Image: QUENCH facility at KIT. Court. KIT.
The purpose of the QUENCH-ATF project is to investigate the chemical, mechanical and thermal-hydraulics behaviour of ATF claddings in Design Basis Accident...
Published date:
24 August 2020
NEA/CSNI/R(2019)10
This report provides descriptions of the current status of PSA programmes in member countries; including basic background information, guidelines, various PSA applications, major results in recent st...
Published date:
15 September 2020
NEA/CSNI/R(2007)2
Aix-en-Provence, 7-9 November 2005
Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios fo...
Published date:
26 February 2007
The Preparatory Study on Analysis of Fuel Debris (PreADES) project and the Analysis of information from Reactor buildings and Containment vessels of Fukushima Daiichi Nuclear Power Station (ARC-F) pr...
Published date:
7 April 2020
14 -
18 December 2020
Zoom webinar
The OECD Nuclear Energy Agency (NEA) in collaboration with the Canadian Nuclear Safety Commission (CNSC) hosted an international, multi-sector workshop on 14-18 December 2020 on safely regulating inn...
Published date:
5 January 2021
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:
30 September 2020
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
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
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
Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant
Published date:
17 December 2020
The Halden Reactor Project has been in operation since 1958 and is the oldest NEA joint project. It brings together an important international technical network in the area of nuclear safety ranging ...
Published date:
6 April 2020
CNRA/CSNI meetings, December 2020
Published date:
7 December 2020
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
Accident analysis and management focusses on understanding the causes and consequences of an accident at a nuclear facility, and on how to manage an accident through prevention and mitigation.
Published date:
17 March 2020
Published date:
30 November 2020
The Working Group on the Analysis and Management of Accidents (WGAMA) is responsible for activities related to potential accidental situations in nuclear power plants, including the following technic...
Published date:
19 November 2020
CANDU Owners Group (COG) and the NEA have signed a Memorandum of Understanding to co-operate in research and activities related to pressurised heavy water reactor (PHWR) technology.
Published date:
30 September 2020
Published date:
4 November 2020
Disruptive technologies for nuclear safety applications
Published date:
13 August 2020
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:
21 October 2020
Nuclear safety can be understood as accident prevention in nuclear installations, via its systems and its human resources, and the mitigation of risks and consequences if an accident should occur.
Published date:
29 January 2020
Nuclear facilities rely on a robust electrical system to power primary and back-up systems required to safely respond to a wide variety of challenging events.
Published date:
17 March 2020
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
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
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
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
Virtual kick-off meeting for the new joint project Experiments on Source Term for Delayed Releases (ESTER), 28-30 September 2020.
Published date:
9 October 2020
NEA Working Group on External Events (WGEV) meeting, 14-18 September 2020.
Published date:
9 October 2020
Published date:
2 April 2020
Common-cause failure (CCF) events can significantly affect the availability of nuclear power plant safety systems. In recognition of this, CCF data is systematically collected and analysed in several...
Published date:
7 April 2020
The main purpose of the project is to encourage multilateral co-operation in the collection and analysis of data relating to fire events. The objectives of the NEA Fire Project are to:
Published date:
3 April 2020
Published date:
2 April 2020
NEA/CSNI/R(2015)4
ROBELSYS Workshop Proceedings
The Defence in Depth of Electrical Systems (DIDELSYS) Project (2008-2011) was launched after a switchyard-induced voltage surge event at Forsmark Nuclear Power Plant (NP...
Published date:
26 January 2015
NEA/CSNI/R(2015)4/ADD
ROBELSYS Workshop Proceedings
Appendix 2 (Cont’d) and Appendix 3
Published date:
26 January 2015
NEA/CSNI/R(2016)17/ADD2
Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015
Appendix C:
Speaker Presentations: Abstracts/Texts and Graphics
Published date:
14 June 2017
NEA/CSNI/R(2016)17/ADD1
Proceedings of the Expert Workshop Charlotte, United States 19-21 February 2015
The word validation has many different meanings depending on the context where it applies. In a general way validation ...
Published date:
14 June 2017
NEA/CSNI/R(2016)3
OECD/CSNI Workshop Proceedings
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 intere...
Published date:
12 January 2016
NEA/CSNI/R(2017)20
Workshop Proceedings 13-15 September 2016 Cambridge USA
The present report summarises the 6th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6) in the bienn...
Published date:
3 September 2018
NEA/CSNI/R(2017)13
Workshop Proceedings -Working Group on External Events (WGEV)
Paris, France, 24-26 February 2016
The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natur...
