The Working Group supports improved uses of Probabilistic Safety Assessment (PSA) in risk-informed regulation and safety management through the analysis of results and the development of perspectives...

The objective of this study is to compare leak rate computation practices and the applied tools and software solutions. Leak rate prediction is an important aspect of the leak-beforebreak assessment,...

The NEA Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Nuclear Regulatory Activities (CNRA) convened on 4-8 December to discuss current activities and plan future body o...

This synthesis report summarises the technical programme and the outcome of the 2018 International Severe Accident Management Conference (ISAMC-2018) organised in Ottawa, Ontario on 15-18 October 201...

As noted in the Joint CSNI/CNRA Strategic Plan and Mandates (NEA, 2019), the safe operation of current, new and advanced nuclear facilities is a key challenge for nuclear regulators and technical saf...

The Fire Incidents Records Exchange (FIRE) Project started in 2002 and phase 7 of the project began in 2023 for a duration of three years, with 14 countries currently participating. The main purpose ...

RASPLAV-A-Salt Facility, EREC.

The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up t...

                                                                                  EPICUR facility, IRSN.

STEM phases

First phase (2011-2015)

The STEM Project was initiated with a first phase in 20...

While there is a growing interest in the deployment of small modular reactors (SMRs) as a promising option to help mitigate climate change, further international efforts are needed to accelerate the ...

The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...

The Nuclear Energy Agency (NEA) Working Group on the Analysis and Management of Accidents (WGAMA) aims to contribute to the assessment of the prevention, mitigation and management of accidents, ultim...

The eighth instalment of the workshop on computational fluid dynamics for nuclear reactor safety (CFD4NRS-8) was organised by the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Instal...

Around 50 delegates from 22 countries and 2 international organisations gathered on 6-7 June 2023 for the 73rd CSNI meeting.

In the current project, a new systematic approach has been developed, called SAPIUM (systematic approach for input uncertainty quantification methodology) for transparent and rigorous model IUQ. This...

Recent operating experience in nuclear power plants has shown that there is a safety concern associated with the use of new industrial devices, including digital devices, in safety power systems in b...

The present report summarises the main results and learnings from the third phase of the NEA Behaviour of Iodine Project (BIP-3), which was conducted between 2016 and 2019 by the Canadian Nuclear Lab...

In order to reach a better understanding of countries’ different approaches to the evaluation of vibrations detected in piping systems and components, the NEA Committee on the Safety of Nuclear Insta...

The aim of this report is to examine whether there are any international variations in the electrical power system designs (“design variations”) of nuclear power plants that affect the system respons...

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

Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4^th October, 2011). Photo: Tokyo Electric Power Company Holdings

The Benchmark Study of the Acci...

In the ASCET Phase III, the goal was to assess and develop the Phase II (blind benchmark) recommendations using additional test results. The Phase III simulations were performed using a full set of t...

Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...

Nuclear Fuel Cycle Facilities Safety Week

The NEA Working Group on Digital Instrumentation and Controls (WGDIC) has agreed that a consensus position on the impact of cyber security features on digital instrumentation and control (I&C) system...

This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-cause Failure Data Exchange (ICDE) Project. The topic was multi-unit CCF events.

T...

This report presents a study performed on a set of common-cause failure (CCF) events within the Nuclear Energy Agency (NEA) International Common-cause Failure Data Exchange (ICDE) Project. The topic ...

The cold leg mixing computational fluid dynamics (CFD) – uncertainty quantification (CLM-UQ) benchmark is the fifth benchmark concerning CFD applications to nuclear reactor safety to be organised in ...

Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...

Since its inception in 2002, the operating experience with thermal fatigue mechanisms has been an intrinsic aspect of the technical scope of CODAP, which is a joint database project within the Commit...

This report summarises the work done for the activity: “Benchmark analysis on the eXtended Finite Element Method (X-FEM) calculation technology in its use to evaluate the fracture mechanics stress in...

The Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), co-organised by the S...

Prevention, mitigation and management of potential accidents in nuclear power plants

This report provides insights from a survey of Nuclear Energy Agency (NEA) member countries on the concepts used to establish effective measures to cope with external flooding hazards and on the term...

The VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...

This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-Cause Failure Data Exchange (ICDE) project. The topic of the study was intersystem...

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...

CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.

The Symposium is free of charge for all participants and is scheduled to take place in person at the ONR’s offices near Liverpool in the United Kingdom. 

Key Dates

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

The investigation conducted in the last 15 years on different aspects of Source Term worldwide, and particularly in the context of the Nuclear Energy Agency (NEA) in the form of projects and the Work...

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 significan...

Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...

After the Fukushima nuclear accident, many activities were initiated in the countries with nuclear energy to assess the robustness of nuclear power plants with respect to earthquakes, tsunamis and fl...

Within the context of the Nuclear Energy Agency (NEA) Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) project, a series of tests were performed to resolve key thermal-hydraulic s...

When looking for a validation experiment for CFD application to reactor simulation for either design or safety studies, it appears that available data often suffer from a lack of local measurements, ...