Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors
Year: 2024
Type: article
DOI: 10.1115/1.4066677
Authors: Mingda Yu, Juan Du, Xuejiao Shao, Zhuo Pu
Institution: Nuclear Power Institute of China
Language: English
Subfield: Aerospace Engineering
Field: Engineering
Domain: Physical Sciences
Open Access status: closed
Award: G3337453538
OpenAlex ID: W4402936756