Published date:
11 July 2017
NEA/CSNI/R(2017)12
CSNI Workshop Proceedings
Aomori City, Japan, 15-17 November 2016
The main objective of the workshop was to review and discuss national activities, plans and regulatory approaches by member countrie...
Published date:
4 July 2017
NEA/CSNI/R(2017)12/ADD1
Aomori City, Japan
15-17 November 2016
On March 11, 2011, the Tohoku–Taiheiyou–Oki earthquake occurred near the east coast of Honshu, Japan. This magnitude 9.0 earthquake and the subsequent tsunami c...
Published date:
8 January 2018
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:
10 July 2017
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:
19 December 2016
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
NEA/CSNI/R(2019)9
Chemical hazards are an important subject for Fuel Cycle facilities, including various chemical processes and substances such as explosions and healthy risks. On 17-18 April 2018, the Nuclear Energy ...
Published date:
12 March 2019
NEA/CSNI/R(2019)9/ADD1
Appendix C
The non-radiological risks involving dangerous chemicals in nuclear fuel cycle facilities,French framework regulation -
Accidents involving hazardous chemicals pose a significant threat to...
Published date:
12 June 2019
NEA/CSNI/R(2001)8
Published date:
10 April 2001
NEA/CNRA/R(1996)1
An International Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, sponsored by the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Inst...
Published date:
1 January 1996
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:
8 September 2009
NEA/CNRA/R(2005)2
In some countries, there is a growing demand for information about NPP performance from the executives, public and media. Such a demand has to be responded to and the information provided need to be ...
Published date:
11 May 2005
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...
Published date:
29 June 2004
17 -
19 April 2018
Boulogne-Billancourt, France
The workshop was hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)
General information
The Nuclear Energy Agency (NEA) Commit...
Published date:
6 February 2020
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 Project (SCAP). The project ran f...
Published date:
17 April 2020
SCIP phases
First phase (2004-2009)
Phase on...
Published date:
14 April 2020
STEM phases
First phase (2011-2015)
The STEM Project was initiated with a first phase in 2011 to improve the general ...
Published date:
8 April 2020
The experimental investigations carried out in the frame of the THAI (2007-09) and THAI-2 (2011-14) projects contributed significantly to hydrogen and fission-product-related issues in a water-cooled...
Published date:
15 April 2020
The acronym PRISME comes from the French phrase propagation d’un incendie pour des scénarios multi-locaux élémentaires, which in English can be translated as "fire propagation in elementary, multi-ro...
Published date:
3 April 2020
The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...
Published date:
7 April 2020
The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...
Published date:
2 April 2020
HYMERES phases
First phase (2013-2016)
The main objective of the first phase of the Hydro...
Published date:
6 April 2020
During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...
Published date:
20 April 2020
The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...
Published date:
20 April 2020
The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japanese rig-of-safety assessment/large-scale...
Published date:
8 April 2020
Published date:
22 April 2020
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 monitoring and assessment s...
Published date:
22 April 2020
In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...
Published date:
22 April 2020
The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...
Published date:
22 April 2020
The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:
- simulate reflood scenarios in a prototypical PWR rod bundle s...
Published date:
8 April 2020
The goal of the Reduction of Severe Accident Uncertainties (ROSAU) Project is to reduce knowledge gaps and uncertainties associated with severe accident progression by performing large-scale tests in...
Published date:
8 April 2020
The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility (PKL)) is a facility is owned and operated by Framatome GmbH (formerly AREVA NP) in Erlangen, Germany to perform experiments on ...
Published date:
8 April 2020
The Cabri International Project (CIP) began in March 2000 to study the behaviour of fuel rods, specifically cladding, during a reactivity-initiated accident (RIA) in a pressurised-water reactor (PWR)...
Published date:
2 April 2020
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 extent different from the ana...
Published date:
22 April 2020
The Loss-of-fluid Test (LOFT) Research Programme was originally set up by the US Nuclear Regulatory Commission. Part of the programme was later broadened into an international collaboration project u...
Published date:
22 April 2020
On 28 March 1979, a partial meltdown of the Three Mile Island unit 2 (TMI-2) reactor occurred at the TMI nuclear power plant near Harrisburg, Pennsylvania, United States.
A TMI accident evaluation pr...
Published date:
20 April 2020
The HEAF Project was planned as a three-year programme to be conducted by the United States Nuclear Regulatory Commission (NRC) at a facility in the US. The project's aim was to conduct experiments i...
Published date:
6 April 2020
The TCOFF project provides a framework for the exchange of technical information on topics related to thermodynamic databases available for modelling the fuel/core degradation process, which include ...
