NEA/SEN/SIN/IAGE/A(2016)1
Published date:
10 March 2016
Published date:
23 December 1997
Published date:
26 December 1986
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
Published date:
1 January 1981
NEA/CSNI/R(2012)17
Probabilistic safety assessment/probabilistic risk assessment (PSA/PRA) for new and advanced reactors is recognized as an important approach to achieve improved safety for the future nuclear power pl...
Published date:
19 February 2013
NEA/CSNI/R(2015)10
Due to the potential safety significance of HEAF events the NEA initiated a project to provide an in-depth investigation on such events in NEA member states. The general objective of the study was to...
Published date:
9 June 2015
The NEA Component Operational Experience, Degradation and Ageing Programme (CODAP) is the continuation of the NEA Pipe Failure Data Exchange Project (OPDE – 2002 to 2011) and the NEA Stress Corrosion...
Published date:
22 April 2024
Published date:
1 January 1992
NEA/CSNI/R(2016)14
The present document deals with scaling in nuclear-system thermal hydraulics (SYS TH), including the connection with nuclear-reactor safety technology (NST). Scaling has constituted “an issue” since ...
Published date:
1 March 2017
Published date:
1 January 1986
Published date:
23 December 1986
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(2015)3
Based on the conclusions of the previous benchmark exercise, the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by examinin...
Published date:
19 June 2015
Published date:
6 October 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
Published date:
9 July 2001
NEA/CSNI/R(2004)16
The main objective of ISP exercises is to increase confidence in the validity and accuracy of the tools that are used in assessing the safety of nuclear installations. The secondary objective is to e...
Published date:
1 November 2004
NEA/CSNI/R(2016)8
The overall objective of the THAI-2 project is to address open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during design-basis or s...
Published date:
1 February 2017
NEA/CSNI/R(2010)4
The objective of the NEA’s Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member coun...
Published date:
24 November 2010
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
Published date:
1 January 1995
Published date:
1 January 1995
Published date:
7 May 2010
Published date:
1 January 1990
Published date:
1 January 1987
Published date:
1 January 1986
Published date:
19 February 2007
Published date:
19 February 2007
Published date:
19 February 2007
NEA/CSNI/R(2003)12
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Published date:
31 March 2003
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
Published date:
23 December 1991
Published date:
10 June 2002
Published date:
10 June 2002
Published date:
1 January 1986
Published date:
1 January 1983
NEA/CSNI/R(2014)12
Following recommendations made at an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) codes to nuclear reactor safety (NRS) problems, h...
Published date:
16 January 2015
NEA/CSNI/R(2007)13
Following recommendations made at an “Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety (NRS) Problems”,...
Published date:
28 January 2008
Published date:
25 November 2021
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(2006)2
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) Programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
19 June 2006
NEA/CSNI/R(2007)4
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the Sa...
Published date:
11 October 2007
NEA/CSNI/R(2008)6/VOL2
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL3
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL1
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2009)13
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
21 December 2009
NEA/CSNI/R(2011)4
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Analysis and Management of Accidents (WGAMA) and endorsed by the Committee on t...
Published date:
28 March 2011
Published date:
1 January 1989
Published date:
16 December 2008
NEA/CSNI/R(2017)11
For most nuclear design and in-service inspection codes, fracture mechanics is used to evaluate the integrity of cracked components. The major parameters used in this kind of analysis are K and J whi...
Published date:
1 November 2017
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
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
NEA/CSNI/R(2010)6
The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicability to high b...
Published date:
15 November 2010
NEA/CSNI/R(2015)19
The objective of this joint WGAMA-WPNEM activity was to benchmark software tools used to estimate consequences of accidents at nuclear facilities. Two aspects of accident consequences were considered...
Published date:
1 January 2016
NEA/CSNI/R(2007)5
In May 2002, an “Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems” was held in Aix-en-Provence...
Published date:
15 May 2007
NEA/CSNI/R(2014)11
In May 2002, an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) Codes to nuclear reactor safety problems was held in Aix-en-Provence, ...
Published date:
12 February 2015
NEA/CSNI/R(2015)5
NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current understanding of those aspects relevant to ensuring the integrity of s...
Published date:
1 June 2015
Published date:
1 January 1996
Published date:
5 February 2001
Published date:
1 January 1973
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
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
Published date:
15 February 2000
Published date:
1 January 1996
Published date:
1 January 1985
NEA/CSNI/R(2014)4
Following the CFD4NRS workshops held in Garching, Germany (September 2006), Grenoble, France (September 2008) and Washington D.C., USA (September 2010), this workshop, held in Daejeon, Korea on 10-12...
Published date:
14 February 2014
NEA/CNRA/R(2015)8
A workshop on challenges and enhancements to the safety culture of the regulatory body (SCRB) was held on 3 June 2015 in Paris, France. The workshop provided an invaluable opportunity for an exchange...
