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
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:
27 September 2023
NEA Working Group on Analysis and Management of Accidents (WGAMA) initiated this activity focusing on computational fluid dynamics (CFD) in nuclear reactor safety (NRS).
Published date:
1 September 2023
The NEA Working Group on the Analysis and Management of Accidents convened for its annual meeting to discuss ongoing work related to accident strategy and management.
Published date:
14 September 2023
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
Experts attended NEA event in France.
Published date:
14 September 2023
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:
10 February 2022
One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, prim...
Published date:
14 September 2023
11 -
13 September 2023
IRSN, Fontenay-aux-Roses, France
Published date:
4 September 2023
The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.
Published date:
1 September 2023
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
TCOFF Phases
First Phase (2017-2020)
The Thermodynamic Characterisation of Fuel Debris and Fission Products ...
Published date:
31 August 2023
Scheme of the ROSA LSTF facility, JAEA
The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...
Published date:
31 August 2023
Irradiation Vessel with Coupons, CNL
The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment bui...
Published date:
31 August 2023
PANDA vessel assembly (construction phase, 1993), PSI.
The PANDA project is a follow-up of the HYMERES-2 project, and its general objective is to advance the knowledge on the containment of thermal...
Published date:
31 August 2023
Scheme of the DIVA Facility, IRSN
The Fire Risk Assessment through Innovative Research Project is a follow-up of the PRISME project series which addresses new fire scenarios and new topics of inter...
Published date:
31 August 2023
NEA/CSNI/R(2021)8
The objective of the NEA THAI-3 project was to address open questions concerning the behaviour of hydrogen, iodine and aerosols under severe accident conditions in the containment of water cooled rea...
Published date:
28 August 2023
In the wake of the THAI project, conducted in three phases from 2007 until 2019, a new project, "THAI Experiments on Mitigation measures, and source term issues to support analysis and further Improv...
Published date:
24 July 2023
The Working Group on the Analysis and Management of Accidents (WGAMA) focuses on the NEA activities related to potential design-basis and beyond design-basis accidents in nuclear reactors and related...
Published date:
21 July 2023
16 -
17 November 2023
US Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, MD 20852, United States
Deadline for submission of abstracts 31 July 2023 (extended)
Notification of accepted contributions 17 August 2023
Deadline for attendance registration 27 Oct 2023
Deadline for presentation submiss...
Published date:
3 July 2023
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
Published date:
30 September 2022
14 -
16 November 2023
Office for Nuclear Regulation, Merton Road, Bootle, Merseyside L20 7HS, United Kingdom
The workshop on the Approaches to design, implementation and operation of electrical systems for beyond design basis equipment and management of geomagnetically induced currents in electrical systems...
Published date:
22 June 2023
Supporting the use of computational fluid dynamics for nuclear reactor safety
Published date:
27 June 2023
Innovations in nuclear safety thermal-hydraulics
Published date:
26 June 2023
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
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
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
13 June 2023
The NEA Second Framework for Irradiation Experiments (FIDES-II) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions ...
Published date:
13 June 2023
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:
23 May 2023
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:
17 May 2023
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
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
Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.
Published date:
21 April 2023
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
Approximately 30 experts from WGAMA discussed how to advance the understanding of phenomena in pool in the situation of a loss of cooling accident.
Published date:
25 April 2023
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
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
The Expert Group on Small and Modular Reactors (EGSMR) continues to make progress with its forthcoming report
Published date:
8 July 2022
Left: Test facility for qualification of melt spreading tests. Photo: Argonne National Laboratory (ANL).
Right: Example of corium melt pouring for a melt spreading preparatory test. Photo: Argonne Nat...
Published date:
6 April 2023
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:
5 April 2023
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:
5 October 2022
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
NEA/CSNI/R(2020)10
Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...
Published date:
18 October 2022
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
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
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(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
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
Published date:
25 November 2022
The 9th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023.
