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)3
Computational fluid dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coola...
Published date:
1 January 2007
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 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:
20 December 2023
In the framework of the WGAMA/WGFS activity "Status Report on Good Practices for Analyses of Design Extension Condition without Significant Fuel Degradation (DEC-A) for Operating Nuclear Power Plants...
Published date:
20 December 2023
Published date:
11 April 2011
NEA/CSNI/R(2013)12/add1
The document contains the appendices of an update of the 1995 state-of-the-art report (SOAR) “Knowledge Base for Emergency Core Cooling System Recirculation Reliability”. The content of the report go...
Published date:
19 December 2013
NEA/CSNI/R(2013)12
The current document is an update of the 1995 state-of-the-art report (SOAR) “Knowledge Base for Emergency Core Cooling System Recirculation Reliability”. The content of the present report goes beyon...
Published date:
20 December 2013
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
Supporting the use of computational fluid dynamics for nuclear reactor safety
Published date:
27 June 2023
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(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(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(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(2007)1
The OECD Nuclear Energy Agency has long recognised the importance of iodine behaviour and has organised workshops and international standard problems on the subject. In the meantime, experimental and...
Published date:
23 February 2007
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
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
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(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(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
NEA/CSNI/R(2005)1
The TMI-2 accident keeps providing unique full scale data giving opportunities to check the ability of the codes to model overall plant behaviour and to perform many sensitivity and uncertainty calcu...
Published date:
10 March 2005
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
NEA/CSNI/R(2011)14
The OECD Nuclear Energy Agency developed an initiative to form writing groups of experts with the specific task of assessing the maturity of computational fluid dynamics (CFD) codes for nuclear reaco...
Published date:
1 February 2012
Prevention, mitigation and management of potential accidents in nuclear power plants
Published date:
5 October 2022
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(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)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(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)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(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(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
The NEA Working Group on Analysis and Management of Accidents (WGAMA) organised a specialist workshop entitled “Reactor core and containment cooling systems: Long-term management and reliability (RCC...
Published date:
29 October 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(2011)9
The main goal of the ISP-49 on Hydrogen Combustion is to identify the contemporary level of the numerical tools in the area of hydrogen combustion simulation under the conditions typical for safety c...
Published date:
18 January 2012
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
Innovations in nuclear safety thermal-hydraulics
Published date:
26 June 2023
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(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(2001)20
The reason for the meeting was that the CSNI felt it timely to “follow-up” on the past activities in the area of severe accident management implementation and to take stock of the progress made since...
Published date:
22 November 2001
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(2009)12
Computational fluid dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coola...
Published date:
6 January 2010
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)6
The “Current Severe Accident Research Facilities and Projects” list was compiled by the Committee on the Safety of Nuclear Installations Working (CSNI) Group on the Analysis and Management of Acciden...
Published date:
9 March 2004
This Technical Opinion Paper (TOP) studies the emerging use of computational fluid dynamics (CFD) as an additional tool for the evaluation of safety cases implying thermal hydraulics. CFD allows a fi...
Published date:
11 March 2024