Published date:
16 April 2020
NEA Committee on the Safety of Nuclear Installations (CSNI) meeting, 4‑5 December 2019.
Published date:
6 December 2019
Advanced instrumentation for nuclear reactor thermal hydraulics experiments
Published date:
18 November 2019
Joint NEA-IAEA meeting on electrical power systems, 2‑5 December 2019
Published date:
5 December 2019
Fukushima Daiichi nuclear safety research projects
Published date:
4 March 2020
CSNI Programme Review Group (PRG) annual review meeting, 27‑28 April 2020.
Published date:
5 May 2020
The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.
Published date:
29 February 2016
NEA Working Group on the Safety of Advanced Reactors (WGSAR) meeting, 23 June 2020.
Published date:
1 July 2020
NEA Committee on the Safety of Nuclear Installations (CSNI) meeting, 4‑5 June 2020.
Published date:
1 July 2020
Published date:
4 October 2017
Published date:
13 June 2017
The OECD Nuclear Energy Agency (NEA) has just published a new report entitled Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt.
Published date:
29 February 2016
NEA/CSNI/R(2000)23
14-15 November 2000, Munich, Germany
Published date:
13 December 2000
Published date:
5 February 2001
NEA/CSNI/R(2001)4
A Report by the OECD Support Group on the VVER Thermal-Hydraulic Code Validation Matrix (2001)
Published date:
16 February 2001
NEA/CSNI/R(2003)12
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Published date:
31 March 2003
NEA/CSNI/R(2005)1
Published date:
4 January 2005
NEA/CSNI/R(2007)6
Published date:
19 March 2007
NEA/CSNI/R(2009)3
Published date:
9 February 2009
NEA/CSNI(1990)181
Published date:
7 May 2010
NEA/SEN/SIN/AMA/A(2011)3
Published date:
11 April 2011
NEA/CSNI/R(2015)9
This report has been written in the framework of seismic subgroup of the OECD/NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to provide a brief review of current...
Published date:
26 February 2015
NEA/CSNI/R(2015)8
Survey of Existing Practices and Status of Benchmark Work
OECD/NEA/CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current underst...
Published date:
20 February 2015
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 ...
Published date:
3 February 2015
NEA/CSNI/R(2015)6
A Topical Report from the Component Operational Experience, Degradation and Ageing Programme
This, the second CODAP Topical Report addresses operating experience insights on two types of piping syste...
Published date:
3 February 2015
NEA/CSNI/R(2015)5
OECD/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...
Published date:
28 January 2015
NEA/CSNI/R(2015)3
Based on the conclusions of the previous benchmark exercise [1], the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by exam...
Published date:
23 January 2015
NEA/CSNI/R(2015)2
Spent fuel pools (SFPs) are large accident-hardened structures that are used to temporarily store irradiated nuclear fuel. Due to the robustness of the structures, SFP severe accidents have long been...
Published date:
23 January 2015
NEA/CSNI/R(2015)1
Joint CSNI WGHOF/WGRISK report
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)....
Published date:
23 January 2015
The brochure provides background information about the NEA.
Published date:
10 September 2018
NEA/CSNI/R(2016)19
Japan earthquake on 11 March 2011 is to ensure that knowledge gaps in nuclear safety are identified and consequently, corresponding research programmes to address these gaps are being instituted.
Fol...
Published date:
24 November 2016
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:
16 September 2016
The NEA Annual Report 2019 provides an overview of the status of nuclear power in NEA member countries and illustrative descriptions of the Agency's activities and international joint projects. 2019 ...
Published date:
12 June 2020
NEA/CSNI/R(2016)16
Published date:
21 June 2016
NEA/CSNI/R(2016)15
Since 2002, the Nuclear Energy Agency (NEA) has sponsored the Melt Coolability and Concrete Interaction (MCCI) co-operative project in two phases in order to investigate ex-vessel melt coolability an...
Published date:
20 June 2016
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:
20 June 2016
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), ...
Published date:
14 June 2016
NEA/CSNI/R(2016)13/ADD1
Taking into account life extension of Nuclear Power Plants (NPPs) there is a need to investigate degradations mechanisms of existing structures defining their aging management program. The Alkali Ag...
Published date:
3 July 2017
NEA/CSNI/R(2016)12
PROSIR - Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel, was a round robin exercise with the primary objective to issue some recommendations of best practice...
Published date:
14 June 2016
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:
18 April 2016
NEA/CSNI/R(2016)11
This report summarises the responses provided by the member organisations of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the Committee on the Safety of Nuclear...
Published date:
14 June 2016
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 the...
