MCS – A Monte Carlo particle transport code for large-scale power reactor analysis
Hyunsuk Lee, Wonkyeong Kim, Peng Zhang, Matthieu Lemaire, Azamat Khassenov, Jiankai Yu, Yunki Jo, Jinsu Park, Deokjung Lee
Topics & Concepts
Monte Carlo methodNuclear engineeringComputer scienceBurnupSupercomputerNeutron transportPressurized water reactorComputational scienceSimulationNeutronParallel computingPhysicsNuclear physicsEngineeringMathematicsStatisticsNuclear reactor physics and engineeringNuclear Physics and ApplicationsNuclear Materials and Properties