The LEADER project aims at the development to a conceptual level of a Lead Fast Reactor Industrial size plant and at a scaled demonstrator of the LFR technology - ALFRED. This paper presents the main safety transient analysis results using the system codes RELAP5, TRACE-FRED, SIM-LFR, CATHARE and SIMMER of the DBC (Design Basis Condition) transients for the ALFRED reactor. Apart from the traditional set of protected transients (PLOF, PTOP, LOOP), safety analysis was carried out for a number of carefully selected plant specific DBC transients, thus enveloping a wide spectrum of design basis conditions
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear En...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...
This paper summarizes the approach to safety for the LFR systems, developed on the basis of the reco...
This report presents results of transient analyses performed for a pre-conceptual design of a Molten...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
M2LFR-1000 is a medium-power modular lead-cooled fast reactor, developed by University of Science an...
Lead-cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in th...
AbstractThe new reactor concepts proposed in the Generation IV International Forum require the devel...
The Advanced Lead Fast Reactor European Demonstrator (ALFRED) was conceived in the framework of the ...
The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility ...
Nowadays, increased attention to safety issues for nuclear research reactors has emerged as a conse...
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research reactor, the s...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
The Advanced Lead Fast Reactor European Demonstrator (ALFRED) is the 300 MWth pool-type reactor aime...
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear En...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...
This paper summarizes the approach to safety for the LFR systems, developed on the basis of the reco...
This report presents results of transient analyses performed for a pre-conceptual design of a Molten...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
M2LFR-1000 is a medium-power modular lead-cooled fast reactor, developed by University of Science an...
Lead-cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in th...
AbstractThe new reactor concepts proposed in the Generation IV International Forum require the devel...
The Advanced Lead Fast Reactor European Demonstrator (ALFRED) was conceived in the framework of the ...
The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility ...
Nowadays, increased attention to safety issues for nuclear research reactors has emerged as a conse...
LOFA is one of the most important PIE in nuclear reactors. For the pool-type research reactor, the s...
The assessment of the tools used for deterministic safety analysis and the compliance with the accep...
The Advanced Lead Fast Reactor European Demonstrator (ALFRED) is the 300 MWth pool-type reactor aime...
So far, Research Reactor safety analysis has been performed using conservative computer tools comm...
The Lead-cooled Fast Reactor is one of the three technologies selected by the Sustainable Nuclear En...
Great interest is given now to advanced nuclear reactors especially those using passive safety compo...