The VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...
The Working Group supports improved uses of Probabilistic Safety Assessment (PSA) in risk-informed regulation and safety management through the analysis of results and the development of perspectives...
The Programme Review Group is established to perform a programme quality review function within the Committee on the Safety of Nuclear Installations (CSNI) and to provide scientific assistance to the...
This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-Cause Failure Data Exchange (ICDE) project. The topic of the study was intersystem...
The joint NEA-IAEA symposium hosted by the United Kingdom’s Office for Nuclear Regulation brought together experts to exchange on the use and application of Probabilistic Safety Analysis (PSA) for re...
CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.
The Symposium is free of charge for all participants and is scheduled to take place in person at the ONR’s offices near Liverpool in the United Kingdom.
Joint NEA and IAEA event will explore probabilistic safety assessment for reactors of singular designs
To meet the overall safety objectives and to achieve a balanced plant design, natural hazards have to be considered in the design of nuclear installations. Deriving the strength of such events from a...
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...
One of the key areas in fuel safety is the analysis of fuel behaviour under reactivity-initiated accident conditions. Reactivity-initiated accident fuel rod codes have been developed for a significan...
Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...
After the Fukushima nuclear accident, many activities were initiated in the countries with nuclear energy to assess the robustness of nuclear power plants with respect to earthquakes, tsunamis and fl...
Within the context of the Nuclear Energy Agency (NEA) Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) project, a series of tests were performed to resolve key thermal-hydraulic s...
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, ...
The main mission of the Working Group on External Events (WGEV) is to improve the understanding and treatment of external hazards that would support the continued safety performance of nuclear instal...
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...
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...
The Committee on the Safety of Nuclear Installations (CSNI) Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components was held in Lyon, France on 25-27 S...
