The Programme Review Group is established to perform a programme quality review function within the Committee on the Safety of Nuclear Installations (CSNI) and to provide scientific assistance to the...
Published date:
13 August 2024
To mark the occassion, an event was organised in Loen, Norway.
Published date:
12 June 2024
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:
2 May 2024
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:
26 April 2024
This publication addresses trends and patterns in material degradation as a function of nuclear power plant ageing, which is a key topic in the regulation of ageing management programmes, codes and s...
Published date:
22 April 2024
Project members held a meeting to discuss the activities.
Published date:
16 April 2024
NEA/CSNI/R(2022)8
Several NEA member countries agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage co-operation in the collection and analysis of data relati...
Published date:
13 March 2024
NEA/CSNI/R(2022)9
The objective of this study is to compare leak rate computation practices and the applied tools and software solutions. Leak rate prediction is an important aspect of the leak-beforebreak assessment,...
Published date:
13 March 2024
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:
21 February 2024
Cable samples of Beznau NPP
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 Pro...
Published date:
20 February 2024
Pipe Degradation & Failure as a Function of In-Service Time (Years) at the time of the OPDE project closure
The goals of the Piping Failure Data Exchange (OPDE) Project were to:
Published date:
20 February 2024
A Task Group on Advanced Reactor Experimental Facilities (TAREF) had been set up to provide an overview of facilities suitable for carrying out safety research on gas-cooled and sodium fast reactors....
Published date:
28 April 2020
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
The Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF) was established at the June 2013 CSNI meeting to identify research activities to address safety research knowledge gaps...
Published date:
4 February 2021
The Senior Expert Group on Safety Research / Support Facilities for Existing and Advanced Reactors 2 (SESAR/SFEAR2) is responsible for reviewing and updating the previous SESAR assessments of researc...
Published date:
22 April 2020
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
The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...
Published date:
10 October 2023
Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...
Published date:
1 January 1999
The main mission of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) is to advance the current understanding of the relevant aspects related with ensuring the integrity...
Published date:
10 August 2022
NEA/CSNI/R(2008)8
Common-cause failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common-Cause Failure Data Exchange (ICDE) Pro...
Published date:
1 July 2008
NEA/CSNI/R(2013)4
The purpose of the ICDE Project is to allow multiple countries to collaborate and exchange common cause failure (CCF) data to enhance the quality of risk analyses that include CCF modelling. Because ...
Published date:
3 July 2013
NEA/CSNI/R(2013)2
The purpose of the International Common Cause Data Exchange (ICDE) Project is to allow multiple countries to collaborate and exchange Common Cause Failure (CCF) data to enhance the quality of risk an...
Published date:
4 July 2013
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
NEA/CSNI/R(2018)5
This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...
Published date:
26 September 2018
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
Published date:
2 August 2022
NEA/CSNI/R(2018)8
The number of ageing nuclear power plants (NPPs) is increasing in NEA member countries. Accordingly, maintenance programmes, in-service inspection and testing of structures, systems and components im...
Published date:
6 December 2018
NEA/CSNI/R(2007)15
The Material Scaling (MASCA) Project investigated in-vessel phenomena during a severe accident. In particular, it addressed the influence of the chemical composition of the molten corium on the heat ...
Published date:
1 June 2007
NEA/CSNI/R(2004)21
The Third International Conference on Fatigue of Reactor Components held in Seville, Spain on 3-6 October 2004 was co-organised by the EPRI, the US NRC and the OECD NEA Committee on the Safety of Nuc...
Published date:
5 January 2005
NEA/CSNI/R(2015)18
In 2012, following a proposal from Japan, the Committee on the Safety of Nuclear Installations (CSNI) decided to initiate a joint project to conduct a study of the accident progression for the Fukush...
Published date:
1 March 2015
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
NEA/CSNI/R(2015)11
This report documents a study performed on a set of ICDE events related to heat exchangers. The events studied here had been collected in the ICDE database. Organisations from Canada, Germany, Japan,...
Published date:
1 April 2013
NEA/CSNI/R(2011)12
In this document, the general coding guidelines for the OECD NEA ICDE Project (International Common Cause Failure Data Exchange) are presented with explanations and appendices for each analysed compo...
Published date:
21 February 2012
The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...
Published date:
29 October 2021
New Joint Project: Studsvik Material Integrity Life Extension (SMILE)
Published date:
26 January 2021
NEA/CSNI/R(2009)9
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) considered there was a need to review the state-of-the-art tech...
Published date:
14 December 2009
NEA/CSNI/R(2009)3
This Phase II exercise was the first benchmarking of severe accident codes promoted by NEA in almost 20 years. The objective of the exercise was to perform a code benchmark on a well-defined plant (s...
Published date:
3 August 2009
NEA/CSNI/R(2008)14
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...
Published date:
17 December 2008
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
NEA/CSNI/R(2008)1
Common-cause-failure (CCF) events can significantly impact the availability of safety systems of nuclear power plants. For this reason, the International Common Cause Failure Data Exchange (ICDE) pro...
Published date:
25 January 2008
NEA/CSNI/R(2008)7
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has as a general mandate to advance the current understanding o...
Published date:
17 July 2008
NEA/CSNI/R(2004)4
Several member countries of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) established the International Common-Cause Failure Data Exchange Project...
Published date:
30 January 2004
NEA/CSNI/R(2004)10
In the report “Nuclear Safety Research in OECD Countries: Summary Report of Major Facilities and Programmes at Risk“ published by the NEA/CSNI Senior Group of Experts on Nuclear Safety Research Facil...
Published date:
7 July 2004
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:
1 January 1998
NEA/CSNI/R(2012)16
Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OECD/NEA OPDE) to encourage multilateral co-operation in the collection and analysis of data relat...
Published date:
26 November 2012
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
Published date:
22 November 2002
The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....
Published date:
22 December 2000
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
Published date:
19 November 2003
Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.
Published date:
18 March 2020