NSUF 10-249: Developing a Mechanistic Understanding of Radiation Tolerant Materials
The objective of this project will be to conduct ion irradiation experiments at MIBL to provide a more quantitative description of the stability of Ti-, Y- and O-enriched nanoclusters (NC) and nano-size grain structure that are present in the advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy that was developed at ORNL. The possibility that NC contain a high vacancy concentration may provide other opportunities for exploring point defect trapping mechanisms, including the trapping of He. Another opportunity for investigation is whether the NC will re-nucleate if they are dissolved by extreme irradiation conditions. The planned experiments at MIBL will consist of using heavy ions to irradiate specimens of 14YWT to high doses over a range of temperatures and to implant high concentrations of He in specimens. Following the ion irradiation experiments on bulk specimens, detailed microstructural analysis using Transmission Electron Microscopy (TEM), Energy-Filtered TEM (EFTEM) and Local Electrode Atom Probe (LEAP) will be performed on specimens that will be prepared by the liftout/ Focused Ion Beam (FIB) method. The analyses will focus on: changes in the size, number density and composition of NC; the accumulation of point defects, i.e. dislocation loops and cavities, resulting from irradiation damage coupled with He implantations to elucidate the point defect trapping mechanisms by NC and grain boundaries; and irradiation induced segregation of solute atoms with grain boundaries. The results obtained from the ion irradiation experiments at MIBL will guide further developments in advanced radiation tolerant materials that are required for future nuclear reactor concepts.
Additional Info
| Field | Value |
|---|---|
| Abstract | The objective of this project will be to conduct ion irradiation experiments at MIBL to provide a more quantitative description of the stability of Ti-, Y- and O-enriched nanoclusters (NC) and nano-size grain structure that are present in the advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy that was developed at ORNL. The possibility that NC contain a high vacancy concentration may provide other opportunities for exploring point defect trapping mechanisms, including the trapping of He. Another opportunity for investigation is whether the NC will re-nucleate if they are dissolved by extreme irradiation conditions. The planned experiments at MIBL will consist of using heavy ions to irradiate specimens of 14YWT to high doses over a range of temperatures and to implant high concentrations of He in specimens. Following the ion irradiation experiments on bulk specimens, detailed microstructural analysis using Transmission Electron Microscopy (TEM), Energy-Filtered TEM (EFTEM) and Local Electrode Atom Probe (LEAP) will be performed on specimens that will be prepared by the liftout/ Focused Ion Beam (FIB) method. The analyses will focus on: changes in the size, number density and composition of NC; the accumulation of point defects, i.e. dislocation loops and cavities, resulting from irradiation damage coupled with He implantations to elucidate the point defect trapping mechanisms by NC and grain boundaries; and irradiation induced segregation of solute atoms with grain boundaries. The results obtained from the ion irradiation experiments at MIBL will guide further developments in advanced radiation tolerant materials that are required for future nuclear reactor concepts. |
| Award Announced Date | 2010-04-06T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kory Linton |
| Irradiation Facility | None |
| PI | David Hoelzer |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | 249 |