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...

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...

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 ...

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...

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, ...

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...

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...

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...

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 ...

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”,...

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...

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...

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...

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...

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...

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...

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...

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...

Supporting files can be downloaded from www.oecd-nea.org/nsd/docs/2003/isp-42/