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Current status of assessment of Tritium inventory in all-W device

Current status of assessment of Tritium inventory in all-W device. O.V. Ogorodnikova and E. d’Agata. Be : port limiter, primary wall, baffle. W : upper vertical targets, dome. Initial plasma-facing materials for ITER divertor. CFC : lower vertical targets. ITER divertor.

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Current status of assessment of Tritium inventory in all-W device

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  1. Current status of assessment of Tritium inventory in all-W device O.V. Ogorodnikova and E. d’Agata

  2. Be: port limiter, primary wall, baffle W: upper vertical targets, dome Initial plasma-facing materials for ITER divertor CFC: lower vertical targets

  3. ITER divertor Upper part InnerVT Tungsten Act as baffles for the neutrals 100 m2 Upper part OuterVT Dome

  4. ITER divertor Lower part InnerVT Interact directly with the scrape-off layer plasma 50 m2 Outer VT CFC Lower part OuterVT

  5. ITER divertor Lower part InnerVT Interact directly with the scrape-off layer plasma 50 m2 Outer VT W Lower part OuterVT

  6. Vertical Target W monoblocks (upper and bottom half) Mario Merola and ITER team

  7. - flat tile concept cooled by HV- Dome W flat tiles with HV cooling Mario Merola and ITER team

  8. CuCrZr W First Wall W macrobrush: W/CuCrZr Plasma spray W: PSW/CuCrZr Mario Merola and ITER team

  9. Tritium inventory Joachim Roth: PSI-18 Toledo, May 26, 2008

  10. Talk outline Normal operation regime • - T retention in outer vertical target • - T retention in inner vertical target • - T retention in dome • - T retention in FW Comments to off-normal operation regime

  11. Talk outline Normal operation regime • - T retention in outer vertical target • - T retention in inner vertical target • - T retention in dome • - T retention in FW

  12. Vertical target at glancing angle of incidence The particles impinge the surface with a glancing angle of alfa=1-3. It will result in high heat and particle fluxes on the edges

  13. Vertical target at glancing angle of incidence inhomogeneous temperature distribution => inhomogeneous T retention The particles impinge the surface with a glancing angle of alfa=1-3. It will result in high heat and particle fluxes on the edges The asymmetrical heat and particle loads as well as asymmetrical cooling result in inhomogeneous temperature distribution

  14. Performance of W under short transient thermal loads Erosion due to off-normal events (?) plasma MK200-U 20 shots @ 1.4 MJm-2 I. Arkhipov, A. Zhitlukhin, Troitsk, RF

  15. Influence of off-normal events plasma How much T will be co-deposited (or re-deposited) and where? MK200-U 20 shots @ 1.4 MJm-2 I. Arkhipov, A. Zhitlukhin, Troitsk, RF

  16. Steady state loads at outer vertical target The total power load consists of about 30% due to irradiation from the plasma and about 70% due to particles heating

  17. Steady state loads at outer vertical target Correlation of the particle fluxes, plasma temperature and power load on outer divertor target

  18. Steady state loads at outer vertical target Correlation of the particle fluxes, plasma temperature and power load on outer divertor target

  19. Steady state loads at outer vertical target • An increase of the plasma temperatureresults in • an increaseof the density and power load

  20. Steady state loads at outer vertical target • An increase of the plasma temperatureresults in • an increaseof the density and power load • Shift of a maximum to the strike point

  21. R&D • n-irradiation effect: • Wmax=f(dpa, tem) • He ions implantationsimultaneously with D ions: influence on D retention and TDS • Helium ion bombardment leads to development of the • surface relief and destruction of near surface layer • Flux dependence • Off-normal events and ELM’s should be taking into account

  22. n-irradiation effect • Embrittlement: W, as typical for bcc metal, after neutron irradiation embrittled due to irradiation hardening and loss of strength at grain boundaries due to contamination by interstitial impurities. • Due the high activation of W there is no direct data on the effect of neutron irradiation on tritium retention. • Voids: • For W despite of low swelling, the vacancy void • formation occurs at ~ 400C < Tirr < 1000C and • damage dose more than ~ several dpa. • Typical structure - superlattice of voids: • ~ 5 - 50 nm diameter and lattice parameter ~ 60 - 200 nm

  23. n-irradiation effect Voids: For W despite of low swelling, the vacancy void formation occurs at ~ 400¡C < Tirr < 1000¡C and damage dose more than ~ several dpa. Typical structure - superlattice of voids: ~ 5 - 50 nm dia and lattice parameter ~ 60 - 200 nm Tungsten for ITER divertor - Tungsten for ITER divertor - damage ~ < 0.1 dpa, T- 200-1000¡C (with replacement) - no changes of physical properties; - no significant changes at transient events (VDE/disr.); - no changes of erosion; - bulk tritium retention seems low (to be confirmed);

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