Published date:
6 October 2023
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...
Published date:
19 October 2022
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...
Published date:
31 August 2023
Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4th October, 2011). Photo: Tokyo Electric Power Company Holdings
The Benchmark Study of the Acci...
Published date:
25 November 2022
General view of the EREC test facility BC V-213, source: EREC
There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine...
Published date:
6 October 2023
In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...
Published date:
17 April 2020
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:
26 April 2023
The International Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking of a limited nu...
Published date:
3 November 2023
Feeders on the Reactor Face in the Feeder Cabinet Photo: Canadian Nuclear Safety Commission (CNSC)
The Component Operational Experience, Degradation and Ageing Programme (CODAP) combines the follow-u...
Published date:
21 October 2022
Control room, PAKS NPP.
Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some ext...
Published date:
7 November 2023
View of Dragon Reactor. Photo: AEA Technology.
In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...
Published date:
14 October 2022
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...
Published date:
9 December 2022
CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: IRSN
Following several years of experimental research in the field of source terms analysis...
Published date:
21 October 2022
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 ...
Published date:
23 November 2023
Electrical cable fire test, IRSN.
The NEA PRISME project addressed in a series of 3 phases from 2006 till 2022 fire risk research. Operating experience shows that fire is one of the highest risks i...
Published date:
4 October 2023
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...
Published date:
31 August 2023
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:
17 October 2022
The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...
Published date:
23 May 2023
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:
17 October 2022
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:
19 April 2023
Illustration of the Horonobe Underground Research Laboratory and locations of the in situ experiments planned in each of the three HIP Joint Project task
The Horonobe International Project (HIP) is a...
Published date:
13 October 2023
HYMERES phases
First phase (2013-2016)
The main objective of the first phase of the Hydro...
Published date:
6 April 2020
The Information System on Occupational Exposure (ISOE) Project provides a forum for radiological protection (RP) professionals from nuclear electricity utilities and national regulatory authorities w...
Published date:
20 November 2023
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:
30 November 2022
Image adapted from Romolo Tavani, Shutterstock.
Exploring how innovative nuclear systems require innovative waste management solutions
The new NEA Joint Project on Waste Integration for Small and Adv...
Published date:
24 October 2023
JAEA High-temperature Engineering Test Reactor Photo: Japan Atomic Energy Agency (JAEA)
The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facil...
Published date:
7 November 2023
View looking down onto the LOFT reactor
The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened int...
Published date:
2 October 2023
View of the RASPLAV-3 Facility.
The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident with core melt. Specifica...
Published date:
6 October 2023
In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...
Published date:
2 October 2023
NEST HYMERES (Hydrogen containment experiments for reactor safety) project is addressing safety relevant phenomena in containments during accidents. It offers hands-on training opportunity during the...
Published date:
6 December 2019
This NEST project led by JAEA/CLADS will be dedicated to advanced remote technology for decommissioning under intense gamma-ray radiation environments (e.g robotics, virtual reality).
A short program...
Published date:
18 February 2020
This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...
Published date:
18 February 2020
PAKS Nuclear Power Plant, Hungary.
During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a sp...
Published date:
2 October 2023
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...
Published date:
31 August 2023
The goals of the Piping Failure Data Exchange (OPDE) Project were to:
- collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
Published date:
17 April 2020
Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monitoring and assessment s...
Published date:
22 April 2020
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:
25 November 2022
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:
6 October 2023
Scheme of the PSB-VVER facility, EREC
The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...
Published date:
6 October 2023
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...
Published date:
17 May 2023
Published date:
7 November 2023
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:
6 April 2023
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...
Published date:
6 October 2023
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:
27 October 2023
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...
Published date:
9 December 2022
Post-test view inside OLHF-4 vessel showing penetrations and resolidified weld material at the vessel bottom.
During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subj...
Published date:
27 October 2023
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 ...
Published date:
21 November 2023
Scheme of the PKL facility, Framatome GmbH.
The SESAR Thermal-hydraulics (SETH) Project began in 2001 and consisted of thermal-hydraulic experiments in support of accident management, which were ca...
Published date:
2 October 2023
Sorption is a combination of physical and chemical processes by which the migration of radionuclides in the geosphere (and possibly from a radioactive waste repository) can be slowed down under certa...
Published date:
28 May 2020
EPICUR facility, IRSN.
STEM phases
First phase (2011-2015)
The STEM Project was initiated with a first phase in 20...
Published date:
27 October 2023
Image at melt distribution and its contour at MBC (KAERI).
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co...
Published date:
2 October 2023
Fire protection layer for electrical cables
The Stress Corrosion Cracking and Cable Ageing Project (SCAP) lasted four years (2006-2010). The project’s main objectives were to:
Published date:
13 October 2023
Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik
Published date:
7 December 2022
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:
11 October 2022
Multi-compartment THAI+ test facility, Becker Technologies GmbH.
In the wake of the OECD/NEA THAI project, conducted in three phases from 2007 until 2019, a new project, THAI Experiments on Mitigat...
Published date:
2 October 2023
Scheme of the THAI+ facility, Becker Technologies.
The experimental investigations carried out in the frame of the THAI (2007-2009), THAI-2 (2011-2014) and THAI-3 (2016-2019) projects contributed s...
Published date:
2 October 2023
The Thermochemical Database (TDB) Project develops a reference database of chemical thermodynamic values for elements and compounds relevant to the safety of radioactive waste repositories and vital ...
Published date:
28 May 2020
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 ...
Published date:
6 October 2023
Published date:
2 August 2023
The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:
- oxide-carbide fuel (U-Pu-O-C, released Decemb...
Published date:
23 February 2023
On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.
A TMI accident evaluation pr...
Published date:
20 April 2020
