Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...

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...

International Fuel Performance Experiments (IFPE) is the public domain database on nuclear fuel performance experiments for the purpose of code development and validation.

Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...

The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.