Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

James O'Callaghan, Walter T. Shmayda, Henry Smith, Matthew Sharpe, Lyn McWilliam, Philippa Almond, Rhiann Canavan, Nathan Eedy, Gowri Karajgikar, David Kennedy, Hazel Gardner, Fatimah Sanni, Alec Shackleford, Callum Steventon, Josh Ruby, Tshepo Mahafa, David T. Hoelzer, Kalle Heinola, Anthony Hollingsworth

Research output: Contribution to journalArticlepeer-review

Abstract

Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount of total tritium compared with austenitic stainless steel AISI 304L, reduced activation ferritic-martensitic (RAFM) Eurofer-97, and advanced nanoferritic alloy 14YWT. Microstructural analyses using electron backscatter diffraction (EBSD) indicate that the number of grains and mean grain size is not a dominant factor in near surface tritium uptake. The quantity of iron dissolved in the surface oxide appears to be the major factor in encouraging tritium absorption.

Original languageEnglish
Pages (from-to)1-0
Number of pages2
JournalIEEE Transactions on Plasma Science
DOIs
StateAccepted/In press - 2024

Keywords

  • Chemicals
  • Etching
  • Liquids
  • Metals
  • Stainless steel alloys
  • Steel
  • Temperature measurement
  • XPS
  • Zinc
  • surface inventory
  • tritium absorption
  • tritium bulk profiles
  • tritium solubility

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