Modelling of tritium retention and target lifetime of the ITER divertor using the ERO code

A. Kirschner, D. Borodin, S. Droste, V. Philipps, U. Samm, G. Federici, A. Kukushkin, A. Loarte

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Material erosion, transport and deposition in the divertor of ITER are modelled with the Monte-Carlo impurity transport code ERO taking into account chemical erosion, physical sputtering, enhanced chemical erosion of redeposited carbon and a beryllium influx from main chamber erosion. The continuous deposition of beryllium leads to reduced carbon erosion along the divertor plates with increasing exposure time. With 1% beryllium in the edge plasma an upper value of the long-term tritium retention rate can be estimated to about 15.9 mg T/s. For 0.1% beryllium this number decreases to about 6.4 mg T/s. These numbers do not change significantly with the sticking assumption for hydrocarbons. The erosion of the divertor plates is less critical. Maximal erosion rates of 0.4 nm/s with 1% beryllium and 1.8 nm/s with 0.1% beryllium occur at the outer target. Erosion due to transient heat loads is not yet included in the modelling.

Original languageEnglish
Pages (from-to)91-95
Number of pages5
JournalJournal of Nuclear Materials
Issue number1-3
StatePublished - 15 Jun 2007
Externally publishedYes


  • B0100
  • Beryllium
  • Chemical erosion
  • E0400
  • ERO
  • Erosion and deposition
  • ITER
  • P0500
  • R0900


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