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
NEA/CSNI/R(2008)2
The OECD-IAEA Paks Fuel Project was established in 2005 as a joint project between the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (NEA). The IAEA provided financial ...
Published date:
18 September 2008
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(2014)15
The SERENA Project Integration Report summarises the outcome of a broad range of activities conducted in the framework of the OECD Nuclear Energy Agency (NEA) Steam Explosion Resolution for Nuclear A...
Published date:
1 February 2015
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
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
Prevention, mitigation and management of potential accidents in nuclear power plants
Published date:
5 October 2022
The NEA Working Group on the Analysis and Management of Accidents (WGAMA) held its annual meeting virtually on 13-15 September 2021 to discuss its ongoing work and activities related to potential acc...
Published date:
1 October 2021
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
Published date:
10 April 2001
NEA/CSNI/R(2020)4
The investigation conducted in the last 15 years on different aspects of Source Term worldwide, and particularly in the context of the Nuclear Energy Agency (NEA) in the form of projects and the Work...
Published date:
14 April 2022
Two new reports from the WGFS highlight the latest developments in RIA research.
Published date:
30 November 2022
NEA/CSNI/R(2005)1
The TMI-2 accident keeps providing unique full scale data giving opportunities to check the ability of the codes to model overall plant behaviour and to perform many sensitivity and uncertainty calcu...
Published date:
10 March 2005
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
Published date:
7 November 2023
NEA/CSNI/R(2000)23
14-15 November 2000, Munich, Germany
Published date:
13 December 2000
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
NEA/CSNI/R(1997)27
Lyon, France, 8-10 September 1997
Published date:
1 January 1997
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
Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant
Published date:
17 December 2020
The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialists’ meeting on transient thermal-hydraulics in water cooled nuclear reactors on 22-23 March 2022.
Published date:
6 April 2022
NEA/CSNI/R(2021)1
The Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), co-organised by the S...
Published date:
5 October 2022
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
NEA/CSNI/R(2020)13
Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...
Published date:
23 November 2022
This task group was set up to carry out a pilot project using the methodology propsed in the final SMAP report published in 2007. In this pilot project, the SMAP methodology was applied to the Zion n...
Published date:
27 April 2020
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
Long-handled tools are used to remove the damaged core from the TMI unit 2 reactor in the US. Samples taken from the fuel and the reactor vessel are examined to provide information about the Behaviou...
Published date:
21 February 2024
NEA/CSNI/R(1991)8
Three Mile Island Unit 2 Analysis Exercise Final Report
Published date:
1 January 1991
Published date:
1 January 1991
Published date:
17 August 2006
NEA/CSNI/R(2001)4
A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix (2001)
Published date:
16 February 2001
Published date:
11 April 2011
In the framework of the WGAMA/WGFS activity "Status Report on Good Practices for Analyses of Design Extension Condition without Significant Fuel Degradation (DEC-A) for Operating Nuclear Power Plants...
Published date:
20 December 2023
The Working Group on the Analysis and Management of Accidents (WGAMA) focuses on the NEA activities related to potential design-basis and beyond design-basis accidents in nuclear reactors and related...
Published date:
20 December 2023
NEA/CSNI/R(2015)17
In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...
Published date:
20 October 2015
15 -
18 November 2016
Aomori City, Japan
The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Developments in Fuel Cycle Facilit...
Published date:
4 May 2020
NEA/CSNI/R(2020)5
The Workshop on Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues, CFD4NRS-7 was the seventh in a series of workshops focusing on Computational Fluid Dyna...
Published date:
19 January 2022
NEA/CSNI/R(2017)8
This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...
Published date:
24 August 2017