Erosion lifetime of ITER divertor plates

H. D. Pacher, I. Smid, G. Federici, Yu Igitkhanov, G. Janeschitz, R. Raffray, G. Vieider

Research output: Contribution to journalArticle

36 Scopus citations

Abstract

For ITER divertor operation in the detached regime, erosion of divertor plates made of beryllium, carbon fibre composites and tungsten-rhenium alloys is evaluated. Erosion due to (a) physical and, for CFC, chemical sputtering (including surface temperature variation over the lifetime because of neutron irradiation), (b) disruption thermal quench using published data and (c) evaporation and melt layer loss (metals) for infrequent high-power transients (20 MW / m2, up to 10 s) is evaluated both with and without the reduction of net incident power by radiation from the evaporated impurities ('low density vapour shield'). The composite lifetime is calculated for normal operation (detached, 10% transients, 10% disruptions); the effect of an increase in transient frequency and in incident power (semi-attached operation) is determined. The resulting erosion lifetime excludes beryllium, whereas both CFC and W-3%Re yield acceptable lifetimes.

Original languageEnglish (US)
Pages (from-to)255-259
Number of pages5
JournalJournal of Nuclear Materials
Volume241-243
StatePublished - Feb 11 1997

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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    Pacher, H. D., Smid, I., Federici, G., Igitkhanov, Y., Janeschitz, G., Raffray, R., & Vieider, G. (1997). Erosion lifetime of ITER divertor plates. Journal of Nuclear Materials, 241-243, 255-259.