Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.
14-15 November 2000, Munich, Germany
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...
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....
Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...
Pipe Degradation & Failure as a Function of In-Service Time (Years) at the time of the OPDE project closure
The goals of the Piping Failure Data Exchange (OPDE) Project were to:
Several OECD member countries agreed to establish the OECD/NEA Piping Failure Data Exchange Project (OECD/NEA OPDE) to encourage multilateral co-operation in the collection and analysis of data relat...
New Joint Project: Studsvik Material Integrity Life Extension (SMILE)
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,...
The Material Scaling (MASCA) Project investigated in-vessel phenomena during a severe accident. In particular, it addressed the influence of the chemical composition of the molten corium on the heat ...
Volume 1 – Integral Experiments and Material Characterization
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...
This report documents a study performed on a set of common-cause failure (CCF) events of Emergency Diesel Generators (EDG) at nuclear power plants. In May 2000, the ICDE Project published a report su...
Project members held a meeting to discuss the activities.
The July 2006 Forsmark-1 event identified a number of design deficiencies related to electrical power supply to systems and components important to safety in nuclear power plants. The CSNI establishe...
In this document, the general coding guidelines for the OECD NEA ICDE Project (International Common Cause Failure Data Exchange) are presented with explanations and appendices for each analysed compo...