This report from the NEA Working Group on Human and Organisational Performance establishes a common understanding around the terms human performance (HP), organisational performance (OP), and human and organisational factors (HOF) through a simple...

One of the key areas in fuel safety is the analysis of fuel behaviour under reactivity-initiated accident conditions. Reactivity-initiated accident fuel rod codes have been developed for a significant period of time and they all have shown their...

Understanding the accident at the Fukushima Daiichi Nuclear Power Plant is important for safe and timely decommissioning of the reactors. This objective, together with the development of better computer codes for analysis of severe accidents, was the...

Experimental facilities in nuclear energy are key to addressing safety issues. The recent loss of some critical infrastructure, from facilities to industry expertise, has therefore become a concern for many countries. In response, the NEA has...

As the Fukushima Daiichi nuclear power plant (NPP) accident illustrates, many challenges have to be faced in maintaining safety over the long term in a damaged NPP following a severe accident. These comprise maintaining and monitoring a stabilised...

Following the 2011 accident at the Fukushima Daiichi nuclear power plant, several high-priority actions were initiated by the NEA to address certain technical issues at nuclear power plants.

Activities carried out over the last three decades in relation to core-concrete interactions and melt coolability, as well as related containment failure modes, have significantly increased the level of understanding in this area.

This reports re-examines nuclear fuel safety criteria, last reviewed in 2001.

This report describes the achievements of the OECD/NEA joint projects on nuclear safety research that have been carried out over the past three decades, with a particular focus on thermal-hydraulics, fuel behaviour and severe accidents.

This third edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle.

This conference proceedings examines the most recent research and developments related to the impact of debris on emergency coolant recirculation.

These proceedings bring together the papers presented at the OECD/NEA Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs.