Published date:
6 October 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
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
The OECD NEA RASPLAV Project provided experiments with prototypical material and data on the behavior of molten core material (corium) in the reactor pressure vessel lower head during a severe accide...
Published date:
6 October 2023
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
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
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
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
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
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
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
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
Experts attended NEA event in France.
Published date:
14 September 2023
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.
Published date:
14 September 2023
11 -
13 September 2023
IRSN, Fontenay-aux-Roses, France
Published date:
4 September 2023
The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.
Published date:
1 September 2023
NEA Working Group on Analysis and Management of Accidents (WGAMA) initiated this activity focusing on computational fluid dynamics (CFD) in nuclear reactor safety (NRS).
Published date:
1 September 2023
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
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
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
NEA/CSNI/R(2021)8
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...
Published date:
28 August 2023
NEA/CSNI/R(2022)2
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...
Published date:
28 August 2023
Supporting the use of computational fluid dynamics for nuclear reactor safety
Published date:
27 June 2023
Innovations in nuclear safety thermal-hydraulics
Published date:
26 June 2023
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
Around 50 delegates from 22 countries and 2 international organisations gathered on 6-7 June 2023 for the 73rd CSNI meeting.
Published date:
14 June 2023
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
13 June 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
NEA/CSNI/R(2021)3
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...
Published date:
15 May 2023
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
Approximately 30 experts from WGAMA discussed how to advance the understanding of phenomena in pool in the situation of a loss of cooling accident.
Published date:
25 April 2023
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.
Published date:
21 April 2023
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
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.
Published date:
7 April 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
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...
Published date:
5 April 2023
The 9th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023.
Published date:
23 March 2023
NEA/CSNI/R(2020)14
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...
Published date:
15 February 2023
NEA/CSNI/R(2020)2
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...
Published date:
15 February 2023
NEA/CSNI/R(2020)8
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...
Published date:
13 January 2023
9 -
13 January 2023
Online
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...
Published date:
27 February 2024
Second Workshop on International Harvesting Co-operation focused on the status of aged metals harvesting and opportunities for international collaborative research.
Published date:
14 December 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
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
Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik
Published date:
7 December 2022
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
Two new reports from the WGFS highlight the latest developments in RIA research.
Published date:
30 November 2022
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
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
NEA/CSNI/R(2019)11
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...
Published date:
24 November 2022