Published date:
7 December 2015
NEA/CSNI/R(2014)6
The Component Operational Experience, Degradation & Ageing Programme (CODAP) Topical Report on FAC of Carbon Steel and Low Alloy Steel Piping includes a primer on the environmental and operational fa...
Published date:
20 January 2015
NEA/CSNI/R(2020)7
The cold leg mixing computational fluid dynamics (CFD) – uncertainty quantification (CLM-UQ) benchmark is the fifth benchmark concerning CFD applications to nuclear reactor safety to be organised in ...
Published date:
3 November 2022
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(2015)14
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) (formerly PWG5) established in 1996 a Task Group to review the status and maturity of methods use...
Published date:
16 December 2015
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
NEA/CSNI/R(2018)10
One of the major conclusions of this workshop was that simulation of electrical systems has not been adequately discussed at the international level despite the fact that it is used more and more fre...
Published date:
19 February 2019
NEA/CSNI/R(2019)1
Seismic hazards remain an important factor that nuclear power plant designers and operators worldwide must take into account. Therefore, the Working Group on the Integrity and Ageing of Components a...
Published date:
3 June 2019
Published date:
1 January 1986
Published date:
1 January 1988
Published date:
1 January 1982
Published date:
16 February 1999
Published date:
29 November 1999
Published date:
1 January 1989
Published date:
1 January 1983
Published date:
1 January 1980
Published date:
1 January 1981
Published date:
1 January 1979
Published date:
1 January 1978
Published date:
16 December 2008
Published date:
1 January 1988
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:
11 April 2024
Published date:
30 November 2020
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
NEA/CSNI/R(2017)20
The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the biennial series, supported by the Nuclear Energy Agency Worki...
Published date:
6 May 2019
NEA/CSNI/R(2016)1
This present workshop was held in Zurich, Switzerland on 9-11 September 2014. It is the 5th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-5), in the biennial series of...
Published date:
1 January 2016
Published date:
1 January 1996
NEA/CSNI/R(2008)13
During the mid 1990s a task group was formed within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA) to exchange information on events involving computer-ba...
Published date:
5 January 2009
NEA/CSNI/R(2012)12
In 2005 the OECD/NEA Steering Committee agreed to establish the international Computer-based Systems Important to Safety (COMPSIS) project to encourage multilateral co-operation in the collection and...
Published date:
19 July 2012
Published date:
18 February 2000
NEA/CSNI/R(2020)9
This report provides insights from a survey of Nuclear Energy Agency (NEA) member countries on the concepts used to establish effective measures to cope with external flooding hazards and on the term...
Published date:
5 October 2022
Published date:
11 December 2002
NEA/CSNI/R(2004)3
This document is the second in a series of CSNI Working Group on Operating Experience (WGOE) technical notes on recent events in nuclear power plants (NPPs). The purpose is to transmit WGOE views to ...
Published date:
16 January 2004
Published date:
7 November 2022
Published date:
1 January 1990
Published date:
1 January 1995
NEA/CSNI/R(2014)3
This report initially provides a brief overview of the main features of a PWR, BWR, CANDU and VVER reactors. It also provides an overview of the ex-vessel corium retention (core catcher) and a genera...
Published date:
23 May 2014
Published date:
1 January 1989
Published date:
1 January 1986
Published date:
1 January 1997
Published date:
1 January 1994
NEA/CSNI/R(2010)9
The Task on the Core Exit Temperature (CET) thermocouple effectiveness in Accident Management (AM) was initiated based on a discussion held by the NEA’s Committe on the Safety of Nuclear Installation...
Published date:
26 November 2010
Published date:
23 December 1998
Published date:
23 December 1998
The CSNI Action Plan in the Area of Safety Margins was set up by the Committee on the Safety of Nuclear Installations (CSNI),
Published date:
27 April 2020
Published date:
1 January 1987
NEA/CSNI/R(2008)5
In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) issued a report titled Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR...
Published date:
20 December 2021
NEA/CSNI/R(1996)17
This report deals with an internationally agreed integral test facility (ITF) matrix for the validation of best estimate thermal-hydraulic computer codes. Firstly, the main physical phenomena that oc...
Published date:
1 January 1996
NEA/CSNI/R(2004)5
This revised document was reviewed and endorsed in September 2003 by the Committee on the Safety of Nuclear Installations (CSNI) Working Group on the Analysis and Management of Accidents (WGAMA), whi...
Published date:
9 March 2004
Published date:
15 February 2000
Published date:
1 January 1977
NEA/CSNI/R(2007)7/REV1
The Operating Plan describes the Committee on the Safety of Nuclear Installations (CSNI) responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-call...
Published date:
11 April 2008
NEA/CSNI/R(2011)2
The Operating Plan describes CSNI responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-called CSNI Activity Report, which contains a description o...
Published date:
19 April 2011
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
CSNI Programme Review Group (PRG) annual review meeting, 27‑28 April 2020.
