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Journal Articles

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031109.
Paper No: NERS-19-1078
https://doi.org/10.1115/1.4044530
Published Online: June 5, 2020
View Article titled, Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C
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Topics: Alloys, Oxidation, Steam, Steel, Superheating, Weight (Mass), Spallation (Nuclear physics)
Proceedings Papers

Assessment Oxidation Kinetics and Products in SCWR Media of Austenitic ODS Steels With Different Austenite Stabilisers

Maria Mihalache, Mihail Mihalache, Iulia Dumitrescu, Zhangjian Zhou
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A014, July 7–11, 2014
Paper No: ICONE22-30665
https://doi.org/10.1115/ICONE22-30665
View Paper titled, Assessment Oxidation Kinetics and Products in SCWR Media of Austenitic ODS Steels With Different Austenite Stabilisers
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Topics: Oxidation, Steel, Supercritical water reactors, Coolants, Water, Corrosion resistance, Pressure, Stainless steel, Temperature, Titanium
Proceedings Papers

Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System

Zhangjian Zhou, Ming Li, Lu Liao, Pei He, Yingli Xu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 219-222, May 17–21, 2010
Paper No: ICONE18-29854
https://doi.org/10.1115/ICONE18-29854
View Paper titled, Assessment of ODS Ferritic Alloy for Advanced Nuclear Energy System
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Topics: Alloys, Nuclear power, High temperature, Steel, Oxidation, Temperature, Cladding systems (Building), Corrosion, Generation IV reactors, Mechanical properties