Litcius/Paper detail

Development and validation of transient analysis code for heat pipe reactor system

Min Feng, Zeyu Ouyang, Pan Wu, Jianqiang Shan

2025Annals of Nuclear Energy5 citationsDOI

Topics & Concepts

Transient (computer programming)Nuclear engineeringCode (set theory)Computer scienceTransient analysisTransient responseProgramming languageEngineeringElectrical engineeringSet (abstract data type)Nuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsHeat Transfer and Boiling Studies
Development and validation of transient analysis code for heat pipe reactor system | Litcius