The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.

High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...

The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...

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.

This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark

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 ...

The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted in 2023 by the Italian National Agency for New Technologies, Energy ...

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...

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 ...

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...

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

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) performs specific tasks associa...

The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...

Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022