Applied Radiation and Isotopes · 2004 · 12 citations · 2 references
EngineeringNuclear EngineeringPhysicsNuclear PhysicsRadiation TransportReactor PhysicsMonte Carlo DosimetryMonte Carlo Radiation TransportMonte Carlo SimulationMonte Carlo Transport MethodsNeutron TransportReactor KineticsMonte Carlo Neutron TransportMonte Carlo Stopping Power CalculationsNeutron Flux CalculationNeutronics AnalysisReactor Core NeutronicsReactor NeutronicsReactor Operation
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MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations