Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on System Reactor Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-scale modelling and simulation (M&S). Coupled behaviours of two or more of the following physics will include, but are not limited to the following:
Multi-physics aspects of both steady-state and transients conditions of existing and advanced nuclear systems are examined along with uncertainty quantification and propagation through different scale (multi-scale M&S) and different physics phenomena (multi-physics M&S).
The expert group provides recommendations to the and the nuclear community on the scientific development needs (data and methods, validation experiments, scenario studies) for multi-physics and multi-scale M&S, including sensitivity and uncertainty methodology for analysis of different reactor systems and scenarios. Guidance and processes to certify experimental data for multi-physics multi-scale M&S and to apply this data to the benchmarking of models will be developed.
To fulfil the above the expert group will provide the following:
To support its activities, the group will collect and evaluate multi-physics data from available integral facilities and Nuclear Power Plant (NPP) experimental data. Analytical and numerical benchmarking will also be used to fulfil the objectives.
|Chair||Timothy E. VALENTINE (USA)|
|Vice-Chair||Evgeny IVANOV (FR)|
All NEA member countries EGMUP members' working area
|Full participant||European Commission (under the NEA Statute)|
Observer (international organisation)
|International Atomic Energy Agency (by agreement)|
WPRS and associated Expert Group meetings are held approximately every twelve months.
Next meeting: 19th Meeting of WPRS, 21st - 25th of Febuary 2022.
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs. The annual workshops are attended by many experts in industry, research institutes, national laboratories, academia, and government agencies.
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) was to determine the uncertainty in light water reactor (LWR) systems and processes in all stages of calculations. It was estimated through a simulation process of nine exercises in three phases provided by the benchmarking framework.
This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-1000 reactors based on actual plant data from the Russian nuclear power plant Kalinin Unit 3 (Kalinin-3)
A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a VVER-1000 with fuel assemblies of type TBC-2M, which enable an 18-month fuel cycle length.
The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data.