Direct observation of solute segregation to voids in a fast-neutron irradiated Mo/1.0 at% Ti Alloy

Alfred Wagner*, David N. Seidman

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

The atom-probe field-ion microscope (FIM) has been employed to study segregation effects, to voids, in a Mo/1.0 at% Ti alloy specimen; this specimen had been irradiated with fast neutrons at ~700° C, to a fluence of ~1 × 1022n/cm2 (E > 1 MeV), in the row 7 midplane position of EBR-II. It had been shown previously, by several other research groups, that this alloy exhibits an enhanced swelling relative to pure Mo under fast-neutron irradiation. The results of the present work, on this alloy, indicated that: (1) titanium does not segregate significantly to voids; (2) the concentration of titanium in solid solution and the spatial distribution of titanium was not affected significantly by the irradiation at 700°C; (3) carbon was not detected in solid solution in either the irradiated or unirradiated specimens; (4) the preceding two results indicated that largescale resolution of TiC or Mo2C precipitates had not occurred as a result of the irradiation; and (5) segregation of carbon to a void was detected. The small amount of carbon segregation which had been detected may have been sufficient to enhance the nucleation rate and/or change the sink properties of a void and thus affect the void growth-rate.

Original languageEnglish (US)
Pages (from-to)48-56
Number of pages9
JournalJournal of Nuclear Materials
Volume83
Issue number1
DOIs
StatePublished - Aug 1979

Funding

* This work was supported by the US Department of Energy under Contract No. EY-764-3158. *OOO.A ddi-tional support was received from the National Science Foundation through the use of the technical facilities of the Materials Science Center at Cornell University. ** Now at BelI Laboratories, 600 Mountain Avenue, Murray Hill, NJ 07974, USA.

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • General Materials Science
  • Nuclear Energy and Engineering

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