The NEA Working Group on the Safety of Advanced Reactors (WGSAR) held its biannual meeting via video conference on 21-23 April 2021, welcoming a new member representing Poland’s National Centre for N...

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...

High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...

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 ...

In 1959, thirteen OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the first experimental high temperature gas-cooled ...

Generation IV International Forum (GIF) updates 

In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...

This study analyses the need for adjustments in or new developments of the fuel cycle for Small Modular Reactors.