1 / 17

Update of ITER first wall geometry, SOL profiles and Power fluxes,

Update of ITER first wall geometry, SOL profiles and Power fluxes,. Marc Goniche CEA. IRFM. F-13108 Saint-Paul-lez-Durance. France HCD08-03-01 EFDA Task 8-9 March 2010. ITER First Wall (FW). Poloidal (18) limiter-like configuration at outer side to protect ports (and antennas)

nelia
Download Presentation

Update of ITER first wall geometry, SOL profiles and Power fluxes,

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Update of ITER first wall geometry, SOL profiles and Power fluxes, Marc Goniche CEA. IRFM. F-13108 Saint-Paul-lez-Durance. France HCD08-03-01 EFDA Task 8-9 March 2010

  2. ITER First Wall (FW) • Poloidal (18) limiter-like configuration at outer side to protect ports (and antennas) • Detachable FW from Blanket Modules • PFC technology not yet finalized From C.Lowry, IO,

  3. Power flux on First Wall 2007 VSOL = 100m/s VSOL = 30m/s B2-EIRENE simulation + empirical extrapolation of mesurements (QDT=10) (A.Loarte, Nov.08) Te,FW = 10-20eV Ti,FW/Te,FW ~ 2 F//,FW=5MW/m-2 ne,FW = 0.5-1.5×1019m-3 VSOL < 100m/s =>lQ,farSOL=Lc VSOL/cs,SOL <0.17m

  4. 3D Field line tracing using CASTEM 2de sep FLFS ceiling BSM 11 banana-shaped far SOL region upper ceiling BSM contact points FLFS*-wall BSM 18 outboard BSM (not recessed) BSM log-shape [P.C. Stangeby, R. Mitteau] Reference plasma equilibrium, QDT = 10 burning phase (*FLFS : First Limited Flux Surface) (exaggerated shape)

  5. Density profiles in the far SOL (2) High ne, low Te, long decay length ne = 1.5 1019 m-3, Te=10 eV, Ti = 2.Te Low ne, high Te, short decay length ne = 5 1018 m-3, Te=20 eV, Ti = 2.Te New reference scenario (∆R = 10cm) + Lc calculations with shaped wall Assuming λ = cst = 0.17m previous reference scenario (∆R = 5cm) + Lc calculations with smooth wall Assuming λ = cst = 0.04m Slightly different between BSM, see new presentation of S.Carpentier, to-morrow at CCIC => ne=2.6x1017m-3 1cm behind BSM (R-Rsep=0.20m) S.Carpentier, CCIC Dec.09,

  6. Heat Fluxes to be considered for the LHCD antenna • Parallel Flux : conduction /convection • Perpendicular flux : • - Plasma radiation • - Charge Exchange (CX) • - Neutrons • - Fast ions • RF losses

  7. Port, antenna 100 mm 100 mm Current shaping does not account for possible port plugs Rplasma = 8350 mm 100 mm C-modules, Port plug, antenna 100 mm flux surfaces every 10 mm Parallel heat flux of LHCD antenna ? F// < 5 exp-(30/50)=2.7MW/m2 (conductive) F// < 5 exp-(30/10)=0.3MW/m2 (convective) • Port plug should be 30-50mm behind FW • Field lines intercept port plugwith a~2.5° (40mrad)=> F<0.1MW/m2 From R.Mitteau, IO

  8. Power e-fold decay length • lQ=(L// / (2pRq)n* lQ0 = (3/150)n * lQ0 • n=1/2 diffusion • n=1 convection • lQ = lQ0/ 7 (diff.) or 50 (conv.) • lQ0 = 0.05 – 0.17 m (far SOL) •  lQ < 170/7 = 25mm (diff) •  lQ < 170/50 = 4mm (conv)

  9. 30mm Toroidal view LHCD antenna shaping Poloidal view • Strong self-shadowing • V-shape in tor.direc. of the port-plug is highly recommended • Lower heat flux on FW by fast electrons

  10. Parallel heat flux of LHCD antenna During ELMs ? t-riseELM = 250ms (sc.2) -550ms(sc.4) F//,ELM < 0.1MW/m2 , 3cm behind FW

  11. Plasma radiation • Prad, FW /Ptot < 60% => P rad, FW /S = 70MW/683m2 • Peaking factor < 2 (<3 for MARFEs) • Radiation max near the bottom of the antenna X-point Top JET LH antenna 0.2 (sc.2) and 0.29 (sc.4) MW/m2

  12. Power fluxes by CX • Estimated from B2-EIRENE code and empirical scaling of total plasma outflux => Large uncertainty • CX heat flux max near the outer mid-plane • Energy of neutrals : up to 1.6keV (sc.2)=> Sputtering (Be) 0.25 (sc.2) and 0.20 (sc.4) MW/m2  Prad + PCX < 0.5 MW/m2

  13. lQ ~ 0.10m Power fluxes by neutrons 5MW/m3 • Maximumneutron wall load calculated using a 3D model22 yields 0.78 MW/m2 at the outboard side (fromNUCLEAR ANALYSIS REPORT (NAR) G 73 DDD 2 W 0.2, p19-20 & 24) • 5MW/m3 , lQ=0.1m (previously assumed) • Monte-Carlo neutron code required for exact calculation of the neutron damping in the antenna

  14. Fast Ions dB/B =0.2% Kramer , IAEA2008 • Fusion born alpha particles lost due to the effect of the Magnetic Ripple amplitude • dB/B should be reduced with magnetic inserts to dB/B =0.2% • With toroidal field ripple only P <0.1MW/m2 (sc.4), <0.02MW/m2 (sc.2) • Computations have been done with a conservative value of 0.3MW/m2

  15. RF losses • RF losses are maximum at mid-height of the large side of the WG • RF losses are modulated along propagation (RC  0) • Average loss depends on reflection R but also on the phase j of the reflected wave •  Provided by coupling code • DDD2001 assumed 13 kW/m2 for Copper, 28 kW/m2 for Beryllium => needs to be up-dated • Should have a minor impact(PRFlosses,Be/Ptot ~5%)

  16. Conclusion • Radiation/CX will not exceed 0.5MW/m2 • Decay length of this flux inside WGs is shortand needs to be accurately determined (Marfisi’s presentation) • Parallel heat flux on antenna front is negligible • Upper value for neutron heating source is taken to be 5MW/m3 • Fast ion flux should be precised ( ITER ripple) • RF losses are a small contribution to power loading of the antenna

  17. Annex: Minimum heat flux for LH coupling ne=ncut-off=3x1017m-3, Te=15eV, sheath factor g=7 => F// = 0.2 MW/m2

More Related