2018•Progress in Nuclear EnergyRequires access

Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors

Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Jing Chen, Xinan Wang, Xiuli Xue, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G.H. Su

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Key concepts: Nuclear engineering, Sodium-cooled fast reactor, Transient (computer programming), Thermal hydraulics, Reactor pressure vessel, Materials science, Breeder reactor, Natural circulation

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Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors — Research Paper | ScholarLens