This publication addresses trends and patterns in material degradation as a function of nuclear power plant ageing, which is a key topic in the regulation of ageing management programmes, codes and s...
Published date:
22 April 2024
NEA/CSNI/R(2023)2
This report provides the results of the fluid structure interaction (FSI) benchmark, which was developed and performed by the designer and engineering company OKBM as part of NEA and ROSATOM activiti...
Published date:
24 April 2024
NEA/CSNI/R(2022)3
The NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for Enhancing Severe Accident Management in a Nuclear Power Plant addressing Emergency, Stabilisation and Long-term Reco...
Published date:
15 April 2024
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
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(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
NEA/CSNI/R(2014)13/REV1
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(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)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(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)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(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)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(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)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
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3 November 2022
Published date:
3 November 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
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(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(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
Published date:
7 November 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(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