NEA/CSNI/R(2022)8
Several NEA member countries agreed to establish the Component Operational Experience, Degradation and Ageing Programme (CODAP) to encourage co-operation in the collection and analysis of data relati...
Published date:
13 March 2024
NEA/CSNI/R(2022)9
The objective of this study is to compare leak rate computation practices and the applied tools and software solutions. Leak rate prediction is an important aspect of the leak-beforebreak assessment,...
Published date:
13 March 2024
NEA/CSNI/R(2021)9
This synthesis report summarises the technical programme and the outcome of the 2018 International Severe Accident Management Conference (ISAMC-2018) organised in Ottawa, Ontario on 15-18 October 201...
Published date:
11 December 2023
NEA/CSNI/R(2020)12
As noted in the Joint CSNI/CNRA Strategic Plan and Mandates (NEA, 2019), the safe operation of current, new and advanced nuclear facilities is a key challenge for nuclear regulators and technical saf...
Published date:
11 December 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:
10 October 2023
The Nuclear Energy Agency (NEA) Working Group on the Analysis and Management of Accidents (WGAMA) aims to contribute to the assessment of the prevention, mitigation and management of accidents, ultim...
Published date:
5 October 2023
NEA/CSNI/R(2022)2
The eighth instalment of the workshop on computational fluid dynamics for nuclear reactor safety (CFD4NRS-8) was organised by the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Instal...
Published date:
28 August 2023
NEA/CSNI/R(2020)16
In the current project, a new systematic approach has been developed, called SAPIUM (systematic approach for input uncertainty quantification methodology) for transparent and rigorous model IUQ. This...
Published date:
30 May 2023
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
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
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(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)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 ...
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23 November 2022
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7 November 2022
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3 November 2022
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3 November 2022
NEA/CSNI/R(2020)7
The cold leg mixing computational fluid dynamics (CFD) – uncertainty quantification (CLM-UQ) benchmark is the fifth benchmark concerning CFD applications to nuclear reactor safety to be organised in ...
Published date:
3 November 2022
NEA/CSNI/R(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)13
Since its inception in 2002, the operating experience with thermal fatigue mechanisms has been an intrinsic aspect of the technical scope of CODAP, which is a joint database project within the Commit...
Published date:
11 October 2022
NEA/CSNI/R(2020)11
This report summarises the work done for the activity: “Benchmark analysis on the eXtended Finite Element Method (X-FEM) calculation technology in its use to evaluate the fracture mechanics stress in...
Published date:
6 October 2022
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
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)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(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...
Published date:
13 April 2022
Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...
Published date:
7 April 2022
NEA/CSNI/R(2021)6
Within the context of the Nuclear Energy Agency (NEA) Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) project, a series of tests were performed to resolve key thermal-hydraulic s...
Published date:
18 February 2022
NEA/CSNI/R(2020)3
When looking for a validation experiment for CFD application to reactor simulation for either design or safety studies, it appears that available data often suffer from a lack of local measurements, ...
Published date:
17 February 2022
Published date:
26 January 2022
NEA/CSNI/R(2007)2
Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios for nuclear power plants. The technic...
Published date:
26 January 2022
NEA/CSNI/R(2020)5
The Workshop on Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues, CFD4NRS-7 was the seventh in a series of workshops focusing on Computational Fluid Dyna...
Published date:
19 January 2022
NEA/CSNI/R(2007)18
The Committee on the Safety of Nuclear Installations (CSNI) Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components was held in Lyon, France on 25-27 S...
Published date:
20 December 2021
NEA/CSNI/R(2008)5
In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) issued a report titled Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR...
Published date:
20 December 2021
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25 November 2021
Published date:
10 August 2021
As the Fukushima Daiichi nuclear power plant (NPP) accident illustrates, many challenges have to be faced in maintaining safety over the long term in a damaged NPP following a severe accident. These ...
Published date:
29 April 2021
NEA/CSNI/R(2019)16
Two important lessons learnt from the March 2011 Fukushima Daiichi nuclear power plant (NPP) accident were: 1) there can be significant interactions between multiple co-located radiological sources (...
Published date:
19 April 2021
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:
3 November 2020
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(2018)14
Workshop Proceedings
21-23 March 2018, Paris, France
The WGEV “Riverine Flooding – Hazard Assessment and Protection of NPPs” task was designed to share regulatory practices and technical approaches fo...
Published date:
7 September 2020
NEA/CSNI/R(2019)4
The objective of the present report is to document a study that was performed on a set of common-cause failure (CCF) events. These events were derived from the International Common-cause Failure Data...
Published date:
21 August 2020
NEA/CSNI/R(2018)6
The Source Term Evaluation and Mitigation Project (STEM) project, hosted by the Nuclear Energy Agency (NEA) and operated by the Institut de Radioprotection et de Sûreté Nucléaire (French Institute of...
Published date:
17 March 2020
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(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)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(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
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(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