The Working Group on Fuel Cycle Safety (WGFCS) of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) will hold an international workshop on Process and Safety Imp...

The NEST Secretariat monitors the progress of the different NEST Projects, supports the Management Board in the Monitoring and Evaluation process and provides the interface between the NEST Projects ...

The webinar served as a kick-off meeting for the NEST fellows and the organisations participating in the NEST Building competence, Expert knowledge, Applied techniques, Safe decommissioning, Train fe...

Nuclear Education, Science, Technology (NEST) Building competence, Expert knowledge, Applied techniques, Safe decommissioning, Train fellows (BEAST) summer school "Expert Knowledge – Research and Dev...

The proposed NEST project BEAST addresses postgraduate students, postdoctoral researchers and young professionals, who intend to work in the field of Nuclear Decommissioning and Waste Management. The...

The NEA Global Forum on Nuclear Education, Science, Technology and Policy Workshop was held on 19-20 July 2022 at Mita Kaigisho Conference Centre in Tokyo, Japan.

Organised in co-operation with Japan...

The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law.

Building on the success of the previous events held in August 2020 and June 2021, the NEA hosted a Global Commencement ceremony on 29 June 2022 to congratulate the graduating nuclear engineering and ...

The objective of the Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding of relevant aspects of nuclear fuel cycle safety, including: uranium mining and milling; uranium refini...

The main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...

Chemical hazards are an important subject for Fuel Cycle facilities, including various chemical processes and substances such as explosions and healthy risks. On 17-18 April 2018, the Nuclear Energy ...

The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.

An NEA delegation led by Director-General William D. Magwood, IV, visited Japan from 18-24 July for a number of nuclear-energy focused meetings and events.

The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...

The overall objective of the THAI-2 project is to address open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during design-basis or s...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

The workshop objectives relative to reviewing and discussing the state-of-the-art knowledge of iodine and ruthenium behaviour in NPP accidents gained through research projects and progress made in th...

Single-phase computational fluid dynamics (CFD) is used more and more for design and safety issues related to light-water reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...

Criticality safety is an integral component of ensuring the continued safe operation of current reactor and fuel cycle facilities, as well as addressing new and interesting challenges that are expect...

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...

Related data at NEA Data Bank: https://www.oecd-nea.org/tools/abstract/detail/nea-1454/

The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...

The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the biennial series, supported by the Nuclear Energy Agency Worki...

This report by the Working Group on Analysis and Management of Accidents (WGAMA) summarises the first Nuclear Energy Agency (NEA) project to address the topic of severe accident management guidance (...

This workshop aimed to facilitate a broad discussion of the challenges around the competency of regulators in the areas of radioactive waste management, decommissioning and legacy management. In Janu...

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

The workshop was held in Aomori City, Japan on 15-17 November 2016.

On 11 March 2011, the Tohoku-Taiheiyou-Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake ...

For most nuclear design and in-service inspection codes, fracture mechanics is used to evaluate the integrity of cracked components. The major parameters used in this kind of analysis are K and J whi...

The workshop was held in Lucca, Italy on 13-15 April 2016.

The PKL3 Project tests consisted of a programme of experiments intended to, inter alia, understand complex heat transfer mechanisms in the s...

The NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Project is one of the NEA supported joint projects under the auspices and with the support of the NEA. It started from Apr...

This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...

For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...

This training course focuses on communicating risk on a daily basis. Its aim is to improve the effectiveness of risk communication in order to enhance public understanding.

Over three days participan...

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...

NEA hosted two workshops in Romania on 25-29 July 2022.

The NEA Nuclear Law Committee and the Contracting Parties to the Paris Convention held their meetings to discuss key issues and future work in the field of nuclear law.

Management of spent fuel (SF) and high-level waste (HLW) is fundamental to the fuel cycle safety. The original management strategies were established on the basis of limited interim storage periods o...

International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain.

In this work, a complete algorithm for monitoring fatigue was developed for nuclear...

This is a summary report from the International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain. Over 90 specialists from 21 countries attended th...

The Metallic Component Margins under High Seismic Loads (MECOS) Project is an international programme organised under an initiative of the NEA. The main objective of the MECOS Project is to quantify ...

Increasingly engineers are confronted with the need to perform predictive structural assessment based on limited or incomplete data set. This may include damage up to failure assessment (in the conte...

The objective of the CSNI ASCET activity is to make general recommendations for ageing management of concrete nuclear facilities taking into account the effect of concrete pathologies on structural d...

