Expert Group on Reactor Stability and LWR Transient Benchmarks
The Expert Group deals with modelling issues in the field of 3-D coupled neutronics / thermal-hydraulics transients for nuclear cores and coupling of core phenomena and system dynamics (PWR, BWR, VVER).
The transients considered include:
Rod Ejection (PWR);
Uncontrolled Withdrawal of Control Rods (PWR);
Main Steam-line Breaks (PWR);
BWR Stability, time series and frequency analysis;
Cold water injection and core pressurisation (BWR);
Turbine Trips (BWR) benchmark;
VVER-1000 Coolant Transient Benchmark (V1000-CT);
BWR Full-size Fine-mesh Bundle Test (BFBT).
Uncertainty Analysis in Modelling (UAM) - Coupled Multi-physics and Multi-scale LWR analysis
Critical Issues in Nuclear Reactor Technology (CRISSUE-S)
The objectives of the NSC in the field of coupled neutronics/thermal-hydraulics computing are to advance scientific knowledge needed for the development of advanced modelling techniques for new nuclear technologies and concepts, as well as for current nuclear applications. This includes:
driving of recent development of coupled 3-D neutronics / T-H codes;
validation and benchmarking of their performance through comparison with experiments;
verifying the correctness of methods and computer codes, building confidence in areas where research is very expensive or lacking;
determination of model uncertainties;
promotion of their use in production runs and safety analysis.
Reactor Stability, Transient, Coupled Neutronics/Thermal-hydraulics, Coupeld Core/Plant 3D Benchmarks