Depletion capabilities in the OpenMC Monte Carlo particle transport code
Paul Romano, Colin Josey, Andrew Johnson, Jingang Liang
Topics & Concepts
Monte Carlo methodCode (set theory)Statistical physicsDynamic Monte Carlo methodComputer scienceNeutron transportNuclear engineeringPhysicsNuclear physicsMathematicsStatisticsNeutronProgramming languageEngineeringSet (abstract data type)Nuclear reactor physics and engineeringNuclear Physics and ApplicationsGraphite, nuclear technology, radiation studies