More than 20 international experts gathered for the second meeting of the third phase of the TAF-ID project.

The project participants, who come from 19 organisations in 8 countries, met in December 2023 in Karlsruhe.

PAKS control room.

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 monito...

“Improving Cross-disciplinary and Transversal Skills for the Severe Accidents Community” approved by NEST Management Board.

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...

FIDES-II member assembled at the Japan Atomic Energy Agency (JAEA) in Mito, Japan.

The NEA ATLAS3 and NEA ETHARINUS projects organised a workshop on 7-9 November 2023. 

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

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...

FACE project members met on 28-30 June 2023 in Paris, France.

TCOFF-2 members discuss future activities.

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...

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...

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

NEA delegation participates in discussions at the Regulatory Information Conference in Washington D.C.

Thermodynamic databases and accident prevention

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 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...

The NEA event reviews the accomplishments of the joint safety projects.

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...

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...

FIDES-II members hold meeting at Idaho National Laboratory

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 ...

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...

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

The NEA’s ruling body the Steering Committee for Nuclear Energy met for its143rd biannual meeting in April 2022.

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...

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) issued a report titled Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR...

The NEA Co‑operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) held its Technical Advisory Group (TAG) meeting ...

Nearly 100 experts from the NEA Analysis of Information from Reactor Buildings and Containment Vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) Project and the Preparatory Study on Fuel Deb...

Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...

NEA Co‑operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) management board meeting on 19-20 November 2020.

Virtual kick-off meeting for the new joint project Experiments on Source Term for Delayed Releases (ESTER), 28-30 September 2020.