Published date:
4 February 2025
Published date:
4 February 2025
Published date:
4 February 2025
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...
Published date:
4 February 2025
Photo of CEA VITI facility
The COrium Properties for reactor Simulation and uncertainties (COPS) project began in April 2024 its five-year programme to investigate the thermo-physical properties of c...
Published date:
4 February 2025
Picture of the ASNR MIDI facility
The Pool during Loss of Cooling Accident (POLCA) project was launched in April 2024 and is planned to last four years. It is operated by the French Autorité de Sûre...
Published date:
4 February 2025
25 February 2025
Hybrid meeting - Zoom
Women are under-represented in the nuclear energy sector, especially in leadership roles. The future of the nuclear industry requires a robust and diverse workforce to not only drive performance and ...
Published date:
4 February 2025
Multi-compartment THAI+ test facility, Becker Technologies GmbH.
In the wake of the NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigation m...
Published date:
4 February 2025
PKL facility. Photo: FRAMATOME, Germany
The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...
Published date:
4 February 2025
Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat...
Published date:
4 February 2025
Photo: RBHT Test Facility. US NRC.
Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...
Published date:
4 February 2025
CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: ASNR
Following several years of experimental research in the field of source terms analysis...
Published date:
4 February 2025
Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...
Published date:
4 February 2025
The Nuclear Fuel Cycle Simulation System (NFCSS) is a scenario based computer simulation tool, implemented in a web based platform, for studying various options of nuclear fuel cycle for nuclear powe...
Published date:
4 February 2025
The FAMILY-21 code is a stand-alone simulation code developed to quantitatively indicate reactor systems and nuclear fuel cycle systems adaptable to future uncertain nuclear needs.
Published date:
4 February 2025
DYMOND simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle including mining, enrichment, fueling, reactors, reprocessing, waste management, disposal, etc.
Published date:
4 February 2025
COSI is a calculation code that simulates nuclear reactor fleets and the associated fuel cycle facilities over several decades. This tool is developed by the SPRC (Reactor Physics and fuel Cycle Serv...
Published date:
4 February 2025
COSAC is used to study the flow and the storage of nuclear materials in a nuclear fleet composed of the following installations:
- mines
- fresh fuel manufacturing plants.
- reactors
- cooling pools
- spent f...
Published date:
4 February 2025
Since 2012, CLASS is developed CNRS/IN2P3 (Centre National de la Recherche Scientifique / Institut National de Physique Nucléaire et de Physique des Particules) with initial support from IRSN (Instit...
Published date:
4 February 2025
The VISION Nuclear Fuel Cycle Simulation Model is a system dynamics model that captures all aspects of the nuclear fuel cycle, from mining of ore to the ultimate disposal of spent fuel and high-level...
Published date:
4 February 2025
31 March 2025 -
3 April 2025
Madrid, Spain
The OECD Nuclear Energy Agency (NEA) and CIEMAT are co-organising the Seventh International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-7). The workshop will be held in Mad...
Published date:
9 January 2025
At the heart of the NEST Framework are multinational and multidisciplinary projects, so-called NEST Projects.
Published date:
3 February 2025
The main decision body of the NEST Framework is the Management Board which includes one member and one alternate from each NEST Country.
Published date:
3 February 2025
The main mission of the Working Group on Human and Organisational Factors (WGHOF) is to improve the understanding and treatment of human and organisational factors within the nuclear industry in orde...
Published date:
3 February 2025
The WGLSC is responsible for supporting and advising the Committee on Nuclear Regulatory Activities (CNRA) in carrying out its programme of work in areas related to leadership and safety culture.
Published date:
3 February 2025
Cabri Reactor (Commissariat à l’énergie atomique et aux énergies alternatives)
The Cabri International Project (CIP) began in March 2000 to study the behaviour of nuclear fuel rods and cladding durin...
Published date:
3 February 2025
Published date:
3 February 2025
Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik
Published date:
3 February 2025
End state of debris in the units 1-3 of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings. Photo: Japan Atomic Energy Agency
The Preparatory Study on Analysis of Fuel D...
Published date:
3 February 2025
A cabinet containing copper bus before the HEAF test (left) and after the test(right). Source: NRC
Massive electrical discharges, referred to as high energy arcing faults (HEAF), have occurred in nuc...
Published date:
3 February 2025
Halden Hammlab research facility for human factor research.
The NEA Halden HTO Project is a continuation of Man-Technology-Organisation (MTO) research carried out for more than 40 years as part of t...
Published date:
3 February 2025
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 projec...
Published date:
3 February 2025
Scheme of the DIVA Facility, ASNR
Fire is a significant contributor to overall core damage frequency for both new and old nuclear reactor designs. Furthermore, it may severely affect plant safety i...
Published date:
3 February 2025
NMB4.0 is designed to provide flexibility and an all-in-one packaged nuclear fuel cycle simulation for users as open code. Various ideas have been implemented to improve user-friendliness. The main t...
Published date:
3 February 2025
TR_EVOL (Transition Evolution code) fuel cycle simulator is a tool dedicated to the study of mass balances of advanced transition electronuclear scenarios.
Published date:
31 January 2025
The Advanced Nuclear Cycle Code, ANICCA, is a nuclear fuel cycle simulation code (NFCSC) that has been developed by SCK-CEN as a flexible tool for nuclear fuel cycle studies. ANICCA is able to simula...
Published date:
31 January 2025
The International Nuclear Law Essentials (INLE) is a one-week programme run by the NEA covering practical issues in international nuclear law.
Published date:
31 January 2025
3 -
7 March 2025
OECD Conference Centre, Paris
3-7 March 2025
The application period is closed.
Due to exceptionally high demand, the course and waitlist are full.
Dates for the 2026 programme will be announced soon.
Programme
The 2025 Interna...
Published date:
31 January 2025
Nuclear legislation: Korea
Published date:
31 January 2025
PKL facility. Photo: FRAMATOME, Germany
The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project was launched in October 2020 to address knowle...
Published date:
31 January 2025
PANDA vessel assembly (construction phase, 1993), PSI.
The PANDA project was launched in July 2021, following the NEA HYMERES project series, to contribute to the extension of the database on large...
Published date:
31 January 2025
Published date:
31 January 2025
Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...
Published date:
26 January 2024
View of the ATLAS experimental loop. KAERI, Korea
The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) is a thermal-hydraulic integral effect test facility for advanced light wate...
Published date:
29 January 2025
The Halden Reactor Project has been in operation at the Institute for Energy Technology (IFE) in Norway since 1958 and is the oldest NEA joint project. It brings together a large international techni...
Published date:
29 January 2025
The Halden Reactor Project has been in operation at the Institute for Energy Technology (IFE) in Norway since 1958 and is the oldest NEA joint project. It brings together a large international techni...
Published date:
26 April 2024
Published date:
29 January 2025
Published date:
29 January 2025
Published date:
29 January 2025
Published date:
29 January 2025