Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) will perform specific tasks associated with neutronics, radiation transport, reactor physics and nuclear fuel feedback along with uncertainty analysis of present and future nuclear power systems. The considered reactor systems that will be studied include but are not limited to:
The objective of the EGPRS is to provide expert advice to the WPRS and the nuclear/accelerator community on the development needs (data and methods, validation experiments, scenario studies) for neutronics and fuel feedback issues of different reactor systems.
The fulfilment of this objective notably entails providing specific technical information on:
This technical information will generally be derived from a combination of direct experimental evidence and/or the results of theoretical benchmark analyses using accurate, validated modelling and simulation (M&S) methods. In either case, the availability of suitable experimental data is a fundamental requirement. The EGPRS will monitor gaps and steer development of the International Radiation Shielding Experiments Database (SINBAD) in collaboration with the United States’ Radiation Safety Information Computational Centre (RSICC).
Hakim Ferroukhi (SUI)
Robert Grove (USA)
All NEA member countries EGPRS working area
|Full participant||European Commission (under the NEA Statute)|
Observer (international organisation)
|International Atomic Energy Agency (by agreement)|
Click on elements in graph above to jump directly to a specific WPRS activity.
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light water reactor (LWR) systems and processes in all stages of calculations. It is estimated through a simulation process of ten exercises in three phases provided by the benchmarking framework.
Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (GIF). Developing tools and methods to support this technology is seen as a priority by NEA member countries.
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neutron kinetics equations without use of the diffusion approximation and spatial homogenisation.
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiation facilities.
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates for a new generation of nuclear energy systems. The LRF physics benchmark is based on the Advanced LFR European Demonstrator (ALFRED) design and consists of a neutronics and thermal hydraulics stage with each three benchmark phases related to pin-cell, sub assembly/super-cell and whole-core simulations.