A preliminary but systematic safety analysis of a liquid metal divertor (LMD) for the EU DEMO performed by means of the Functional Failure Mode and Effect Analysis (FFMEA) is presented. This methodology is suitable for the analysis of the LMD, which is undergoing preconceptual design. In fact, the FFMEA compensates for the lack of detailed design information by postulating the loss of a system function, rather than a specific component failure. The implementation of the FFMEA led to a better understanding of the safety and operational issues associated with the system and to the identification of a list of postulated initiating events (PIEs), i.e., the most challenging conditions for the plant. The PIEs, together with their possible cons...
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under...
The Sodium-cooled Fast Reactor (SFR) is by far the most advanced reactor of the six Generation IV re...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
International audienceThe Molten Salt Fast Reactor (MSFR) with its liquid circulating fuel and its f...
The design of the European Union (EU) DEMO reactor magnet system, currently ongoing within the EUROf...
Safety studies are performed in the frame of the conceptual design studies for the European Demonstr...
In the last decades, the research activity for the development of innovative nuclear systems tries t...
The functional deviations able to compromise system safety in the EU DEMO Primary Heat Transfer Syst...
As part of the pre-conceptual design activities for the European DEMOnstration plant, a carefully se...
The primary purpose of this study is to perform an Initiating Event Analysis for a Lithium Fluoride ...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
International audienceSodium-cooled Fast Reactors (SFR) are investigated as future Generation IV rea...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
Within the framework of the European Roadmap to the realization of fusion energy, a strong internati...
Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available wat...
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under...
The Sodium-cooled Fast Reactor (SFR) is by far the most advanced reactor of the six Generation IV re...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
International audienceThe Molten Salt Fast Reactor (MSFR) with its liquid circulating fuel and its f...
The design of the European Union (EU) DEMO reactor magnet system, currently ongoing within the EUROf...
Safety studies are performed in the frame of the conceptual design studies for the European Demonstr...
In the last decades, the research activity for the development of innovative nuclear systems tries t...
The functional deviations able to compromise system safety in the EU DEMO Primary Heat Transfer Syst...
As part of the pre-conceptual design activities for the European DEMOnstration plant, a carefully se...
The primary purpose of this study is to perform an Initiating Event Analysis for a Lithium Fluoride ...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
International audienceSodium-cooled Fast Reactors (SFR) are investigated as future Generation IV rea...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenario...
Within the framework of the European Roadmap to the realization of fusion energy, a strong internati...
Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available wat...
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under...
The Sodium-cooled Fast Reactor (SFR) is by far the most advanced reactor of the six Generation IV re...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...