Published date:
5 May 2020
Published date:
1 January 1997
Published date:
7 October 1980
Published date:
6 October 1980
Published date:
1 January 1991
Published date:
1 January 1993
Published date:
1 January 1987
Published date:
1 January 1980
The Nuclear Energy Agency (NEA) Working Group on the Analysis and Management of Accidents (WGAMA) aims to contribute to the assessment of the prevention, mitigation and management of accidents, ultim...
Published date:
5 October 2023
Published date:
1 January 1996
The NEA Committee on the Safety of Nuclear Installations (CSNI) established a task group to examine Defence in Depth of Electrical Systems and Grid Interaction (DIDELSYS). The DIDELSYS Project, carri...
Published date:
17 April 2020
NEA/CSNI/R(2009)7
This technical opinion paper represents the consensus of the Committe on the Safety of Nuclear Installations (CSNI) Working Group on Human and Organisational Factors (WGHOF) on the state of research ...
Published date:
1 January 2009
NEA/CSNI/R(2012)7
The objective of the OECD Nuclear Energy Agency (NEA) Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding for both regulators and operators of relevant aspects of fuel cycle sa...
Published date:
1 January 2012
CSNI Technical Opinion Paper No. 17: Fire Probabilistic Safety Assessments for Nuclear Power Plants: 2019 Update provides an authoritative review of the current status and use of the fire PSA in nucl...
Published date:
27 May 2019
While there is a growing interest in the deployment of small modular reactors (SMRs) as a promising option to help mitigate climate change, further international efforts are needed to accelerate the ...
Published date:
10 October 2023
Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; fe...
Published date:
3 February 2009
Errors during maintenance and periodic testing are significant contributors to plant events. These errors may not always be revealed by post-maintenance tests and may remain undetected for extended p...
Published date:
26 February 2009
It is a dynamic time for the nuclear power sector. Existing reactor control rooms are undergoing various forms of modernisation. New reactors are being built in many countries and advanced reactors a...
Published date:
11 December 2009
Feedback on operating experience from nuclear power plants is intended to help avoid occurrence or recurrence of safety-significant events. Well-established feedback systems exist on the national and...
Published date:
31 December 2004
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of human reliability analysis (HRA) in probabilistic safety assessment (...
Published date:
9 February 2004
Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as electricity markets are liberalised. One of the costs that is often perceived as being amenable to...
Published date:
9 June 2004
This technical opinion paper provides the reader with a concise description of both the benefits and disadvantages of using probabilistic safety assessment (PSA) to analyse operational events in nucl...
Published date:
2 December 2004
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of level-2 probabilistic safety assessment (PSA) and its applications in...
Published date:
20 April 2007
These technical opinion papers represent the consensus of risk analysts and experts in NEA Member countries on the current state of the art in Fire Probabilistic Safety Assessment (PSA) for nuclear p...
Published date:
26 September 2002
Probabilistic safety analyses (PSAs) for many of the nuclear power plants throughout the world are being maintained as "living PSAs" (LPSAs), being updated to take account of changes to the design an...
Published date:
1 February 2005
Acceptance criteria for emergency core cooling systems (ECCS) define the maximum temperature and degree of oxidation in order to avoid excessive embrittlement and hence failure of the fuel cladding, ...
Published date:
21 September 2011
The way in which nuclear licensees’ organisations are structured and resourced clearly has a potential impact on nuclear safety. As experience has continually demonstrated, operating organisations wi...
Published date:
15 May 2012
NEA/CSNI/R(2011)13
The primary role of the OECD Nuclear Energy Agency (NEA) Working Group on Human and Organisational Factors (WGHOF) is to improve the current understanding and treatment of human and organisational fa...
Published date:
1 January 2012
Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into a...
Published date:
31 December 2013
As all safety systems in the majority of existing nuclear power plants use the preferred power supply, any voltage surges in these systems could lead to common-cause failures. In the event of an unus...
Published date:
17 May 2013
NEA/CSNI/R(2011)7
The NEA Committe on the Safety of Nuclear Installations (CSNI), noting that different approaches to determining cladding embrittlement criteria produced nearly identical limits, asked the Working Gro...
Published date:
1 January 2011
Published date:
12 October 1999
Published date:
1 January 1996
Published date:
1 January 1991
NEA/CSNI/R(2015)9
This report has been written in the framework of seismic subgroup of the NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to provide a brief review of current prac...
Published date:
29 May 2015
NEA/CSNI/R(2004)6
The “Current Severe Accident Research Facilities and Projects” list was compiled by the Committee on the Safety of Nuclear Installations Working (CSNI) Group on the Analysis and Management of Acciden...
Published date:
9 March 2004
NEA/CSNI/R(2004)2
The workshop on Debris Impact on Emergency Coolant Recirculation was held in Albuquerque, the United States on 25-27 February 2004. It was organised under the auspices of the NEA Committee on the Saf...