This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...

The Source Term Evaluation and Mitigation Project (STEM) project, hosted by the Nuclear Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of...

It has long been recognised that external hazards can present a potential common cause source of initiating events that could challenge nuclear power plant safety. Modelling of these hazards is a com...

^{Figure 1: Generation IV International Forum [gen-4.org]}

The Nuclear Energy Agency (NEA) and Natural Resources Canada (NRCan) are organising an international workshop on the implementation of radioact...

An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.

This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...

Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark

NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark

A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...

The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted in 2023 by the Italian National Agency for New Technologies, Energy ...

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...

Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...

The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...

Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022

Image: John Schnobrich, Unsplash

Information note on nuclear power installations in Ukraine, updated periodically

The NEST HYMERES project addresses safety-relevant phenomena in containments during accidents. It offers hands-on training opportunities during the experimental test campaigns carried at the PSI PAND...

NEA Task Group on Improving the Gender Balance in the Nuclear Sector met to make progress on a forthcoming report on gender balance in the nuclear sector.

Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.

The NEA Data Bank's first in-person course since the pandemic started was on FISPACT, an enhanced multi-physics platform for neutron, proton, alpha, deuteron or gamma particle interactions.

The Multinational Design Evaluation Programme (MDEP) continues under a new organisational structure after the second Management Board meeting.

MDEP VVER Working Group (VVERWG) meeting, 25-26 May 2021.

The Multinational Design Evaluation Programme (MDEP) entered a new phase on 14 December 2021. The MDEP will continue in its role as a unique multinational initiative leveraging the resources and know...

The Multinational Design Evaluation Program (MDEP) Policy Group held its annual meeting on 22 October 2020 to discuss the status of ongoing MDEP work, plans for future restructuring and interest in c...

The Multinational Design Evaluation Programme (MDEP) begins operation under a new framework agreement.

Source: Pixabay

The new project assembled global experts at the NEA.

The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report 

^{Picture: ANSTO}

The Nuclear Energy Agency (NEA) Working Party on Technical, Environmental and Safety Aspects of Decommissioning and Legacy Management (WPTES) is organising an international workshop on...

Nuclear energy is an important source of low-carbon electricity and plays a significant role in avoiding carbon emissions. It has the potential to contribute further to the decarbonisation of the wor...

Applications for the fourth session of the International Radiological Protection School (IRPS) are now closed.

Although feedback was generally positive after holding the IRPS entirely online in 2021 ...

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...

PWR MOX/UO2 Core Transient Benchmark

The main mission of the Working Group on Fuel Safety (WGFS) is to advance the current understanding and address cross-cutting issues related to fuel behaviour in accident conditions, including work o...

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 ...

TVA Watts Bar Unit 1 Multi-Physics Benchmark

The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...

Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark

Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...

To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...

This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...

The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...

The Nuclear Energy Agency (NEA) and the Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF) are organising an international workshop on the characterisation of large quanti...

Vogtle 3, 4 nuclear power plant, Georgia, Photo: Georgia Power

Nuclear Innovation. Photo: Shutterstock, PopTika.

A stack of trays of TEX plutonium plates. Photo: Lawrence Livermore National Laboratory

The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information o...

The Nuclear Law Bulletin is a unique international publication for both professionals and academics in the field of nuclear law. It provides readers with authoritative and comprehensive information o...

Reducing industrial carbon emissions is one of the most difficult challenges on the path to net zero by 2050, due to the magnitude of greenhouse gas emissions from the industrial sector and technolog...

This workshop is organised by the NEA Radioactive Waste Management Committee (RWMC) and hosted by the Nuclear and Radioactive Waste Agency (ANDR), Romania.

At the back end of the nuclear fuel cycle, ...

Following the accident at the Fukushima Daiichi Nuclear Power Plant, many countries began funding research and development on nuclear fuel designs with enhanced accident tolerance (ATFs). ATFs have i...

National legislation: Republic of Türkiye

Photo by Headway on Unsplash

Radioactive waste is produced in all phases of the nuclear fuel cycle and from the use of radioactive materials in industrial, medical, defence and research applications. Disposal in engineered repos...

Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority

 The FACE proje...

The goal of EGCUL is to share state-of-the-art knowledge and experience in characterising a large amount of unknown waste derived from nuclear accidents and past nuclear activities.

Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...

Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority

NEA Committee Structure, July 2022

Structure des comités et organes subsidiaires de l’Agence pour l’énergie nucléaire, juillet 2022.

