3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...
The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...
This Phase II exercise was the first benchmarking of severe accident codes promoted by NEA in almost 20 years. The objective of the exercise was to perform a code benchmark on a well-defined plant (s...
Based on the conclusions of the previous benchmark exercise, the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by examinin...
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.
Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...
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 unce...