19 papers found
Refreshing results…
Optimal time step length and statistics in Monte Carlo burnup simulations
Stochastic-deterministic response matrix method for reactor transients
Optimal neutron population growth in accelerated Monte Carlo criticality calculations
Stabilization effect of fission source in coupled Monte Carlo simulations
Monte Carlo criticality calculations accelerated by a growing neutron population
Performance of the Explicit Euler and Predictor-Corrector–Based Coupling Schemes in Monte Carlo Burnup Calculations of Fast Reactors
Neutron batch size optimisation methodology for Monte Carlo criticality calculations
Estimation of errors in the cumulative Monte Carlo fission source
Time step length versus efficiency of Monte Carlo burnup calculations
Development and comparison of spectral methods for passive acoustic anomaly detection in nuclear power plants
Description of a stable scheme for steady-state coupled Monte Carlo–thermal–hydraulic calculations
Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal–hydraulic feedback
The stochastic implicit Euler method – A stable coupling scheme for Monte Carlo burnup calculations
Numerical stability of the predictor–corrector method in Monte Carlo burnup calculations of critical reactors
Building the nodal nuclear data dependences in a many-dimensional state-variable space
Stability and convergence problems of the Monte Carlo fission matrix acceleration methods
Fission matrix based Monte Carlo criticality calculations
Pracovní migrace cizinců v ČR
From once-through nuclear fuel cycle to accelerator-driven transmutation
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