Microstructure and mechanical properties of 16 Cr-ODS ferritic steel for advanced nuclear energy system
Author:
Publisher
IOP Publishing
Subject
General Physics and Astronomy
Link
http://stacks.iop.org/1742-6596/419/i=1/a=012036/pdf
Reference14 articles.
1. Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems
2. Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT
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1. Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics;International Journal of Technology;2024-05-17
2. Oxidation behavior of oxide dispersion strengthened (ODS) steel sintered by arc plasma sintering (APS) foraccident tolerant fuel (ATF) cladding material;AIP Conference Proceedings;2024
3. 16Cr3Al-Hf ODS steel: Surface effects of high laser intensity of 1015 W/cm2 in ambiences of air, helium and vacuum;Fusion Engineering and Design;2023-06
4. Isothermal Oxidation Behavior of Ferritic Oxide Dispersion Strengthened Alloy at High Temperatures;Journal of Engineering and Technological Sciences;2022-03-31
5. Synthesis and microstructure evaluation of ODS steel 316L with zirconia dispersion;Journal of Physics: Conference Series;2021-05-01
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