Published date:
10 March 2016
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:
16 April 2020
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:
3 February 2016
NEA/CSNI/R(2016)7
The Fire Incidents Records Exchange Project
Topical Report No. 3
Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular externa...
Published date:
3 February 2016
NEA/CSNI/R(2016)6/VOL2
Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenar...
Published date:
29 January 2016
NEA/CSNI/R(2016)6/VOL1
Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenar...
Published date:
3 February 2016
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:
21 January 2016
NEA/CSNI/R(2016)4
Single-phase Computational Fluid Dynamics (CFD) is used more and more for design and safety issues related to Light-Water Reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...
Published date:
19 January 2016
NEA/CSNI/R(2016)2
The OECD Nuclear Energy Agency-Paul Scherrer Institut (NEA-PSI) Benchmark was initiated to test the capability of state-of-the-art Computational Fluid Dynamics (CFD) and dedicated containment codes ...
Published date:
8 January 2016
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:
19 December 2017
NEA/CSNI/R(2017)18
The main objective of the report is to identify research and development priorities related to loss-ofcooling and loss-of-coolant accidents in spent fuel pools. This is done by applying a PIRT proce...
Published date:
8 December 2017
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:
5 October 2017
NEA/CSNI/R(2017)15
The Status Report on Ex-Vessel Steam Explosion (EVSE) summarises the significant progress made in the field of Fuel Coolant Interaction/Steam Explosion (FCI/SE) knowledge during these last ten years...
Published date:
17 August 2017
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:
2 August 2017
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
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:
3 July 2017
NEA/CSNI/R(2017)10
Lucca, Italy 13-15 April 2016
The PKL3 Project tests consisted of a programme of experiments intended to, inter alia, understand complex heat transfer mechanisms in the steam generators and the cours...
Published date:
3 July 2017
NEA/CSNI/R(2017)9
The NEA Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) Project is one of the NEA supported joint projects under the auspices and with the support of the NEA. It started from Apr...
Published date:
3 July 2017
NEA/CSNI/R(2017)8
International Common-Cause Failure Data Exchange (ICDE) Project Report
This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were der...
Published date:
27 February 2017
NEA/CSNI/R(2017)7
This report documents an experimental programme designed to investigate the High Energy Arcing Fault (HEAF) phenomena. The most recent international nuclear power plant (NPP) operating experience wi...
Published date:
16 February 2017
NEA/CSNI/R(2017)6
For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...
Published date:
14 February 2017
NEA/CSNI/R(2017)5
The main objective of the Working Group on Risk Assessment (WGRISK) is to advance Probabilistic Safety Assessment (PSA) understanding and to enhance its use for improving the safety of nuclear instal...
Published date:
14 February 2017
NEA/CSNI/R(2017)4
Management of spent fuel (SF) and high-level waste (HLW) is fundamental to the fuel cycle safety. The original management strategies were established on the basis of limited interim storage periods o...
Published date:
17 January 2017
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:
9 January 2017
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:
30 January 2018
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:
19 February 2018
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:
30 August 2018
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:
19 February 2018
NEA/CSNI/R(2018)1
The mission of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Risk Assessment (WGRISK) is to advance understanding of probabilistic safety as...
Published date:
11 January 2018
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:
19 February 2018
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:
11 May 2018
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:
8 June 2018
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:
26 June 2018
NEA/CSNI/R(2018)11
Resolving Complex Safety Relevant Issues Related to Hydrogen Release in Nuclear Power Plant Containments During a Postulated Severe Accident
Phase 1 of the Project, between 2013 and 2016, focused on ...
Published date:
31 July 2018
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:
22 August 2018
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:
17 January 2019
NEA/CSNI/R(2019)2/ADD1
Components and Structures under Severe Accident Loading (COSSAL) Final Report (Appendices)
Questions and Answers
Published date:
5 April 2019
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:
17 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
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
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
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
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(2001)10
Published date:
26 April 2001
NEA/CSNI/R(2002)19
Published date:
15 July 2002
NEA/CSNI/R(2008)1
Published date:
21 January 2008
NEA/CSNI/R(2015)11
Published date:
9 June 2015
NEA/CSNI/R(1999)2
Published date:
16 February 1999
NEA/CSNI/R(2000)20
Published date:
23 August 2000
NEA/CSNI/R(2003)15
Published date:
11 July 2003
NEA/CSNI/R(2013)4
Published date:
18 March 2013
NEA/CSNI/R(2008)8
Published date:
16 June 2008
NEA/CSNI/R(2003)19
Published date:
28 November 2003
NEA/CSNI/R(2004)4
Published date:
21 January 2004
NEA/CSNI/R(2013)2
Published date:
7 February 2013
NEA/CSNI/R(2015)17
Published date:
29 September 2015
NEA/CSNI/R(2011)12
Published date:
1 February 2012
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 Nuclear Energy Agency (NEA) of Organisation for Economic Cooperation and ...
