Research of Thermal–Hydraulic Characterization in Narrow-Slit Flow of Core Bypass Under the Fuel Assembly Blockage Accident Condition of SMILE Lead-Cooled Fast Reactor in the Range of Natural Circulation Flow Rate

Springer proceedings in physics 2026

View at publisher

Authors: Xiaotian Wang, Daogang Lu, Yangguang Zhang, Qiong Cao

DOI: 10.1007/978-981-95-3241-4_60

Cited by: 0

References: 8

Fields of Study & Subjects

Nuclear Engineering Thermal-Hydraulics Heat transfer and supercritical fluids Nuclear reactor physics and engineering

References 8