Published date:
23 March 2023
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
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:
11 October 2022
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
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
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 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
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
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:
21 October 2022
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
Studsvik’s pool facility for storage and inspection of SMILE materials, left: 29 tonnes transportation flask, three pools each about 8 meters deep; and right: pool-in-pool for cutting and inspections...
Published date:
11 October 2022
Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority
The FACE projec...
Published date:
17 October 2022
Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...
Published date:
19 October 2022
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
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
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
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
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
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 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 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
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
Published date:
22 April 2020
HYMERES phases
First phase (2013-2016)
The main objective of the first phase of the Hydro...
Published date:
6 April 2020
The experimental investigations carried out in the frame of the THAI (2007-2009) and THAI-2 (2011-2014) projects contributed significantly to improve the understanding of hydrogen and fission-product...
Published date:
18 February 2022
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
Photo: RBHT Test Facility. US NRC.
Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...
Published date:
13 December 2022
PKL facility. Photo: FRAMATOME, Germany
The Experimental Thermal Hydraulics for Analysis, Research and Innovations in Nuclear Safety (ETHARINUS) project serves the objectives of investigating phenome...
Published date:
9 December 2022
PKL facility. Photo: FRAMATOME, Germany
The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...
Published date:
20 December 2022
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
Photos: SFP testing. Left: fuel assembly after a Zr fire; right: fire ignition test. SNL/USNRC.
The goal of the Sandia Fuel Project was to provide experimental data relevant for hydraulic and ignitio...
Published date:
9 December 2022
Left: Scheme of Studsvik LOCA test facility Right: Microstructure of fragmented nuclear fuel, Studsvik
Published date:
7 December 2022
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 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
The brochure provides background information about the NEA.
Published date:
10 September 2018
The OECD Nuclear Energy Agency (NEA) Strategic Plan serves as a guiding instrument that reflects the priorities of its member countries as the Agency addresses evolving needs in the exploration and a...
Published date:
25 January 2022
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
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
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
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
9 -
13 January 2023
Online
Since its inception, the NEA has provided a highly flexible and powerful platform for multinational research co-operation, particularly in areas related to providing understanding and insights needed...
Published date:
19 January 2023
Second Workshop on International Harvesting Co-operation focused on the status of aged metals harvesting and opportunities for international collaborative research.
Published date:
14 December 2022
Two new reports from the WGFS highlight the latest developments in RIA research.
Published date:
30 November 2022
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
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(2020)13
Since 2001, the NEA has supported the Senior Expert Group on Safety Research Thermal-hydraulics (SETH), the Primärkreislauf-Versuchsanlage - Primary Coolant Loop Test Facility (PKL), PKL-2 and PKL-3 ...
Published date:
23 November 2022
3 -
4 October 2022
OECD Nuclear Energy Agency, 46 Quai Alphonse le Gallo, 92100 Boulogne-Billancourt
Published date:
3 November 2022
Prevention, mitigation and management of potential accidents in nuclear power plants
Published date:
5 October 2022
As a follow-up to the 2010 NEA report Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions: State-of-the-art Report 2010, this report presents the state-of-the-art knowledge on...
Published date:
17 October 2022
CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.
Published date:
10 June 2022
Fukushima Daiichi Nuclear Power Plant Accident: Message from Director-General Magwood
Published date:
11 March 2022
The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialists’ meeting on transient thermal-hydraulics in water cooled nuclear reactors on 22-23 March 2022.
Published date:
6 April 2022
This report further explores some of the key elements presented in The Safety Culture of an Effective Regulatory Body (2016), commonly known as the NEA Green Booklet, and provides both an overview an...
Published date:
10 May 2021
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(2021)1
The Specialists Workshop on Advanced Instrumentation and Measurement Techniques for Experiments Related to Nuclear Reactor Thermal Hydraulics and Severe Accidents (SWINTH-2019), co-organised by the S...
Published date:
5 October 2022
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
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:
4 October 2022
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(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
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(2004)1
The present document is a summary record of an experts meeting held in Madrid, Spain on 18-19 November 2003. The purpose of the meeting was to determine the interest in member countries for the types...
