Microstructure of the {chi} phase in ODS ferritic alloys
- Ecole Centrale Paris, Malabry (France)
- Commissariat a l`Energie Atomique, Gif sur Yvette (France). Service de Recherches Metallurgiques Appliquees
Ferritic alloys as core components of a fast neutron reactor are more resistant to swelling in the temperature range 400 to 650 C than austenitic ones but they have usually a poor creep resistance in this temperature range. In order to improve their creep properties, oxide dispersion strengthened (ODS) ferritic alloys can be elaborated by mechanical alloying, a process derived from powder metallurgy, compaction and extrusion. Therefore, two ODS ferritic alloys, DT (DT 2906) and DY (DT2203Y03), containing an intermetallic {chi} phase, have been developed by CEN/SCK, Belgium. The lattice parameter and the chemical composition of the {chi} phase have been determined by XR analysis and TEM examinations in two ODS ferritic steels. In both DT and DY alloys it is found that: the {chi} phase is partially coherent with the ferritic matrix, the stoichiometry of the {chi} phase is Fe{sub 42}Cr{sub 9}Ti{sub 5}Mo{sub 2}, and the lattice parameter is 0.886 nm. These results, which are similar to oxide free materials indicate that oxide strengthening do not affect the {chi} phase composition.
- OSTI ID:
- 233892
- Journal Information:
- Scripta Materialia, Vol. 34, Issue 9; Other Information: PBD: 1 May 1996
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 NUCLEAR REACTOR TECHNOLOGY
FERRITIC STEELS
MICROSTRUCTURE
CHROMIUM ALLOYS
TITANIUM ALLOYS
MOLYBDENUM ALLOYS
REACTORS
MATERIALS
INTERMETALLIC COMPOUNDS
CHEMICAL COMPOSITION
TRANSMISSION ELECTRON MICROSCOPY
X-RAY DIFFRACTION
X-RAY SPECTROSCOPY
ORIENTATION
LATTICE PARAMETERS
STOICHIOMETRY
EXPERIMENTAL DATA