Development of ODS ferritic-martensitic steels for application to high temperature and irradiation environment
Description
Iron oxide dispersion strengthened alloys are candidate for nuclear fuel cladding. Therefore, it is crucial to control their microstructure in order to optimise their mechanical properties at temperatures up to 700 deg C. The industrial candidates, ODS ferritic alloys, present an anisotropic microstructure which induces a weakening of mechanical properties in transversal direction as well as the precipitation of brittle phases under thermal aging and irradiation. For this purpose, we tried to develop a material with isotropic properties. We studied several 9Cr-1Mo ferritic/martensitic alloys, strengthened or not by oxide dispersion. The mechanical alloying was performed by attribution and powders were consolidated by hot extrusion. In this work, different metallurgical characterisation techniques and modelling were used to optimise a new martensitic ODS alloy. Microstructural and chemical characterization of matrix has been done. The effect of austenitizing and isochronal tempering treatments on microstructure and hardness has been studied. Oxide distribution, size and chemical composition have been studied before and after high temperature thermal treatment. The study of phase transformation upon heating has permitted the extrapolation to the equilibrium temperature formation of austenite. Phase transformation diagrams upon cooling have been determined and the transformation kinetics have been linked to austenite grain size by a simple relation. Fine grain size is unfavourable for the targeted application, so a particular thermal treatment inducing a coarser grain structure has been developed. Finally, tensile properties have been determined for the different microstructures. (author)
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Additional details
Additional titles
- Original title (French)
- Developpement d'une nouvelle nuance martensitique ODS pour utilisation sous rayonnement a haute temperature
Publishing Information
- Imprint Pagination
- 210 p.
- Report number
- CEA-R--5918
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 32007851
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AGING; CALORIMETRY; CEA; CEA SACLAY; CHEMICAL COMPOSITION; CHEMICAL REACTION KINETICS; COOLING; CREEP; CRYSTAL STRUCTURE; DILATOMETRY; DUCTILITY; FUEL CANS; GRAIN GROWTH; GRAIN SIZE; HARDNESS; HEAT TREATMENTS; IRON BASE ALLOYS; IRRADIATION; ISOTROPY; OPTICAL MICROSCOPY; OPTIMIZATION; QUENCHING; RECRYSTALLIZATION; RESEARCH PROGRAMS; SCANNING ELECTRON MICROSCOPY; SWELLING; TRANSMISSION ELECTRON MICROSCOPY; YTTRIUM OXIDES
- Descriptors DEC
- ALLOYS; CEA; CHALCOGENIDES; DEFORMATION; ELECTRON MICROSCOPY; FRENCH ORGANIZATIONS; IRON ALLOYS; KINETICS; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; NATIONAL ORGANIZATIONS; OXIDES; OXYGEN COMPOUNDS; REACTION KINETICS; SIZE; TENSILE PROPERTIES; THERMAL ANALYSIS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; YTTRIUM COMPOUNDS