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...
31 December 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...
2 December 2004
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...
1 February 2005
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 (...
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...
9 June 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...
20 April 2007
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...
26 February 2009
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...
3 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...
11 December 2009
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...
15 May 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...
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...
17 May 2013
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...
27 May 2019
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...
26 September 2002
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, ...
21 September 2011
4 October 2022
OECD, Room BB 2, 46 Quai Alphonse le Gallo, 92100 Boulogne-Billancourt
The Working Group on Fuel Cycle Safety (WGFCS) of the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) will hold an international workshop on Process and Safety Imp...
24 June 2022
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...
24 June 2022
The Preparatory Study on Analysis of Fuel Debris (PreADES) project was proposed as a near-term project by the Senior Expert Group on Safety Research Opportunities Post-Fukushima (SAREF).
PreADES was ...
22 June 2022
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...
21 June 2022
CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.
10 June 2022
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...
14 June 2022
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...
19 May 2022
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...
6 December 2018
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...
19 February 2019
This is a summary report by the Hydrogen Mitigation Experiments for Reactor Safety (HYMERES) project on the PANDA and MISTRA experiments.
Phase 1 of the Project, between 2013 and 2016, focused on imp...
23 November 2018
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...
3 June 2019
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 ...
1 June 2007
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...
1 November 2004
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...
1 December 2004
The Committee on the Safety of Nuclear Installations (CSNI) workshop on “Seismic Input Motions Incorporating Recent Geological Studies” was held in Tsukuba, Japan on 15-17 November 2004, and was host...
14 February 2005
The Third International Conference on Fatigue of Reactor Components held in Seville, Spain on 3-6 October 2004 was co-organised by the EPRI, the US NRC and the OECD NEA Committee on the Safety of Nuc...
5 January 2005
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...
16 August 2019
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...
16 August 2019
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...
1 February 2015
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...
23 February 2015
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...
1 November 2014
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...
16 January 2015
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, ...
12 February 2015
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...
18 July 2014
At the 14th plenary meeting of the Working Group on Analysis and Management of Accidents (WGAMA), a proposal for a status paper on hydrogen generation, transport and mitigation under severe accident ...
20 January 2015
The main objectives of this status report on FCVSs in OECD countries, as defined by the Working Group on Analysis and Management of Accidents (WGAMA), were to: compile the status on the implementatio...
2 July 2014
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 ...
27 August 2014
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...
30 June 2014
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...
14 February 2014
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...
23 May 2014
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 ...
30 January 2015
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...
1 January 2016
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...
1 March 2015
In the light of the TEPCO Fukushima accident, this report documents a study performed on a set of common-cause failure (CCF) events due to external factors, meaning that not only storms and hurricane...
20 October 2015
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...
20 October 2015