Published date:
24 November 2004
NEA/CSNI/R(2009)10
The NEA Committee on the Safety of Nuclear Installations (CSNI) authorised formation of a task group in January 2008 to examine Defence in Depth of Electrical Systems and Grid Interaction with nuclea...
Published date:
9 November 2009
Published date:
6 December 1999
Published date:
1 January 1996
Published date:
1 January 1986
Published date:
1 January 1986
Published date:
1 January 1986
Published date:
1 January 1986
Published date:
1 January 1986
Published date:
1 January 1986
Published date:
1 January 1997
Published date:
1 January 1998
NEA/CSNI/R(2017)12
The main objective of the workshop, held in Aomori City, Japan on 15-17 November 2016, was to review and discuss national activities, plans and regulatory approaches by member countries in light of ...
Published date:
8 January 2018
NEA/CSNI/R(2017)12/ADD1
The workshop was held in Aomori City, Japan on 15-17 November 2016.
On 11 March 2011, the Tohoku-Taiheiyou-Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake ...
Published date:
1 January 2018
NEA/CSNI/R(2007)17
At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2003, a proposal of the CSNI Working Group on the Integrity and Ageing (WGIAGE) to examine the differences in approach b...
Published date:
1 February 2008
Published date:
23 December 1997
Published date:
23 December 1997
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
Published date:
1 January 1993
Published date:
19 July 2002
Published date:
1 January 1989
Published date:
1 January 1987
Published date:
22 December 2000
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...
Published date:
15 February 2023
Published date:
1 January 1992
Published date:
1 January 1986
Published date:
1 January 1996
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
Published date:
1 January 1995
Published date:
1 January 1995
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...
Published date:
2 April 2019
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
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.
Published date:
7 April 2023
Published date:
1 January 1985
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
Published date:
28 April 1998
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
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
Published date:
1 January 1994
Published date:
1 January 1996
Published date:
29 April 1998
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
Published date:
1 January 1997
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
Published date:
1 January 1988
Published date:
1 January 1990
Published date:
29 November 1999
Published date:
29 November 1999
Published date:
29 November 1999
Published date:
1 January 1994
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
Published date:
17 February 2004
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
Published date:
27 June 2002
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
Published date:
23 December 1999
Published date:
1 January 1980
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
Published date:
15 February 2000
Published date:
7 February 2000
Published date:
16 December 2008
Published date:
1 January 1995
Published date:
24 February 2003
Published date:
6 December 1999
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
Published date:
1 January 1982
Published date:
1 January 1994
Published date:
1 January 1988
Published date:
1 January 1998
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
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:
17 October 2022
Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...
Published date:
7 April 2022
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
Published date:
1 January 1996
Published date:
3 October 2008
Published date:
1 January 1995
Published date:
1 January 1995
NEA/CSNI/R(2016)17
The theme of this workshop, held in Charlotte, United States on 19-21 February 2015, was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Po...
Published date:
2 June 2017
NEA/CSNI/R(2016)17/ADD1
This document is Appendix B of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications, held in Charlotte, United States on 19...
Published date:
1 March 2017
NEA/CSNI/R(2016)17/ADD2
Thisi document contains Appendix C of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications held in Charlotte, United States...
Published date:
1 March 2017
NEA/CSNI/R(2015)16
The workshop took place in Brugg, Switzerland on 24-26 February 2014. It was conducted with participation of a number of invited key speakers from academic research and a range of industries, includi...
Published date:
20 October 2015
Published date:
22 December 1989
Published date:
1 January 1993
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(2019)4
The objective of the present report is to document a study that was performed on a set of common-cause failure (CCF) events. These events were derived from the International Common-cause Failure Data...
Published date:
21 August 2020
NEA/CSNI/R(2020)1
This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-Cause Failure Data Exchange (ICDE) project. The topic of the study was intersystem...
Published date:
21 June 2022
Published date:
3 November 2022
Published date:
3 November 2022
Published date:
19 February 1999
Published date:
1 January 1998
Published date:
19 November 1999
Published date:
2 March 2000
NEA/CSNI/R(2004)7
The overall objective of the international OECD programme SERENA is to obtain convergence on the understanding of fuel-coolant interaction (FCI) processes and energetics, as well as on method(s) for ...
Published date:
12 March 2004
NEA/CSNI/R(2010)8
An NEA specialists’ meeting “Identifying and Overcoming Barriers to Effective Consideration of Human and Organisational Factors in Event Analysis and Root Cause Analysis” was held in Paris, France on...
Published date:
8 March 2011
Published date:
1 January 1984
Published date:
15 February 2000
Published date:
1 January 1996
Published date:
25 June 2002
NEA/CSNI/R(2001)20
The reason for the meeting was that the CSNI felt it timely to “follow-up” on the past activities in the area of severe accident management implementation and to take stock of the progress made since...
Published date:
22 November 2001
NEA/CSNI/R(2010)10/VOL1
A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...
