Neutronics analysis for MSR cell with different fuel salt channel geometries
Shihe Yu, Yafen Liu, Pu Yang, Rui-Min Ji, Guifeng Zhu, Bo Zhou, Xuzhong Kang, Rui Yan, Yang Zou, Ye Dai
Topics & Concepts
Neutron transportChord (peer-to-peer)Nuclear engineeringMonte Carlo methodMolten saltGraphiteAtomic packing factorMaterials scienceEllipseNeutronPhysicsNuclear physicsGeometryMathematicsThermodynamicsComputer scienceEngineeringNuclear magnetic resonanceStatisticsComposite materialDistributed computingNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies