Hydrogen in Neutron-irradiated Materials

This experimental activity, part of the Hydrogen Permeation CRP, consists of the analysis of samples and undertaking hydrogen permeation and retention research with fusion reactor materials having been irradiated with neutrons. The aim is to increase the knowledge and to evaluate experimental results obtained on the effects of neutron irradiation-induced damage with respect to hydrogen permeation. This is achieved by coordinated research activities at participating institutes utilizing same analysis methodologies.

Sample characteristics

  • Material: ITER-grade W Plansee (provided by D. Terentyev, SCK•CEN, Belgium)
  • Preparation: i) rod, ii) rod recrystallized at 1600 °C for 1h
  • Irradiation dose: 0.072 dpa, 0.083 dpa and 0.098 dpa
  • Irradiation temperature: 600 °C, 800 °C and 1200 °C

Sample analyses and research methods

  • Pre-characterisation and defect analysis: positron annihilation spectroscopy (PAS)
  • Permeation: plasma-driven permeation (PDP); gas-driven permeation (GDP)
  • Fuel retention: thermal desorption spectrometry (TDS); nuclear reaction analysis (NRA)
  • Post-characterisation: PAS

For more information please contact fusion-data@iaea.org.

Participants

6 participants from 3 countries.

Edward SHELTON Culham Centre for Fusion Energy, United Kingdom
Filip TUOMISTO Department of Physics, University of Helsinki, Finland
Anthony HOLLINGSWORTH Culham Centre for Fusion Energy, United Kingdom
Kalle HEINOLA IAEA
Tommy AHLGREN Department of Physics, University of Helsinki, Finland
Dmitry TERENTYEV SCK•CEN, Belgium