The CDLM assists member states in holistically addressing challenges in the execution of decommissioning and legacy management through sharing experiences among members with a broad range of expertis...

Nuclear emergency planning, response and recovery

Two new reports from the WGFS highlight the latest developments in RIA research.

The NEA Working Group on Safety Culture (WGSC) gathered delegates for its biannual meeting on 18-20 October 2022.

MeshTal Viewer user manual

The new task force will explore radiological protection and publich health challenges of SMRs.

Around 90 radiological protection professionals and researchers, representing regulators, research institutions and government entities from NEA member countries and beyond, joined Preparedness for P...

JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...

The 2021 edition can be downloaded online.

The Information System on Occupational Exposure (ISOE) is jointly sponsored by the Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA). Since 1992, ISOE has provided a forum...

A delegation led by NEA Director-General William D. Magwood, IV attended the conference on 26-28 October 2022.

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

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...

The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues. 

The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

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...