Published date:
3 December 2010
NEA/CSNI/R(2010)10/VOL2
A joint workshop of the Working Group on the Analysis and Management of Accidents (WGAMA) and the Working Group on Risk Assessment (WGRISK) on implementation of severe accident management (SAM) measu...
Published date:
3 December 2010
NEA/CSNI/R(2018)6
The Source Term Evaluation and Mitigation Project (STEM) project, hosted by the Nuclear Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of...
Published date:
17 March 2020
Published date:
20 September 2005
Published date:
20 September 2005
Published date:
21 September 2005
Published date:
1 January 1997
NEA/CSNI/R(2011)8
In December 2008, the Committee on the Safety of Nuclear Installations (CSNI) approved a proposal of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to conduct a round...
Published date:
19 January 2012
NEA/CSNI/R(2014)5/ADD1
A round robin exercise (RRE) on Improving the Robustness Assessments Methodologies for Structures Impacted by Missiles (IRIS-2012) was instituted jointly by IRSN, France and CNSC, Canada based on exp...
Published date:
30 June 2014
NEA/CSNI/R(2014)5
The Committee on the Safety of Nuclear Installations (CSNI) approved in December 2008 a proposal of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to conduct a round ...
Published date:
27 August 2014
Published date:
9 July 2001
NEA/CSNI/R(2010)11
Severe accident management guidelines (SAMGs) increase focus on containment integrity after some progression in the course of a severe accident. This change in priorities is made according to criteri...
Published date:
18 January 2011
Published date:
1 January 1994
Published date:
1 January 1995
Published date:
28 November 2000
Published date:
1 January 1991
Published date:
1 January 1990
NEA/CSNI/R(2017)16
This report by the Working Group on Analysis and Management of Accidents (WGAMA) summarises the first Nuclear Energy Agency (NEA) project to address the topic of severe accident management guidance (...
Published date:
2 July 2018
Published date:
15 February 2000
Published date:
1 January 1992
Published date:
23 December 1997
NEA/CSNI/R(2018)3
The Metallic Component Margins under High Seismic Loads (MECOS) Project is an international programme organised under an initiative of the NEA. The main objective of the MECOS Project is to quantify ...
Published date:
12 November 2018
NEA/CSNI/R(2015)8
Survey of Existing Practices and Status of Benchmark Work
NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current understandin...
Published date:
17 April 2015
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
NEA/CSNI/R(2004)9
The Committee on the Safety of Nuclear Installations (CSNI) workshop on “International Development and Co-operation on Risk-Informed In-Service (RI-ISI) and Non-destructive Testing (NDT) Qualificatio...
Published date:
14 February 2005
NEA/CSNI/R(2016)5
The workshop objectives relative to reviewing and discussing the state-of-the-art knowledge of iodine and ruthenium behaviour in NPP accidents gained through research projects and progress made in th...
Published date:
30 May 2016
Published date:
1 January 1991
Published date:
1 January 1997
NEA/CSNI/R(2021)9
This synthesis report summarises the technical programme and the outcome of the 2018 International Severe Accident Management Conference (ISAMC-2018) organised in Ottawa, Ontario on 15-18 October 201...
Published date:
11 December 2023
Published date:
1 January 1993
Published date:
1 January 1985
Published date:
1 January 1985
Published date:
1 January 1985
Published date:
1 January 1992
Published date:
1 January 1987
Published date:
1 July 2003
Published date:
1 January 1995
Published date:
1 January 1996
Published date:
16 December 2008
Published date:
29 November 1999
Published date:
29 November 1999
Published date:
1 January 1987
Published date:
1 January 1993
NEA/CSNI/R(2005)7
At the Committee on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia t...
Published date:
11 October 2005
NEA/CSNI/R(2005)5/VOL2
At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...
Published date:
6 September 2005
NEA/CSNI/R(2005)5/VOL3
At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...
Published date:
6 September 2005
NEA/CSNI/R(2004)11
At the Committe on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia te...
Published date:
20 July 2004
NEA/CSNI/R(2005)5/VOL1
At the Committee on the Safety of Nuclear Installations (CSNI) meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia...
Published date:
6 September 2005
NEA/CSNI/R(2012)6/VOL1
This report describes final prediction results by system analysis codes during the OECD/NEA ISP-50 exercise, targeting a 50% direct vessel injection (DVI) line break integral effect test performed wi...
Published date:
23 February 2012
NEA/CSNI/R(2012)6/VOL2
This report describes final prediction results by system analysis codes during the OECD/NEA ISP-50 exercise, targeting a 50% direct vessel injection (DVI) line break integral effect test performed wi...
Published date:
27 February 2012
NEA/CSNI/R(2012)6/VOL3
This report describes final prediction results by system analysis codes during the OECD/NEA ISP-50 exercise, targeting a 50% direct vessel injection (DVI) line break integral effect test performe...
