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Oxide particles in oxide dispersion strengthened steel neutron-irradiated up to 158 dpa at Joyo.
- Source :
-
Journal of Nuclear Materials . Oct2024, Vol. 599, pN.PAG-N.PAG. 1p. - Publication Year :
- 2024
-
Abstract
- We investigated the stability of oxide nano particles in oxide dispersion-strengthened (ODS) steel, which is a promising candidate material for next-generation reactors, under neutron irradiation at high temperature to high doses. MA957, a 14Cr-ODS steel, was irradiated with Joyo in Japan Atomic Energy Agency under irradiation conditions of 130 dpa at 502 ºC, 154 dpa at 589 ºC, and 158 dpa at 709 ºC. Three-dimensional atom probe (3D-AP) and transmission electron microscope (TEM) observation were performed to characterize the oxide particles in the ODS steels. A high number density of Y-Ti-O particle was observed in the unirradiated and irradiated samples. Almost no change in the morphology of the oxide particles, i.e. average diameter, number density, and chemical composition, has been observed in the samples irradiated to 130 dpa at 502 ºC and to 154 dpa at 589 ºC. A slight decrease in number density was observed in the sample irradiated to 158 dpa at 709 ºC. The hardness of any of the irradiated samples was almost unchanged from that of the unirradiated sample. It was revealed that the oxide particles existed stable, and the strength of the material was sufficiently maintained even after being neutron irradiated to high dose of ∼160 dpa at high temperature up to 700 ºC. Atom maps for Yttrium, Titanium and Oxygen in ODS steel before/after neutron irradiation obtained with three-dimensional atom probe. [Display omitted] [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00223115
- Volume :
- 599
- Database :
- Academic Search Index
- Journal :
- Journal of Nuclear Materials
- Publication Type :
- Academic Journal
- Accession number :
- 178401149
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2024.155252