The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

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

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 ...

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...