Published date:
27 February 2012
Published date:
1 January 1988
Published date:
1 January 1989
Published date:
29 November 1999
NEA/CSNI/R(2007)10
The main objective of ISP-47 was to assess the capabilities of lumped parameter (LP) and computational fluid dynamics (CFD) codes in the area of containment thermal-hydraulics. Following the recommen...
Published date:
11 September 2007
Published date:
1 January 1994
Published date:
1 January 1997
Published date:
1 January 1995
Published date:
1 January 1990
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
NEA/CSNI/R(2015)12
On 28-30 April 2014, the CSNI Working Group on Risk Assessment (WGRISK) held a workshop on Fire Probabilistic Risk Assessment (PRA) in Garching, Germany. The meeting was attended by nearly 60 partici...
Published date:
1 November 2015
19 -
21 May 2015
Albuquerque, New Mexico, USA
The OECD Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Operational and Regulatory As...
Published date:
19 May 2015
3 -
4 October 2022
OECD Nuclear Energy Agency, 46 Quai Alphonse le Gallo, 92100 Boulogne-Billancourt
Published date:
3 November 2022
Published date:
1 January 1998
NEA/CSNI/R(2017)14
Fire hazards analyses (FHA) and probabilistic fire safety analyses (Fire PSA) have demonstrated that fire may be an important contributor to core damage frequency and other major plant damage states...
Published date:
11 January 2018
Published date:
1 January 1991
Published date:
15 February 2000
Published date:
7 April 2000
Published date:
14 September 1999
Published date:
1 January 1992
Published date:
12 August 1998
Published date:
1 January 1997
Published date:
1 January 1997
Published date:
16 February 1999
Published date:
5 February 2003
Published date:
11 February 2003
Published date:
5 February 2003
Published date:
18 November 2002
NEA/CSNI/R(2011)9
The main goal of the ISP-49 on Hydrogen Combustion is to identify the contemporary level of the numerical tools in the area of hydrogen combustion simulation under the conditions typical for safety c...
Published date:
18 January 2012
NEA/CNRA/R(2006)1
In 1998, the NEA Committee on Nuclear Regulatory Activities (CNRA) began an activity, the objective of which was to advance the discussion on how to enhance and measure regulatory effectiveness in re...
Published date:
1 March 2006
Published date:
7 October 2010
NEA/CNRA/R(2011)1
This Joint Strategic Plan for the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) takes into account the evolving statut of the nucle...
Published date:
7 October 2010
NEA/CSNI/R(2011)1/REV1
This Joint Strategic Plan for the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) takes into account the evolving status of the nucle...
Published date:
25 February 2013
Published date:
1 January 1997
Published date:
10 March 1999
7 -
9 June 2022
Liverpool, United Kingdom
The Symposium is free of charge for all participants and is scheduled to take place in person at the ONR’s offices near Liverpool in the United Kingdom.
Key Dates
31 March 2022 |
Deadline for a... |
Published date:
6 April 2022
Joint NEA-IAEA meeting on electrical power systems, 2‑5 December 2019
Published date:
5 December 2019
The joint NEA-IAEA symposium hosted by the United Kingdom’s Office for Nuclear Regulation brought together experts to exchange on the use and application of Probabilistic Safety Analysis (PSA) for re...
Published date:
14 June 2022
Published date:
1 January 1995
Published date:
1 January 1988
Published date:
29 November 1999
Published date:
1 January 1997
The NEA Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) held their biannual meetings from 6 to 9 December 2021 and discussed the evol...
Published date:
14 December 2021
Published date:
1 January 1995
Published date:
28 May 2002
Published date:
1 January 1997
CNRA/CSNI meetings, May-June 2021.
Published date:
10 June 2021
Published date:
1 January 1995
NEA/CSNI/R(2014)10
The impact of leaking fuel rods on the operation of nuclear power plants and the practices of handling leaking fuel has been reviewed by the CSNI Working Group on Fuel Safety (WGFS) in order to promo...
Published date:
18 July 2014
NEA/CSNI/R(2005)4
This document is the third in a series of the NEA’s Committee on the Safety of Nuclear Installations (CSNI) Working Group on Operating Experience (WGOE) technical notes on nuclear power plant (NPP) r...
Published date:
25 January 2005
Published date:
1 January 1996
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
Published date:
18 November 2002
Published date:
26 January 2022
NEA/CNRA/R(1997)2
Based on a request of Committees, an Organising Committee of Experts on sofware licensing issues was established to develop a state-of-the-art view of the technological problems and methods for ident...
Published date:
1 January 1997
Published date:
1 January 1977
Published date:
22 December 1995
As the Fukushima Daiichi nuclear power plant (NPP) accident illustrates, many challenges have to be faced in maintaining safety over the long term in a damaged NPP following a severe accident. These ...
Published date:
29 April 2021
JAEA High-temperature Engineering Test Reactor Photo: Japan Atomic Energy Agency (JAEA)
The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facil...
