Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel
Mikołaj Oettingen, Jerzy Cetnar
Abstract
Abstract The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes ( 233 U, 235 U, 239 Pu, 241 Pu) for a few configurations of the initial reactor core.
Topics & Concepts
ThoriumNuclear engineeringEnriched uraniumModular designUraniumNuclear reactor coreComputationFissile materialMonte Carlo methodThorium fuel cycleDelayed neutronNeutron transportNeutronMaterials scienceNuclear physicsPhysicsNeutron temperatureComputer scienceMathematicsEngineeringAlgorithmStatisticsOperating systemNuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies