IAEA FEC 6/11/ R. Neu iaea_div1 1 kj
10 Operation with divertor power load in between ELMs heat flux (M/m ) high performance discharge β N =.8, H 98y =.95 n e/n gr =.75 in upper SNU feasible at low c Upper Divertor #19 3. s inner outer radial dist. (a.u.) th IAEA FEC 6/11/ R. Neu iaea_div toroidal dist. (a.u.) Γ D (5 1 s ) T (kev) e c (1 kev) _ 19 n e (1 m -3) c (.5 kev) β N D (a.u.) P (M) NBI P (M) ICRH Time (s) α H 98y,
11 erosion by thermal and fast particles Erosion at guard limiter: particle fluxes from spectroscopic measurements energy deposition from thermocouples in 3 tiles post mortem analysis (X-ray fluorescence): max. erosion 1 µm, ( > 1 x larger than measured at other main chamber components) ➄ ➅ ➁ ➃ ➂ ➄ ➅ x x x th IAEA FEC 6/11/ R. Neu iaea_ero1
12 erosion by thermal and fast particles Erosion at guard limiter: particle fluxes from spectroscopic measurements energy deposition from thermocouples in 3 tiles post mortem analysis (X-ray fluorescence): max. erosion 1 µm, ( > 1 x larger than measured at other main chamber components) same range of influx densities and effective sputtering yields as in Div I Y eff Γ (1 m - s -1 ) Γ (1 19 m - s -1 ) H Rsep(m) P(M) D α radial scan towards guard limiter #187 l.o.s. ➁-➅ t (s) th IAEA FEC 6/11/ R. Neu iaea_ero
13 erosion by thermal and fast particles erosion at guard limiters depends strongly on: plasma parameter influx density follows roughly: Γ exp [ - x / λ] x = separatrix distance, λ = 1.5 cm distance of observed limiter region to separatrix localized ion load if plasma does not fit limiter shape shielding of limiter by other limiters separatrix medium triangularity limiter ➁ ➂ ➃ ➄ ➅ separatrix high triangularity limiter (log Γ ) - (R. Dux, PSI) Ch and 5 Ch 3 and - - x /1.5cm power decay lengths:.8 cm (see A. Herrmann, EX/-Rb) th IAEA FEC 6/11/ R. Neu iaea_ero
14 erosion by thermal and fast particles Theoretical estimate for erosion yield + thermal ion load with 1% C assuming equilibrated carbon coverage: explains range of effective sputtering yield does not explain large deposited energy per D fast ions contribute strongly to energy deposition less sputtered particles per deposited energy! Y = Γ eff /Γ D Preliminary results form code calculations (FAFNER, ASCOT) support picture % C + E fast=kev D E dep = T=1eV T=5eV T=eV thermal ions (f=%) D + f Γ fast 1 1 D E [ev] dep f=5% T=5eV R. Dux (PSI) total deposited energy on tile shot integrated deuterium flux = average deposited energy per D (discharges with dominant staedy state) th IAEA FEC 6/11/ R. Neu iaea_ero6
15 behaviour / operational issues Conditions for low -concentration (c < 1 ) divertor configuration control impurity transport in plasma centre: (accumulation) avoid strongly peaked density profiles combined with low anomalous transport central heating by ECRH/ICRH small reduction of performance ( 1%) (see A. Stäbler, EX/-5) -5 c 3 kev c 1 kev imp. transport from Si LBO: strong increase of D an for central heating NBI NBI+ICRH P <.5 P ICRH P.5 P ICRH NBI NBI NBI+ECRH P ECRH < 1M P ECRH 1M n e ()/n e (.8) impurity control see: R. Dux, EX/P6-1 th IAEA FEC 6/11/ R. Neu iaea_ops
16 behaviour / operational issues Conditions for low -concentration (c < 1 ) divertor configuration control impurity transport in plasma centre (accumulation): avoid strongly peaked density profiles combined with low anomalous transport central heating by ECRH/ICRH small reduction of performance ( 1%) control impurity transport in H-Mode edge transport barrier (impurity inventory): avoid long ELM free H-phases stay away from H-L threshold ELM pace-making integrated scenario with: central heating ELM pace-making radiation cooling by Ar seeding -5-6 tungsten concentration (1 ) ELM frequency (Hz) see P. Lang, EX/-6 ρ.7 p IEC scenario Ar seeded intrinsic th IAEA FEC 6/11/ R. Neu iaea_ops3
17 Prediction for ITER reference scenario (inductive operation) Q=1 P(NBI)=M U 75mV T,T fixed e Dan at edge: 1m /s in centre: varied v (fit to GLF3 profile) an D,v from NEOART neo 6 components D,T,He,Be,Ar, n from quasi neutrality e i neo edge densities fixed He( 3%) Be(%) Ar(.1%) (.1%) loop n (1 m -3 ) D (m s -1 ) no strong accumulation expected as long as D D and (v/d) not increasing with Z an th IAEA FEC 6/11/ R. Neu iaea_iter1 > neo e DT He x1 an He Be Ar DT r (m) c/c edge (1) an e i He Be Ar r (m) see R. Dux, EX/P T (kev)
