Fukushima Daiichi Nuclear Power Plant Accident: Message from Director-General Magwood
Published date:
11 March 2022
3 -
4 October 2022
OECD Nuclear Energy Agency, 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...
Published date:
24 June 2022
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:
10 August 2022
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:
10 August 2022
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:
6 October 2020
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:
11 October 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:
1 June 2017
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
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(2016)7
Operating experience from nuclear installations worldwide has shown that combinations of fires and other events, in particular external and internal hazards, occur throughout their entire lifetime. ...
Published date:
27 July 2016
NEA/CSNI/R(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 scenari...
Published date:
1 February 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 scenari...
Published date:
19 April 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:
30 May 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:
1 February 2016
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(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:
23 February 2016
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(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(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
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
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:
1 March 2018
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
NEA/CSNI/R(2017)13
The March 2011 accident at Fukushima Daiichi nuclear power plant triggered discussions about the natural external events that are low-frequency but high-consequence. In order to address these issues...
Published date:
16 April 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(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)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(2017)10
The workshop was held in Lucca, Italy on 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 s...
Published date:
31 January 2018
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:
11 April 2018
NEA/CSNI/R(2017)8
This report documents a study performed on a set of common-cause failure (CCF) events for diesel generators. The events were derived from the International CCF Data Exchange (ICDE) database and the s...
Published date:
24 August 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:
23 May 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:
17 January 2018
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:
19 January 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
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(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(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(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)5
This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...
Published date:
26 September 2018
NEA/CSNI/R(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
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:
2 August 2022
The new project assembled global experts at the NEA.
Published date:
25 July 2022
The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report
Published date:
8 July 2022
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:
20 July 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...
Published date:
19 July 2022
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 February 2021
Following the accident at the Fukushima Daiichi Nuclear Power Plant, many countries began funding research and development on nuclear fuel designs with enhanced accident tolerance (ATFs). ATFs have i...
Published date:
18 July 2022
Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority
The FACE proje...
Published date:
12 July 2022
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
The brochure provides background information about the NEA.
Published date:
10 September 2018
The NEA Framework for Irradiation Experiments (FIDES) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions and indust...
Published date:
28 June 2022
English