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 radiatio...

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 neu...

The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...

The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...

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 (...

For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.

Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...

The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...

An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.

The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.