Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics
NUCLEAR ENERGY SCIENCE AND ENGINEERING|更新时间:2025-01-07
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Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics
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“In the field of nuclear energy, experts have built a nuclear thermal material coupling framework based on the MOOSE platform to study the influence of lead bismuth reactor oxidation corrosion on core parameters, providing important references for the application of lead bismuth reactors.”
JI Xu,CHAI Xiang,ZHANG Lefu,et al.Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J].NUCLEAR TECHNIQUES,2024,47(11):110604.
JI Xu,CHAI Xiang,ZHANG Lefu,et al.Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J].NUCLEAR TECHNIQUES,2024,47(11):110604. DOI: 10.11889/j.0253-3219.2024.hjs.47.110604.
Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics增强出版