Microstructure and mechanical property of ferritic–martensitic steel cladding under a 650°C liquid sodium environment
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference18 articles.
1. TECHNICAL RATIONALE FOR METAL FUEL IN FAST REACTORS
2. Interactions between structural materials and liquid metals at elevated temperatures
3. Sodium effects on mechanical performance and consideration in high temperature structural design for advanced reactors
4. Compatibility Study between 316-series Stainless Steel and Sodium Coolant
5. D.L. Smith, R.H. Lee, ANL-7891, 1972.
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1. Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation;Nuclear Engineering and Technology;2024-07
2. Effect of LBE corrosion on microstructure of amorphous Al2O3 coating by magnetron sputtering;Surface and Coatings Technology;2022-08
3. Further insights into the mechanisms involved in the corrosion of 316L(N) austenitic steel in oxygenated liquid sodium at 550 °C;Corrosion Science;2020-04
4. Material Performance in Sodium;Comprehensive Nuclear Materials;2020
5. Axial crack resistance of cladding tubes for fast reactors;Annals of Nuclear Energy;2017-12
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