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Journal Articles

Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors

Mingda Yu, Juan Du, Xuejiao Shao, Zhuo Pu
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2024, 146(6): 061505.
Paper No: PVT-24-1074
https://doi.org/10.1115/1.4066677
Published Online: October 23, 2024
...Mingda Yu; Juan Du; Xuejiao Shao; Zhuo Pu The structural safety of the cylinder in liquid-cooled fast reactors is significantly affected by high-temperature thermal striping on the cylinder wall due to the free level fluctuation. Based on the elevated-temperature creep-fatigue evaluation theory...
View Article titled, Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear <span class="search-highlight">Fast</span> <span class="search-highlight">Reactors</span>
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Topics: Creep, Cylinders, Damage, Fast neutron reactors, Fatigue, Fracture (Materials), Stress, Temperature, Transients (Dynamics), Stainless steel