Experts attended NEA event in France.

Scheme showing the technical scope of NEA ICDE project activities, NEA 

Common-cause failure (CCF) events can significantly affect the availability of safety systems of nuclear power plants. In recog...

The joint NEA-IAEA symposium hosted by the United Kingdom’s Office for Nuclear Regulation brought together experts to exchange on the use and application of Probabilistic Safety Analysis (PSA) for re...

Joint NEA and IAEA event will explore probabilistic safety assessment for reactors of singular designs

The Committee on the Safety of Nuclear Installations (CSNI) Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components was held in Lyon, France on 25-27 S...

Seismic probabilistic safety assessment (SPSA) is a systematic method for examining and evaluating the risk from earthquake-initiated accidents. The significant advances in the area of SPSA since the...

Two important lessons learnt from the March 2011 Fukushima Daiichi nuclear power plant (NPP) accident were: 1) there can be significant interactions between multiple co-located radiological sources (...

This report provides descriptions of the current status of PSA programmes in member countries; including basic background information, guidelines, various PSA applications, major results in recent st...

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) (formerly PWG5) established in 1996 a Task Group to review the status and maturity of methods use...

On 28-30 April 2014, the CSNI Working Group on Risk Assessment (WGRISK) held a workshop on Fire Probabilistic Risk Assessment (PRA) in Garching, Germany. The meeting was attended by nearly 60 partici...

The objective of the Digital System Reliability Failure Mode Taxonomy (DIGREL) task group, formed under the OECD/NEA Working Group on Risk Assessment (WGRISK), has been to develop a taxonomy of failu...

The Component Operational Experience, Degradation & Ageing Programme (CODAP) Topical Report on FAC of Carbon Steel and Low Alloy Steel Piping includes a primer on the environmental and operational fa...

The Fukushima Dai-ichi accident triggered discussions about the significance of external hazards and their treatment in safety analyses. In addition, stress tests results have shown vulnerabilities a...

Probabilistic safety assessment/probabilistic risk assessment (PSA/PRA) for new and advanced reactors is recognized as an important approach to achieve improved safety for the future nuclear power pl...

The main objective of the Working Group on Risk Assessment (WGRISK) of the Nuclear Energy Agency (NEA)/Committee on the Safety of Nuclear Installations (CSNI) is to advance the probabilistic safety a...

The maintenance of sufficient expertise, data, analytical and experimental capabilities to be able to develop the technical basis to resolve currently identified safety issues and respond to and inve...

In 2008, the NEA's Working Group on Risk Assessment (WGRISK) issued a report [NEA/CSNI/R(2008)9] addressing the feasibility of a joint international effort on human reliability analysis (HRA) data. T...

Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OPDE) to encourage multilateral co-operation in the collection and analysis of data relating to de...

Following the recommendations of a previous meeting held in Jeju, Korea on 6-8 November 2006, the Committee on the Safety of Nuclear Installations (CSNI) approved a proposal of the Working Group on I...

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...