Relationships between mechanical behavior and microstructural evolutions in Fe 9Cr–ODS during the fabrication route of SFR cladding tubes
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference18 articles.
1. Structural materials challenges for advanced reactor systems
2. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts
3. CEA developments of new ferritic ODS alloys for nuclear applications
4. The development and stability of Y–Ti–O nanoclusters in mechanically alloyed Fe–Cr based ferritic alloys
5. ODS Ferritic/martensitic alloys for Sodium Fast Reactor fuel pin cladding
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1. Formulation of high-temperature strength equation of 9Cr-ODS tempered martensitic steels using the Larson–Miller parameter and life-fraction rule for rupture life assessment in steady-state, transient, and accident conditions of fast reactor fuel;Journal of Nuclear Materials;2024-05
2. Microstructure Evolution and Mechanical Properties of a High Cr Oxide Dispersion-Strengthened Steel through STARS Route Followed by Hot Isostatic Pressing;Journal of Materials Engineering and Performance;2024-04-08
3. Effect of directional anisotropy on mechanical properties of 9Cr Ferritic/Martensitic ODS steels processed by mechanical alloying and powder forging;Materials Today Communications;2023-12
4. Optimization of the Pressure Resistance Welding Process for Nuclear Fuel Cladding Coupling Experimental and Numerical Approaches;Metals;2023-01-31
5. Comprehensive analysis of the cladding tubes manufactured by a new 10Cr1SiY ferrite/martensitic steel;Nuclear Materials and Energy;2022-09
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