18 Summary progressive increase of coated PFCs towards a full tungsten based ASDEX Upgrade ICRH Limiter diagnostic well established and ready for extrapolation typ. c increased with area more demanding plasma operation: equilibria, heating profile, ELM activity USN and LSN discharges have similar content divertor source is not dominant fast particle play important role for low field side erosion impurity seeding compatible with -PFCs stable integrated scenario available no accumulation expected for ITER reference scenario further extension of surfaces under way, full device first possible in 6/7 th IAEA FEC 6/11/ R. Neu iaea_con1
19 Extension of surface / main investigations /5 extensions: newly designed guard limiter vertical plate between lower divertor and PSL aux. limiter between upper PSL and divertor ICRH antenna limiter guard limiters Investigations will be concentrated on: performance of coatings parameter dependance of influx from ICRH and guard limiter interconnection of content and discharge conditions / plasma parameters behaviour with seeded impurities provide information for full device (first possible in 6/7) th IAEA FEC 6/11/ R. Neu iaea_out1
20 Extension of surface / main investigations /5 extensions: newly designed guard limiter vertical plate between lower divertor and PSL aux. limiter between upper PSL and divertor ICRH antenna limiter ICRH Limiter Investigations will be concentrated on: performance of coatings parameter dependance of influx from ICRH and guard limiter interconnection of content and discharge conditions / plasma parameters behaviour with seeded impurities provide information for full device (first possible in 6/7) th IAEA FEC 6/11/ R. Neu iaea_out
21 Performance of tiles divertor baffle ( µm) power load: coating problems delamination at test limiter ( µm): CFC surface very inhomogeneous central column (ramp/down limiter) beam dump (1 µm) > discharged, no damage upper divertor ( µm) P 1 M/m avg melting at edges: estim. power > M/m no strong degradation during second half of campaign upper divertor loss of -coating µm melting th IAEA FEC 6/11/ R. Neu iaea_per1
22 behaviour / operational issues Conditions for low -concentration (c < 1-5 ) divertor configuration divertor limiter divertor #1788 HH-fac P rad (1 k) ASDEX Upgrade SXR (1 /m ) n (1/m ) e T e (ev) Γ (1/m s) R[m] R[m] R[m] Langmuir probe (equatorial plane) # time (s) n (1 /m ) th IAEA FEC 6/11/ R. Neu iaea_ops1 C D e α 19 3 PNBI (M) inner gap (cm) DCN H time (s)
23 Long term evolution of concentration gradual increase of concentration (5-1 x) for increasing coverage (1 3) ohmic discharge: good measure for source centr. col. + PSL, in. baffle + up. div., out. baffle 7.1 m 1.6 m.8 m Ohmic standard discharge I = 8 ka, n =.5 1 /m p e 19 3 similar increase for H-Mode discharges, partly obscured by transport effect of boronisation not very pronounced concentration C content in main plasma barely changed first hints for increased divertor electron temperatures shot number boronisation siliconisation vent th IAEA FEC 6/11/ R. Neu iaea_lte1
24 behaviour / operational issues limiter ITBs: high central -content divertor ITBs c w strongly reduced compared to limiter operation ITB formation and decay usually not influenced long term evolution of c w not clear 1 T e, T i (kev) 8 t=1.1s...8 c T e, T i (kev) P, P (M) NBI ECCD #175 decay of i-itb concentration central edge ctr ECCD n e (1 m ) mhd (MJ) th IAEA FEC 6/11/ R. Neu iaea_itb1
25 erosion by thermal and fast particles Distribution of lost ions from NBI (beam +3) FAFNER start distribution of fast beam ions ASCOT (Helsinki University) fast ion orbits + collisions First (preliminary) simulations support assumption of considerable fast ion contribution to limiter load z[m] R[m] th IAEA FEC 6/11/ R. Neu iaea_ero7
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