Preliminary safety comparison of lead-cooled fast reactors with advanced fuels in unprotected transients
Xin Jin, Zimu Zhang, Yubo Sun, Maolong Liu, Yao Xiao, Hui Guo, Xinbiao Jiang, Lixin Chen, Hanyang Gu
Topics & Concepts
MOX fuelNuclear engineeringScramTransient (computer programming)Benchmark (surveying)Sodium-cooled fast reactorNitrideNeutron transportMaterials scienceEngineeringPlutoniumComputer scienceNeutronNuclear chemistryNuclear physicsChemistryPhysicsComposite materialLayer (electronics)GeographyOperating systemGeodesyNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies