This document is Appendix B of the Proceedings of the Expert Workshop on Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications, held in Charlotte, United States on 19...

Survey of Existing Practices and Status of Benchmark Work

NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current understandin...

NEA CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE) has the main mission to advance the current understanding of those aspects relevant to ensuring the integrity of s...

The Defence in Depth of Electrical Systems (DIDELSYS) Project (2008-2011) was launched after a switchyard-induced voltage surge event at Forsmark nuclear power plant (NPP) in July 2006 which caused t...

This document contains Appendix 2 (cont'd) and Appendix 3 of the workshop on Robustness of Electrical Systems (ROBELSYS) of Nuclear Power Plants in Light of the Fukushima Daiichi Accident, held in Pa...

Based on the conclusions of the previous benchmark exercise, the NEA Working Group on Analysis and Management of Accidents (WGAMA) felt it worthwhile to extend the accident analysis scope by examinin...

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...

The work described in this report was conducted as a joint task under the CSNI Working Groups on Human and Organisational Factors (WGHOF) and Risk Assessment (WGRISK). The task has two primary purpos...

One of the imperatives following the accident at the Fukushima Daiichi nuclear power station is for the nuclear science and industry communities to ensure that knowledge gaps in nuclear safety are id...

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...

The theme of this workshop, held in Charlotte, United States on 19-21 February 2015, was “Establishing Reasonable Confidence in the Human Factors Validation of Main Control Room Systems of Nuclear Po...

Since the time of the first LOCA experiments, which were largely conducted with fresh fuel, changes in the fuel design, the introduction of new cladding materials and in particular the move to high b...

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...

The present document deals with scaling in nuclear-system thermal hydraulics (SYS TH), including the connection with nuclear-reactor safety technology (NST). Scaling has constituted “an issue” since ...

Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressure Vessel (PROSIR ) was a round robin exercise with the primary objective to issue some recommendations of best practices...

Chemical hazards are an important subject for Fuel Cycle facilities, including various chemical processes and substances such as explosions and healthy risks. On 17-18 April 2018, the Nuclear Energy ...

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...

The overall objective of the THAI-2 project is to address open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during design-basis or s...