Title of article
Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature
Author/Authors
Yamashita، نويسنده , , S. and Akasaka، نويسنده , , N. and Ukai، نويسنده , , S. and Ohnuki، نويسنده , , S.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2007
Pages
6
From page
202
To page
207
Abstract
Microstructural observation was performed on a neutron-irradiated oxide dispersion strengthened (ODS) ferritic steel with emphasis on oxide behavior, including phase stability under irradiation at elevated temperature (∼973 K). Transmission electron microscopy observation of the Y–Ti complex oxide particles showed they were fine (∼40 nm) whereas the Ti-oxide particles were relatively coarse (∼300 nm). Dispersion parameters of oxide particles, such as mean size and number density, changed due to irradiation. This implies recoil resolution of the oxide particles. When irradiated at 973 K, some Y–Ti complex oxides survived and interacted with the dislocation structures, which delayed the dislocation recovery and stabilized the elongated grain structure. It is considered that oxide particles could be effective pinning points of dislocations in motion under irradiation to a dose of ∼100 dpa.
Journal title
Journal of Nuclear Materials
Serial Year
2007
Journal title
Journal of Nuclear Materials
Record number
1365394
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