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Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe

Xiang Chai, Chaoran Guan, Jiaolong Deng, Tengfei Zhang, Xiaojing Liu

2022Annals of Nuclear Energy16 citationsDOI

Topics & Concepts

Nuclear engineeringDecay heatShutdownNuclear reactor coreSodium-cooled fast reactorCore (optical fiber)Conceptual designNuclear powerParametric statisticsControl rodEnvironmental scienceNeutron moderatorPower (physics)Computer scienceNuclear reactorMonte Carlo methodNeutronNeutron temperatureMechanical engineeringNuclear physicsNeutron cross sectionPhysicsEngineeringMathematicsStatisticsHuman–computer interactionTelecommunicationsQuantum mechanicsNuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe | Litcius