Published date:
25 November 2014
NEA/CSNI/R(2016)17
The theme of this workshop was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Power Plants”, with three high level objectives:
Published date:
27 June 2016
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:
30 July 2013
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/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
NEA/CNRA/R(2005)3
In some countries, there is a growing demand for information about NPP performance from the executives, public and media. Such a demand has to be responded to and the information provided need to be ...
Published date:
27 May 2005
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
NEA/CNRA/R(2014)4
An international Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Light of the Fukushima Daiichi Accident was jointly organised by the NEA Committee on Nuclear Regulatory Activiti...
Published date:
22 May 2014
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
The Working Group supports improved uses of Probabilistic Safety Assessment (PSA) in risk-informed regulation and safety management through the analysis of results and the development of perspectives...
Published date:
16 April 2020
The objective of the Working Group on Fuel Cycle Safety (WGFCS) is to advance the understanding of relevant aspects of nuclear fuel cycle safety, including: uranium mining and milling; uranium refini...
Published date:
15 April 2020
The main mission of the Working Group on Fuel Safety (WGFS) is to advance the current understanding and address cross-cutting issues related to fuel behaviour in accident conditions, including work o...
Published date:
14 April 2020
The main mission of the Working Group on External Events (WGEV) is to improve the understanding and treatment of external hazards that would support the continued safety performance of nuclear instal...
Published date:
14 April 2020
The main mission of the Working Group on the Safety of Electrical Systems (WGELEC) is to advance the current understanding and address safety issues related to electrical systems of nuclear installat...
Published date:
14 April 2020
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:
3 April 2020
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
Published date:
22 April 2020
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
A Task Group on the Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident (ROBELSYS) had been set up to improve the understanding of nuclear power plant electrical syste...
Published date:
22 April 2020
The Task Group on Sump Clogging had been set up to update the State-of-the-art Report (SOAR) on Knowledge Base for Emergency Core Cooling System Recirculation Reliability issued in 1996, and with foc...
Published date:
28 April 2020
15 -
18 November 2016
Aomori City, Japan
The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) Working Group on Fuel Cycle Safety (WGFCS) held an international workshop on Developments in Fuel Cycle Facilit...
Published date:
4 May 2020
10 -
11 May 2011
OECD Conference Centre, Paris, France
The July 2006 Forsmark-1 event identified a number of design deficiencies related to electrical power supply to systems and components important to safety in nuclear power plants. The CSNI establishe...
Published date:
4 May 2020
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
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:
22 April 2020
This working group's objective was to advance the current understanding and to address safety issues related to fuel safety margins, in particular to systematically assess the technical basis for cur...
Published date:
29 April 2020
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
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
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 Strategic Plan is intended to guide the NEA as it seeks to meet the evolving needs of member countries in the application and exploration of nuclear science and technology. The plan includes an ...
Published date:
22 December 2016
There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine. VVER-440/213 pressurised water reactors (PWRs) have a pressure...
Published date:
22 April 2020
Lyon, France, 8-10 September 1997
Published date:
1 January 1997
Published date:
1 January 1998
NEA/CSNI(1987)132
Published date:
1 January 1987
NEA/CSNI/R(2007)15
Report on the Material Scaling (MASCA) Project, 2000-2007
Published date:
8 November 2007
During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subjected to significant thermal and pressure loads. The lower head has the potential to fail, releasing large amoun...
Published date:
21 April 2020
The goal of the project was to provide experimental data relevant for hydraulic and ignition phenomena of prototypic water reactor fuel assemblies. The intended scope of work was defined in an expert...
Published date:
21 April 2020
Published date:
1 January 1991
NEA/CSNI/R(1992)9/VOL2
Published date:
17 August 2006
Three Mile Island Unit 2 Analysis Exercise Final Report
Published date:
1 January 1991
NEA/CSNI/R(2002)27
Volume 1 – Integral Experiments and Material Characterization
Published date:
28 May 2003
The goals of the Piping Failure Data Exchange (OPDE) Project were to:
- collect and analyse piping failure event data to promote a better understanding of underlying causes, impact on operations and s...
Published date:
17 April 2020
Paper about the Stress Corrosion Cracking and Cable Ageing Project (SCAP)
Published date:
17 April 2020
Published date:
5 November 2015
English