Published date:
19 March 2024
Published date:
1 January 1986
Published date:
29 November 1999
Published date:
23 December 2009
Published date:
1 January 1994
NEA/CSNI/R(2002)27
Volume 1 – Integral Experiments and Material Characterization
Published date:
28 May 2003
NEA/CSNI/R(2004)23
The focus of the Material Scaling (MASCA) Project was to investigate in detail the chemical behaviour of corium in contact with structural materials, with emphasis mainly on steel. This report provid...
Published date:
1 November 2004
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
Published date:
1 January 1993
Published date:
1 January 1994
Published date:
1 January 1978
Published date:
1 January 1976
Published date:
13 March 2001
Published date:
1 January 1997
Published date:
1 January 1997
NEA/CSNI/R(2017)19
The main objectives of the current activity are the promotion, test and evaluation of various methodologies for uncertainty quantification in computational fluid dynamics (UQCFD) for nuclear reactor...
Published date:
6 February 2019
NEA/CSNI/R(2018)12
Several NEA member countries have agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage multilateral co-operation in the collection and analy...
Published date:
4 April 2019
NEA/CSNI/R(2019)13
Since its inception in 2002, the operating experience with thermal fatigue mechanisms has been an intrinsic aspect of the technical scope of CODAP, which is a joint database project within the Commit...
Published date:
11 October 2022
NEA/CSNI/R(2019)7
Several Nuclear Energy Agency (NEA) member countries have agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage multilateral co-operation in...
Published date:
21 January 2019
25 -
28 May 2021
Videoconference, Zoom
In the aftermath of the Fukushima accident, the nuclear community has been re-evaluating seismic hazard at nuclear facilities worldwide. One of the major challenges in this effort is quantifying and ...
Published date:
1 December 2021
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
The NEA Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Nuclear Regulatory Activities (CNRA) convened on 4-8 December to discuss current activities and plan future body o...
Published date:
18 December 2023
NEA/CSNI/R(2022)3
The NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant addressing Emergency, Stabilisation and Long-term Reco...
Published date:
15 April 2024
Published date:
1 January 1991
Published date:
1 January 1985
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
Published date:
1 January 1994
NEA/CSNI/R(2014)1
This NEA WGIAGE workshop was held in Prague, Czech Republic on17-19 September 2013, with the objective to present and discuss the state-of-the-art techniques for the integrity assessment of concrete ...
Published date:
30 January 2015
Published date:
1 January 1994
Published date:
1 January 1989
Published date:
31 July 2001
NEA/CSNI/R(2010)7
The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing the current understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicabili...
Published date:
15 December 2010
Published date:
29 June 2009
NEA/CSNI/R(2009)15
The present report has been prepared by the Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Safety (WGFS) and covers the following technical aspects:
Published date:
1 January 2009
Published date:
24 March 2010
NEA/CSNI/R(2010)1
In 1986, a working group of the NEA Committee on the Safety of Nuclear Installations issued a state-of-the-art report on water reactor fuel behaviour in design-basis accident (DBA) conditions. The re...
Published date:
23 April 2010
Nuclear Fuel Cycle Facilities Safety Week
Published date:
7 November 2022
Published date:
14 September 2012
NEA/CSNI/R(2012)3
A set of fuel-related safety criteria was presented – along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them – in the...
Published date:
1 January 2012
NEA/CSNI/R(2019)2
In the face of severe accident scenarios with melted core material, such as those that occurred at Three Mile Island-2 in 1979 and at Fukushima Daiichi in 2011, the integrity assessment of primary ci...
Published date:
16 August 2019
NEA/CSNI/R(2019)2/ADD1
This is a companion document to the final report of the COSSAL project. It includes appendices which address participant responses to a questionnaire, the data of the problem statement on the large-s...
Published date:
16 August 2019
CNRA/CSNI meetings, December 2020
Published date:
7 December 2020
Major nuclear safety research facilities and programmes are facing increasing budgetary constraints, and in many cases are being closed or terminated. This report identifies major facilities of vital...
Published date:
20 April 2001
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
NEA/CSNI/R(2013)6
Due to the high safety significance and importance to nuclear regulators NEA Committee on the Safety of Nuclear Installations (CSNI) initiated in 2009 an international activity on high energy arcing ...
Published date:
25 June 2013
Published date:
1 January 1994
NEA/CSNI/R(2007)11
The Steam Explosion Resolution for Nuclear Applications (SERENA) programme stems from concerns expressed by the Senior Group of Experts on Nuclear Safety Research Facilities and Programmes (SESAR/FAP...
Published date:
17 September 2007
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(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
Published date:
6 June 2002
Published date:
9 September 2002
Published date:
7 February 2000
Published date:
1 January 1976
Published date:
6 December 1999
Published date:
2 February 2001
Published date:
25 April 2001
Published date:
22 May 2001
NEA/CSNI/R(2013)8/part1
The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...
Published date:
28 November 2013
NEA/CSNI/R(2013)8/PART2
The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...
Published date:
17 December 2013
NEA/CSNI/R(2013)8/PART3
The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...