Published date:
13 January 2004
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
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/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/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)7
The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing the understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicability to hi...
Published date:
18 November 2013
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
NEA/CSNI/R(2013)5
The OECD/NEA-KAERI MATiS-H benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict important turbulence parameters downstream of a generic ...
Published date:
15 July 2013
NEA/CSNI/R(2013)3
The first workshop on Seismic Observation in Deep Borehole and Its Applications (Kashiwazaki WS) was held as an embedded workshop in the First Kashiwazaki Symposium on Seismic Safety of Nuclear Insta...
Published date:
25 April 2013
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
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
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(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(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(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(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(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
NEA/CSNI/R(2015)4
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 (NPP) in July 2006 which caused t...
Published date:
12 March 2015
NEA/CSNI/R(2015)4/ADD1
This document contains Appendix 2 (cont'd) and Appendix 3 of the workshop on Robustness of Electrical Systems (ROBELSYS) of Nuclear Power Plants in Light of the Fukushima Daiichi Accident, held in Pa...
Published date:
12 March 2015
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
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:
4 May 2015
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(2016)19
One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are id...
Published date:
1 February 2017
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
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)16
Since the time of the first LOCA experiments, which were largely conducted with fresh fuel, changes in the fuel design, the introduction of new cladding materials and in particular the move to high b...
Published date:
10 October 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:
1 January 2017
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
NEA/CSNI/R(2016)12
Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel (PROSIR ) was a round robin exercise with the primary objective to issue some recommendations of best practices...
Published date:
1 December 2016
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)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
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
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
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
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
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
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(2018)11
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...
Published date:
23 November 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:
3 June 2019
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
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(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(2004)22
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...
Published date:
14 February 2005
NEA/CSNI/R(2004)21
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...
Published date:
5 January 2005
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
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(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(2014)13
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(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(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(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(2014)8
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 ...
Published date:
20 January 2015
NEA/CSNI/R(2014)7
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...
Published date:
2 July 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
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)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/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
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
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(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
NEA/CSNI/R(2015)17
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...
Published date:
20 October 2015
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
NEA/CSNI/R(2015)15
This workshop, held in Pavia, Italy on 4-6 February 2015, was the fourth in a series of NEA meetings (Tokyo, Japan, August 1999, Jeju, Korea, November 2006, Lyon, France, April 2008), dedicated to pr...
Published date:
7 September 2015
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
NEA/CSNI/R(2015)13
This report was written by members of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) of the NEA, and the members of the metal subgroup were responsible for developing...
Published date:
22 December 2015
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)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
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
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
NEA/CSNI/R(2011)3
In 1998, the Committee on Nuclear Regulatory Activities (CNRA) issued a report on future nuclear regulatory challenges which discussed the potential erosion of safety margins as an area for further r...
Published date:
30 November 2011
NEA/CSNI/R(2011)5
The OECD/NEA-Vattenfall T-Junction Benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict the important parameters affecting high-cycle th...
Published date:
12 May 2011
NEA/CSNI/R(2010)15
Two subjects – stress corrosion cracking (SCC) and degradation of cable insulation – were selected as the focus of the SCC and Cable Ageing Project (SCAP) due to their relevance for plant ageing asse...
Published date:
13 April 2011
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
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(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
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(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)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
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
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(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(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(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
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(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(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
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21 April 2022
Zoom - REGISTRATION CLOSED
To meet the overall safety objectives and to achieve a balanced plant design, natural hazards have to be considered in the design of nuclear installations. Deriving the strength of such events from a...
Published date:
15 April 2022
NEA/CSNI/R(2020)4
The investigation conducted in the last 15 years on different aspects of Source Term worldwide, and particularly in the context of the Nuclear Energy Agency (NEA) in the form of projects and the Work...
Published date:
14 April 2022
One of the key areas in fuel safety is the analysis of fuel behaviour under reactivity-initiated accident conditions. Reactivity-initiated accident fuel rod codes have been developed for a significan...