NEA/CSNI/R(2021)14/ADD
During the 28-30 January 2019 meeting on Digital I&C PSA – Comparative application of Digital Instrumentation and Control (I&C) Modelling Approaches for Probabilistic Safety Assessment (PSA) hosted b...
Published date:
6 February 2024
International workshop convened experts in the field to United States.
Published date:
20 November 2023
Disruptive technologies for nuclear safety applications
Published date:
13 August 2020
NEA/CSNI/R(2006)6
The purpose of this report is to present in a concise form how some safety matters associated with currently operating light water reactors have been addressed. The issues discussed in this report ar...
Published date:
2 November 2006
NEA/CSNI/R(2010)13
The idea of a benchmark study on risk-informed in-service inspection (RI-ISI) was initially developed within a subgroup of the ENIQ Task Group on Risk. The preliminary JRC project proposal was endors...
Published date:
26 January 2011
Published date:
30 September 2022
NEA/CSNI/R(2015)1
The work described in this report was conducted as a joint task under the CSNI Working Groups on Human and Organisational Factors (WGHOF) and Risk Assessment (WGRISK). The task has two primary purpos...
Published date:
1 March 2015
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...
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15 February 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
NEA/CSNI/R(2016)7
Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular external and internal hazards, occur throughout their entire lifetime. ...
Published date:
27 July 2016
NEA/CSNI/R(2018)7
It has long been recognised that external hazards can present a potential common cause source of initiating events that could challenge nuclear power plant safety. Modelling of these hazards is a com...
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2 April 2019
The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report
Published date:
8 July 2022
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(2009)8
The Committee on the Safety of Nuclear Installations (CSNI) established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facil...
Published date:
1 January 2009
This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for sodium fast reactors and identifies priorities for organising international co-op...
Published date:
15 April 2011
NEA/CSNI/R(2010)12
In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) ...
Published date:
1 January 2011
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
NEA/CSNI/R(2009)12
Computational fluid dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coola...
Published date:
6 January 2010
CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: IRSN
Following several years of experimental research in the field of source terms analysis...
Published date:
21 October 2022
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.
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7 April 2023
The fourth FACE meeting brought together experts to Cologne, Germany.
Published date:
27 February 2024
CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.
Published date:
10 June 2022
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
NEA/CSNI/R(2014)13/REV1
This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by the Writing Group 3 on the extension of CFD to two-phase flow safety problems, which was formed following the recommen...
Published date:
1 November 2014
NEA/CSNI/R(2010)2
This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by Writing Group 3 on the extension of computational fluid dynamics (CFD) to two-phase flow safety problems. Writing Group ...
Published date:
21 July 2010
Demonstrating the safety of a nuclear facility requires that the consequences of all possible threats be considered, including external hazards such as severe weather, floods and earthquakes.
Published date:
18 March 2020
NEA Working Group on External Events (WGEV) meeting, 1-5 March 2021.
Published date:
24 March 2021
NEA Working Group on External Events (WGEV) meeting, 14-18 September 2020.
Published date:
9 October 2020
NEA/CSNI/R(2014)16
The objective of the Digital System Reliability Failure Mode Taxonomy (DIGREL) task group, formed under the OECD/NEA Working Group on Risk Assessment (WGRISK), has been to develop a taxonomy of failu...
Published date:
16 February 2015
NEA/CSNI/R(2005)2
At the Committee on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for a benchmark on thermal fatigue in fluid mixing areas based on the test performed by the Commissaria...
Published date:
1 August 2005
NEA/CSNI/R(2017)2
This is a summary report from the International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain. Over 90 specialists from 21 countries attended th...
Published date:
17 July 2017
NEA/CSNI/R(2017)2/ADD1
International Conference on Fatigue of Nuclear Reactor Components on 28 September-1 October 2015 in Seville, Spain.
In this work, a complete algorithm for monitoring fatigue was developed for nuclear...
Published date:
17 July 2017
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
NEA/CSNI/R(2013)1
The OECD/NEA ROSA Project was performed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety by using the ROSA/LSTF of JAEA for 4 years from April 2005. In pa...
Published date:
30 April 2013
NEA/CSNI/R(2016)10
The use of computer codes is required in safety evaluation of light water reactors (LWRs) in order to simulate plant behaviour during design basis event (DBE) and beyond-DBE (BDBE). This involves co...
Published date:
1 June 2017
NEA/CSNI/R(2004)24
At its annual meeting in December 1999, the Committee on the Safety of Nuclear Installations (CSNI) issued a recommendation to set up an international collaborative project in the field of thermal-hy...
Published date:
1 December 2004
NEA/CSNI/R(2016)13
Taking into account life extension, concrete degradation becomes one of the main issues for long-term operation (LTO). Concrete pathologies/degradation mechanisms – alkali-aggregate reaction (AAR), d...
Published date:
4 July 2017
NEA/CSNI/R(2016)13/ADD1
Taking into account life extension of nuclear power plants (NPPs) there is a need to investigate degradation mechanisms of existing structures defining their aging management program. The Alkali Aggr...
Published date:
1 July 2017
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
NEA/CSNI/R(2009)6
In 2000, the Committee on the Safety of Nuclear Installations (CSNI) approved the establishment of a Fire Incident Records Exchange Project on collection of data on fire events at nuclear power plant...
Published date:
24 September 2009
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
NEA/CSNI/R(2015)7
CODAP is the continuation of the 2002-2011 “OECD/NEA Pipe Failure Data Exchange Project” (OPDE) and the work by the Stress Corrosion Cracking Working Group of the 2006–2010 “OECD/NEA SCC and Cable Ag...
Published date:
4 May 2015
26 -
27 September 2024
Argonne National Laboratory, Lemont, IL, United States
Context of the workshop
Since its inception, the Nuclear Energy Agency (NEA) has served as a flexible and powerful platform for multinational research co-operation, particularly in areas related to n...
Published date:
15 April 2024
The facilities associated with nuclear fuel from mining to fabrication to post-irradiation management have some specific safety concerns that are different from those of nuclear reactors.
Published date:
18 March 2020
The fuel for a nuclear reactor is both the source of the fission energy that is used to produce electricity and the source of radioactive material during an accident.
Published date:
18 March 2020
Fukushima Daiichi Nuclear Power Plant Accident: Message from Director-General Magwood
Published date:
11 March 2022
Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority
The FACE projec...
Published date:
17 October 2022
Fukushima Daiichi nuclear safety research projects
Published date:
4 March 2020
Halden Hammlab research facility for human factor research.
The NEA Halden HTO Project is a continuation of Man-Technology-Organisation (MTO) research carried out for more than 40 years as part of t...
Published date:
22 March 2024