The Influence of Radiation, Mechanical, and Plasma-Induced Damage on Deuterium Retention in Tungsten

Wall Forum

  • Datum: 17.10.2018
  • Uhrzeit: 15:30 - 16:30
  • Vortragende(r): Mikhail Zibrov
  • IPP
  • Ort: Garching
  • Raum: Seminarraum D3

Tungsten will be used as a plasma-facing material in the divertor of ITER and is also likely to be used as the divertor and the first wall material in DEMO and future fusion power plants. Retention of hydrogen isotopes in plasma-facing materials is an issue from the safety and economic points and of view. It is well established that hydrogen retention in tungsten is governed by the trapping in lattice defects, but the contributions of some defect types are not completely clear. This contribution reports the results of recent experiments devoted to the investigation of deuterium trapping characteristics of vacancies, vacancy clusters, dislocations, and blisters in tungsten. This was achieved by using specially prepared samples having one dominant and well-characterized defect type. It was demonstrated that vacancies and jogs on dislocations bind deuterium more strongly than dislocations, but less strongly than vacancy clusters.

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