Progress in Nuclear Energy
 2023
DOI: 10.1016/j.pnucene.2023.104711
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An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction

Qifan Yu
1
,
Suizheng Qiu
2
,
Chenglong Wang
3
et al.
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Cited by 10 publications
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Numerical analysis and structural optimization of a DLC coated capacitance wire-mesh sensor for measuring liquid metal-gas two-phase distribution

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et al. 2024
Annals of Nuclear Energy
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Research of VDT scheme for porous media thermal-hydraulics analysis of plate-type fuel assembly

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Bubble transport during SGTR accident in lead-cooled fast reactor: A machine learning

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Nuclear Engineering and Design
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