Deuterium and helium ion irradiation of nanograined tungsten and tungsten–titanium alloys

L. Buzi, M. Yeh, Y. W. Yeh, O. K. Donaldson, M. I. Patino, J. R. Trelewicz, N. Yao, R. Doerner, B. E. Koel

Research output: Contribution to journalArticle

Abstract

Tungsten (W), a primary candidate for the plasma-facing components of nuclear fusion reactors (e.g. the divertor region in ITER) is susceptible to cracks, blisters, bubbles, and other morphological changes when irradiated with energetic particles. This work investigated two new materials, nanograined W and a nanograined W–Ti alloy, for potential use as plasma-facing materials. Their retention properties and morphological changes after exposure to deuterium (D) and helium (He) plasma at 50 eV and surface temperatures of 500 and 1000 K were analyzed. Nanograined W was found to have smaller blisters and be less prone to fuzz formation than commonly-utilized micro-grain polycrystalline W. Additionally, the nanograined W–Ti alloy exhibited a lower concentration of blisters on its surface than pure W, including nanograined W.

Original languageEnglish (US)
Article number100713
JournalNuclear Materials and Energy
Volume21
DOIs
StatePublished - Dec 2019

All Science Journal Classification (ASJC) codes

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

Keywords

  • Deuterium
  • Helium
  • Plasma-facing materials
  • Tungsten

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