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...
26 January 2022
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 ...
29 April 2021
This present workshop was held in Zurich, Switzerland on 9-11 September 2014. It is the 5th workshop on Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS-5), in the biennial series of...
1 January 2016
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...
23 February 2015
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, ...
12 February 2015
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...
16 January 2015
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...
1 November 2014
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...
14 February 2014
11 April 2011
This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by Writing Group 3 on the extension of computational fluid dynamics (CFD) to two-phase flow safety problems. Writing Group ...
21 July 2010
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”,...
28 January 2008
The main objective of ISP-47 was to assess the capabilities of lumped parameter (LP) and computational fluid dynamics (CFD) codes in the area of containment thermal-hydraulics. Following the recommen...
11 September 2007
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...
23 February 2007
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...
1 January 2007
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) Programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
19 June 2006
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...
10 March 2005
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...
24 November 2004
The main objective of ISP exercises is to increase confidence in the validity and accuracy of the tools that are used in assessing the safety of nuclear installations. The secondary objective is to e...
1 November 2004
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...
9 March 2004
5 February 2003