Several innovative solutions for a liquid metal fast reactor design are being investigated within the framework of the ELSY (the acronym for the European Lead-cooled System) Sixth Framework Programme of URATOM. Among these solutions the open-assembly core option adopted by ENEA for the preliminary neutronic analysis requires a new approach to the thermal-hydraulic core design. In addition, it could have important implication on the reactor safety. Therefore a two-step approach at the T/H analysis of the core is being followed: Utilization of a one-dimensional RELAP5 model for independent channels analysis for a prompt verification of the thermal-hydraulic and safety of the core neutronic design. Development of a dedicated tool for the e...
The European Lead Fast Reactor is being developed starting from September 2006, in the frame of the ...
The present report is a contribution to the “Numerical analysis of operational scenarios and inciden...
The next generation of nuclear energy systems, also known as Generation IV reactors, are being devel...
Several innovative solutions for a liquid metal fast reactor design are being investigated within th...
Several innovative solutions for a liquid metal fast reactor design are being investigated. Among th...
none5This paper deals with the neutronic design of ELSY (the European Lead-cooled SYstem), a 600 MWe...
This paper presents the current status of development of ELSY - European Lead-cooled System - a pool...
Two alternative core restraint concepts are considered for a conceptual design of a 900 MWth liquid ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The Generation IV International Forum (GIF) has among its main goals the excellence in safety and re...
The European Lead Fast Reactor is being developed starting from September 2006, in the frame of the ...
The paper is aimed at preliminary evaluating the load bearing capability of a Generation IV metal co...
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II s...
This paper concerns two independent safety investigations on critical and sub-critical heavy liquid ...
The lack of full understanding of complex mechanisms connected with the interaction between thermal-...
The European Lead Fast Reactor is being developed starting from September 2006, in the frame of the ...
The present report is a contribution to the “Numerical analysis of operational scenarios and inciden...
The next generation of nuclear energy systems, also known as Generation IV reactors, are being devel...
Several innovative solutions for a liquid metal fast reactor design are being investigated within th...
Several innovative solutions for a liquid metal fast reactor design are being investigated. Among th...
none5This paper deals with the neutronic design of ELSY (the European Lead-cooled SYstem), a 600 MWe...
This paper presents the current status of development of ELSY - European Lead-cooled System - a pool...
Two alternative core restraint concepts are considered for a conceptual design of a 900 MWth liquid ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The Generation IV International Forum (GIF) has among its main goals the excellence in safety and re...
The European Lead Fast Reactor is being developed starting from September 2006, in the frame of the ...
The paper is aimed at preliminary evaluating the load bearing capability of a Generation IV metal co...
The International Atomic Energy Agency established a Coordinated Research Project (CRP) for EBR-II s...
This paper concerns two independent safety investigations on critical and sub-critical heavy liquid ...
The lack of full understanding of complex mechanisms connected with the interaction between thermal-...
The European Lead Fast Reactor is being developed starting from September 2006, in the frame of the ...
The present report is a contribution to the “Numerical analysis of operational scenarios and inciden...
The next generation of nuclear energy systems, also known as Generation IV reactors, are being devel...