Deadline for submission of abstracts       31 July 2023  (extended) 

Notification of accepted contributions      17 August 2023

Deadline for attendance registration          27 Oct 2023      

Deadline for presentation submiss...

The workshop on the Approaches to design, implementation and operation of electrical systems for beyond design basis equipment and management of geomagnetically induced currents in electrical systems...

Experts attended NEA event in France.

The NEA Working Group on the Analysis and Management of Accidents convened for its annual meeting to discuss ongoing work related to accident strategy and management.

One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, prim...

In response to the technical and scientific needs emerged recently in this area, the Working Group of External Events (WGEV) and the Working Group on Risk Assessment (WGRISK) initiated a joint task e...

The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.

NEA Working Group on Analysis and Management of Accidents (WGAMA) initiated this activity focusing on computational fluid dynamics (CFD) in nuclear reactor safety (NRS).

Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA

TCOFF Phases

First Phase (2017-2020)

The Thermodynamic Characterisation of Fuel Debris and Fission Products ...

Scheme of the ROSA LSTF facility, JAEA

The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...

Irradiation Vessel with Coupons, CNL

The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment bui...

PANDA vessel assembly (construction phase, 1993), PSI.

The PANDA project is a follow-up of the HYMERES-2 project, and its general objective is to advance the knowledge on the containment of thermal...

Scheme of the DIVA Facility, IRSN

The Fire Risk Assessment through Innovative Research Project is a follow-up of the PRISME project series which addresses new fire scenarios and new topics of inter...

The objective of the NEA THAI-3 project was to address open questions concerning the behaviour of hydrogen, iodine and aerosols under severe accident conditions in the containment of water cooled rea...

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...

Supporting the use of computational fluid dynamics for nuclear reactor safety

Innovations in nuclear safety thermal-hydraulics

10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.

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

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

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

Image: QUENCH facility at KIT. Court. KIT. 

The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...

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...

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...

Approximately 30 experts from WGAMA discussed how to advance the understanding of phenomena in pool in the situation of a loss of cooling accident.

Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

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...

With the growing importance of SMRs, following the proposal of the CSNI Bureau, the CSNI has decided to create an Expert Group on SMRs (EGSMR), at its 69th meeting held on 2-3 June 2021.

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...

The 9^th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023. 

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...

Since its inception, the NEA has provided a highly flexible and powerful platform for multinational research co-operation, particularly in areas related to providing understanding and insights needed...

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...

Second Workshop on International Harvesting Co-operation focused on the status of aged metals harvesting and opportunities for international collaborative research.

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...

PKL facility. Photo: FRAMATOME, Germany

The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...

Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.

The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...

Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik

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...

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...

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...

^{View of the ATLAS experimental loop. KAERI, Korea}

The Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...

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...