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Uncertainty analysis of neutronic/thermal-hydraulic coupling in pressurized water reactor fuel assemblies

Deyan Kong, Zhibo Gao, Di Wu, Jie Cheng, Jianjun Wang

2024Annals of Nuclear Energy10 citationsDOI

Topics & Concepts

Thermal hydraulicsNuclear engineeringEnvironmental scienceCoupling (piping)Pressurized water reactorMaterials scienceMechanicsHeat transferPhysicsEngineeringMetallurgyNuclear reactor physics and engineeringNuclear Engineering Thermal-HydraulicsNuclear Materials and Properties
Uncertainty analysis of neutronic/thermal-hydraulic coupling in pressurized water reactor fuel assemblies | Litcius