The Programme Review Group is established to perform a programme quality review function within the Committee on the Safety of Nuclear Installations (CSNI) and to provide scientific assistance to the...

The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...

The EGFSF will work on harmonising post-accident food safety management approaches to build and maintain producer and retailer’s accountability and consumer trust.

NEA Director-General speaks at NE•RS 2022 conference, meets with Deputy Minister of Industry and Trade.

The objective of the OECD LWR UAM activity is to establish an internationally accepted benchmark framework to compare, assess and further develop different uncertainty analysis methods associated wit...

The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

Always credit: Nuscale

Participants at the first in-person course held by the NEA Data Bank since the pandemic started,  21- 23 June 2022. 

How can knowledge of high-level radioactive waste existence, nature and history be passed on to future generations? The NEA Expert Group on Awareness Preservation (EGAP) has been focusing on this que...

The OECD Nuclear Energy Agency (NEA), Idaho National Laboratory, and International Atomic Energy Agency (IAEA) are co-organising the Sixth International Workshop on Structural Materials for Innovativ...

The mission of the CRPPH Working Party on Nuclear Emergency Matters (WPNEM) is to improve nuclear emergency management systems within member countries, and to share its knowledge and experience widel...

In 2019, the NEA Committee on Radiological Protection and Public Health's(CRPPH) Working Party on Nuclear Emergency Matters (WPNEM) created the Expert Group on Non‑radiological Public Health Aspects ...

Addressing the mental health impacts of radiological and nuclear emergencies

NEA Expert Group on Non‑radiological Public Health Aspects of Radiation Emergency Planning and Response (EGNR) kick‑off meeting on 5 November 2019.

In the aftermath of the Chernobyl and Fukushima Daiichi nuclear accidents, the notion of sustainable recovery from nuclear or radiological accidents has been at the centre of attention for the intern...

The NEA Expert Group on Recovery Management (EGRM) held a meeting on 6 May 2021.

The NEA Expert Group on Non-radiological Public Health Aspects of Radiation Emergency Planning and Response (EGNR) provided input to the development of the recently launched World Health Organization...

The NEA Expert Group on Non‑Radiological Public Health Aspects of Radiation Emergency Planning and Response (EGNR) is developing an operational approach for mitigating the mental health and psychosoc...

Online services for official delegates to NEA meetings.

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 ...

Source: Idaho National Laboratory, always cite and link to:

https://www.flickr.com/photos/inl/32176790930/in/album-72157622641333808/

Source: Foro Nuclear, always cite and link to the original at:

https://www.flickr.com/photos/foronuclear/9300792402/in/gallery-138473945@N07-72157661769933199/

The brochure provides background information about the NEA.

The NEA Framework for Irradiation Experiments (FIDES) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions and indust...

État d’avancement des ratifications ou des adhésions à la Convention de Paris sur la responsabilité civile nucléaire.

This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

Photo by Lukáš Lehotský on Unsplash

Photo by Ümit Yıldırım on Unsplash

Nuclear emergency preparedness and response management are essential components to ensure safety and radiation protection in any nuclear or non-nuclear country. While international guidelines for eme...

The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...

7 October 2021, 14:00-16:30 CEST

Reducing industrial carbon emissions is one of the most difficult challenges on the path to net zero by 2050, due to the magnitude of greenhouse gas emissions from th...

To learn how to handle NaK, a group of experts at the Research Centre Rez (CVR) in the Czech Republic travelled to Cadarache in France to learn from experts at the Commissariat for Atomic Energy and ...

Recent meetings of groups working under the aegis of the Framework for Irradiation Experiments (FIDES) have demonstrated that the international community is enthusiastic and on a strong course to ful...

DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

Nadiia Vynar / unsplash

Table on Application of the Paris Convention to non-metropolitan territories of the Contracting Parties (English version)

Table on Application of the Paris Convention to non-metropolitan territories of the Contracting Parties (French version)

P2M includes in-pile tests and Post-Irradiated Examinations in Hot-Laboratory to assess the operational margins at high power.

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

The INCA experiments will provide comparative data on the irradiation induced creep of current Zr alloys and Cr coated samples

High Burnup Experiments in Reactivity Initiated Accident (HERA) is dedicated to the understanding of LWR fuel performance at high burn-up under reactivity-initiated accidents (RIA).

The goal of the LOCA-MIR experiments is to study the behaviour of high burnup, gadolinia-doped fuel under design-basis LOCA conditions.