Published July 2013 | Version v1
Journal article

The effect of displacement damage on deuterium retention in tungsten exposed to D neutrals and D2 gas

  • 1. Hydrogen Isotope Research Center, University of Toyama, Toyama 930-8555 (Japan)
  • 2. Max-Planck-Institut für Plasmaphysik, EURATOM Association, D-85748 Garching (Germany)
  • 3. Tritium Technology Group, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan)

Description

Samples of polycrystalline ITER-grade W and recrystallized W were irradiated at room temperature with 20 MeV W ions to displacement damage up to 0.5 dpa. The damaged W samples were then exposed to (i) D neutrals at 403–573 K and (ii) D2 gas at 673–1073 K and pressures of 1.2 and 100 kPa. Trapping of deuterium in the damage zone was examined by the D(3He, p)4He nuclear reaction with 3He energies between 0.69 and 4.0 MeV allowing determination of the D concentration up to a depth of 6 μm. It has been found that generation of the W-ion-induced displacement damage leads to accumulation of deuterium in the damage zone up to concentration depending on the exposure temperature and, at temperatures ⩾673 K, on the D2 gas pressure. Thermal desorption spectra allowed a conclusion that deuterium is mainly accumulated in the form of D atoms bound to inner walls of vacancy clusters

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2013.01.208

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2013.01.208;
PII
S0022-3115(13)00216-X;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
438
Journal Issue
Suppl
Journal Page Range
p. S959-S962
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
20. international conference on plasma-surface interactions in controlled fusion devices
Acronym
PSI-20
Dates
21-25 May 2012
Place
Aachen (Germany)

Optional Information

Copyright
Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.