Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Cited by
26 articles.
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1. Prediction of critical heat flux in rod bowing geometries by coupled subchannel analysis and mechanistic model;Annals of Nuclear Energy;2024-06
2. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024
3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024
4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024
5. Improvement of the critical heat flux correlation in a thermal-hydraulic system code for a downward-flow narrow rectangular channel;Nuclear Engineering and Technology;2022-10