Analysis of defect structural evolution in fcc metals irradiated with neutrons under well defined boundary conditions

T. Yoshiie, Y. Satoh, Q. Xu

Research output: Contribution to journalConference articlepeer-review

14 Citations (Scopus)

Abstract

Defect structural evolutions near pre-existing defects such as surfaces, grain boundaries and dislocations in fcc metals are studied to clarify point defect processes during irradiation. By the comparison of Au irradiated as thin foils with fission neutrons and fusion neutrons, the PKA energy to produce a stacking fault tetrahedron is determined to be 80 keV with a production efficiency of 0.05. Grain boundaries are effectively used to detect the existence of one-dimensional motion of interstitial clusters. In Ni and Ni binary alloys (2 at.% Si, Cu, Ge or Sn), there is a good coincidence between the void growth and one-dimensional motion of interstitial clusters. The coincidence is, however, not good for Cu. Screw dislocations with jogs turn into helical dislocations by absorbing one type of point defects. The difference of freely migrating defects between fission and fusion neutron irradiation is measured as a function of irradiation dose and it is concluded that the same number of freely migrating defects is generated from each subcascade in fission and fusion neutron irradiated Ni.

Original languageEnglish
Pages (from-to)81-87
Number of pages7
JournalJournal of Nuclear Materials
Volume329-333
Issue number1-3 PART A
DOIs
Publication statusPublished - 2004 Aug 1
EventProceedings of the 11th Conference on Fusion Research - Kyoto, Japan
Duration: 2003 Dec 72003 Dec 12

ASJC Scopus subject areas

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

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