1 / 16

J. Roth 1 With the help of and discussions with

D/T retention in W, Be and C. J. Roth 1 With the help of and discussions with K. Schmid 1 , M. Mayer 1 , A. Kirschner 2 , A. Kukushkin 2 1 M ax-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany

nate
Download Presentation

J. Roth 1 With the help of and discussions with

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. D/T retention in W, Be and C J. Roth1 With the help of and discussions with K. Schmid1, M. Mayer1, A. Kirschner2, A. Kukushkin2 1 Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany 2 Institut für Plasmaphysik, FZ Juelich, EURATOM Association, Jülich, Germany 3ITER Joint Central Team, Garching Joint Worksite, Garching, Germany Outline: Implantation into CFC, W and Be materials Present knowledge about co-deposition Total inventories dependent on fluence and time Relevance for ITER

  2. Carbon fibre composites

  3. CFC-material irradiated with 200 eV D ions exposed to 100 eV D plasma Dependence on fluence

  4. CFC-material: irradiated with 200 eV D ions exposed to 100 eV D plasma

  5. Tungsten

  6. W: exposed to high-flux (1024 D/m2s) 200 eV D plasma Dependence on temperature at 2x1024 D/m2s Single crystalline W Polycrystalline W

  7. W:irradiated with 200 eV D ions Polycrystalline W Retention is strongly dependent on material structure. Largest retention in plasma-sprayed coatings

  8. Beryllium

  9. Be:: irradiated with 200 and 1000 eV D ions No deep diffusion Saturation of retention

  10. Be: mainly review of data from 1990’s From review of R. Anderl et al., JNM 273 (1999) 1 D retention saturates. For 1 keV D ion irradiation, saturation is reached at a fluence of 1023 D/m2. For D ion irradiation at low temperatures (below 400 K), deuterium is trapped in the implantation zone. When the irradiation temperature increases, the D retention decreases.

  11. Comparison

  12. Total retention of D

  13. M. Baldwin, K. Schmid et al., 16th PSI Portland (2004) 1 Be Balden, Mayer, Roth (1999) C 0.1 D/C, D/W W M. Mayer et al. (1996) B 0.01 400 600 800 1000 Temperature (K) Temperature (K) Co-deposition in fusion devices contaminated clean Be If C and O fluxes are comparable to Be fluxes, the layer will grow as a BeO with incorporated C and D. D concentrations vary between ~0.3 D/Be at 300 K and ~0.01 D/Be at 600 K.

  14. Retention due to co-deposition • Andreas Kirschner, ERO • Assumptions: • T in carbon layers: T/C = 0.05 at target, T/C = 0.5 in remote areas T in beryllium layers: T/Be = 0.05 (PISCES)

  15. Be concentrations after wall erosion Andrei Kukushkin, B2/Eirene Klaus Schmid, DIVIMP 0.2% Be ITPA Tarragona:

  16. Total retention with ITER material mix • Initially, implantation into CFC and Be dominates • The T limit is reached due to co-deposition with C and/or Be • W not important for inventory

More Related