Published date:
28 November 2013
NEA/CSNI/R(2013)8/PART4
The CSNI Working Group on Analysis and Management of Accidents (WGAMA) objective is to assess and where necessary strengthen the technical basis needed for the prevention, mitigation and management o...
Published date:
5 December 2013
Published date:
13 April 2000
NEA/CSNI/R(2011)11
A status report by the NEA’s Committee on the Safety of Nuclear Installations (CSNI) on iodine behaviour published in February 2007 concluded that although the understanding of iodine behaviour in co...
Published date:
11 January 2012
NEA/CSNI/R(2009)19
Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OPDE) to encourage multilateral co-operation in the collection and analysis of data relating to de...
Published date:
5 November 2009
NEA/CSNI/R(2012)14
A number of OECD member countries expressed their interest in participating in an OECD/NEA joint international research project on the topic of fire propagation. The PRISME project (PRISME is the Fre...
Published date:
6 July 2012
NEA/CSNI/R(2010)3
In June 2005, the Committee on the Safety of Nuclear Installations (CSNI) agreed to set up an expert meeting on the German proposal concerning the THAI Project. The objectives of the project were to ...
Published date:
22 June 2010
Published date:
16 December 1999
Published date:
17 May 2001
Published date:
30 September 2003
NEA/CSNI/R(2020)11
This report summarises the work done for the activity: “Benchmark analysis on the eXtended Finite Element Method (X-FEM) calculation technology in its use to evaluate the fracture mechanics stress in...
Published date:
6 October 2022
Published date:
1 January 1991
Published date:
1 January 1994
NEA/CSNI/R(1994)24/VOL II
Published date:
14 March 2008
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
NEA/CSNI/R(2012)5
The OECD/SETH-2 project was carried out during the period 2007-2010 under the auspices of the Nuclear Energy Agency (NEA) and with support provided by the Czech Republic, Finland, France, Germany, Ja...
Published date:
6 April 2012
Published date:
24 February 2003
Published date:
1 January 1997
NEA/CSNI/R(2018)2
Structural integrity of piping systems is important for safety and operability of nuclear plants. In recognition of this, information on degradation and failure of piping components and systems is co...
Published date:
24 May 2018
NEA/CSNI/R(2015)6
This Topical Report from the Component Operational Experience, Degradation and Ageing Programme (CODAP) addresses operating experience insights on two types of piping systems that have the following ...
Published date:
26 March 2015
NEA/CSNI/R(2017)3
This third topical report is concerned with the effectiveness of pressure boundary component reliability and integrity management (RIM). Specifically, this report addresses operating experience insig...
Published date:
15 January 2017
Published date:
10 August 2021
NEA/CSNI/R(2016)3
Criticality safety is an integral component of ensuring the continued safe operation of current reactor and fuel cycle facilities, as well as addressing new and interesting challenges that are expect...
Published date:
31 August 2016
NEA/CSNI/R(2012)13
Both regulators and the nuclear industry recognise the need for licensees to develop a strong, positive safety culture to support successful and sustainable nuclear safety performance. In recognition...
Published date:
27 June 2012
Published date:
1 January 1994
Published date:
23 December 2002
Published date:
1 January 1987
NEA/CSNI/R(2018)9
This report documents the proceedings of the Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors held in Lucca, Italy on 22-24 June 2016. The workshop was organised jointly by the ...
Published date:
11 June 2018
Published date:
12 October 1999
NEA/CSNI/R(2018)4
The objective of the CSNI ASCET activity is to make general recommendations for ageing management of concrete nuclear facilities taking into account the effect of concrete pathologies on structural d...
Published date:
21 January 2019
NEA/CSNI/R(2018)4/ADD1
Increasingly engineers are confronted with the need to perform predictive structural assessment based on limited or incomplete data set. This may include damage up to failure assessment (in the conte...
Published date:
1 January 2019
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
Published date:
31 March 1999
Published date:
1 January 1992
NEA/CSNI/R(2017)18
The main objective of the report is to identify research and development priorities related to loss-of-cooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proc...
Published date:
11 June 2018
Published date:
1 January 1993
Published date:
1 January 1976
Published date:
1 January 1993
NEA/CSNI/R(2014)14
The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...
Published date:
23 February 2015
NEA/CSNI/R(2016)18
PREMIUM is the follow-up of a series of projects promoted by NEA/CSNI and focused on the issue of best estimate plus uncertainty (BEPU) analysis of thermo-hydraulic accident scenarios in nuclear plan...
Published date:
24 August 2017
Published date:
16 December 2008
NEA/CSNI/R(2016)9
The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system ther...
Published date:
28 April 2016
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
Published date:
1 January 1986
NEA/CSNI/R(2019)15
The VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...
Published date:
27 September 2022
Prevention, mitigation and management of potential accidents in nuclear power plants
Published date:
5 October 2022
Published date:
1 January 1994
Published date:
23 December 1980