Verification of depletion capability of OpenMC using VERA depletion benchmark
Jiankai Yu, Benoit Forget
Topics & Concepts
Computer scienceSolverNuclidePython (programming language)Computational scienceParallel computingBenchmark (surveying)Monte Carlo methodAlgorithmPhysicsOperating systemMathematicsProgramming languageNuclear physicsGeographyStatisticsGeodesyNuclear reactor physics and engineeringNuclear Physics and ApplicationsGraphite, nuclear technology, radiation studies