Nuclear Science and Engineering · 1977 · 16 citations · 0 references
EngineeringNuclear EngineeringChemical KineticsNuclear PhysicsReactor PhysicsHeat Transfer In ReactorsReactor DesignReactor DynamicsReactor KineticsReactor ModelingThermal Reactor PhysicsFinite Difference SchemesFinite Difference SimulationQuasi-static ApproximationsReactor Kinetics AnalysisReactor OperationReactor Transient AnalysisTransient Reactor ModelingTransient Reactor Response
A description of reactor kinetics benchmark activity in support of the Canadian naturaluranium heavy water (CANDU) reactor program is presented. Two benchmark problems with neutronic characteristics resembling current generation CANDU reactors have been defined, and accurate solutions to both problems are summarized. In addition, the performance of an improved quasi-static code has been tested and compared with a finite difference method. A brief description of the reactor kinetics experimental program related to reactor transient studies is also given.