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
Advanced instrumentation for nuclear reactor thermal hydraulics experiments
Published date:
18 November 2019
Published date:
7 May 2010
NEA/CSNI/R(2003)12
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Published date:
31 March 2003
Published date:
5 February 2001
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
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
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
Published date:
1 January 1987
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:
7 July 2022
International workshop convened experts in the field to United States.
Published date:
20 November 2023
NEA/CSNI/R(2007)2
Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios for nuclear power plants. The technic...
Published date:
26 January 2022
The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report
Published date:
8 July 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
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
HYMERES phases
First phase (2013-2016)
The main objective of the first phase of the Hydro...
Published date:
6 April 2020
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
Published date:
11 July 2003
Published date:
28 November 2003
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
Published date:
16 February 1999
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
Published date:
23 August 2000
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
Published date:
26 April 2001
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
Published date:
15 July 2002
NEA/CSNI/R(2019)3
The ICDE project allows multiple countries to collaborate and exchange CCF data to enhance the quality of risk analyses, which include CCF modelling. Because CCF events are typically rare, most count...
Published date:
21 January 2019
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
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
17 -
19 April 2018
Boulogne-Billancourt, France
Hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)
Objectives
Working under the mandate of the CSNI, the objective of the WGFCS i...
Published date:
30 April 2020
16 -
17 November 2023
US Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, MD 20852, United States
Published date:
10 October 2023
11 -
13 September 2023
IRSN, Fontenay-aux-Roses, France
Published date:
4 September 2023
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
NEA/CSNI/R(2002)27
Volume 1 – Integral Experiments and Material Characterization
Published date:
28 May 2003
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(2007)6
This report provides an overview of experimental facilities that can be used to address nuclear safety research issues in OECD member countries, and identifies priorities for organising international...
Published date:
1 January 2007
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...
Published date:
19 December 2023
Published date:
10 April 2001
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(2000)23
14-15 November 2000, Munich, Germany
Published date:
13 December 2000
Risk assessments are used to determine the probability of harmful events at a nuclear plant. They are valuable for determining the relative benefit and better selection of safety enhancements.
Published date:
17 March 2020
Experts attended NEA event in France.
Published date:
14 September 2023
Published date:
1 January 1998
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(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