The increasing worldwide interest in Lead-cooled Fast Reactors (LFRs) substantiates the need to validate the analytical codes and methods used to support their design. For neutronic analyses, this is chiefly reflected in assessing the impact of nuclear data uncertainties on the integral and local parameters resulting from such analyses. The aim of refining nuclear data moves continuous efforts for more accurate measurements, be them differential or integral, for which adequate facilities are required. The availability at the ENEA's Casaccia research center of a fast source reactor – RSV TAPIRO – provides a unique opportunity to perform new integral experiments in support of fast reactors, including LFRs, owing to the well-characterized neut...
In the coming future, the electric energy production from nuclear power plants will be provided by b...
The Lead-Cooled Fast Reactors (LFR) has in some cases advantages from a safety point of view compare...
The status of the development of a coupled neutronic/thermal-hydraulic model for the stability and s...
The increasing worldwide interest in Lead-cooled Fast Reactors (LFRs) substantiates the need to vali...
The paper presents the results of the efforts concerned with expanding the verification database and...
The demand for new and advance nuclear systems are widely studied all over the world. By the late 20...
Lead cooled fast reactors (LFRs) are among next generation of safer nuclear reactors. Molten lead (P...
%PS211 %title \\ \\The purpose of PS211 is to determine how neutrons, produced by spallation inside ...
It is well known, that lead coolant, highly enriched by 208Pb, has some advantages over other coolan...
The paper presents the results of a comparative analysis of criticality calculations using a Monte-C...
The purpose of the present study is the justification of the possibility of improving fast reactor s...
In this paper, neutronics and severe safety characteristics of Lead-cooled Fast Reactor (LFR) and So...
The next generation of nuclear energy systems, also known as Generation IV reactors, are being devel...
An Italian effort has been initiated under a cooperation between ENEA and CIRTEN for the investigati...
The next generation of nuclear energy systems, also known as Generation-IV reactors are being develo...
In the coming future, the electric energy production from nuclear power plants will be provided by b...
The Lead-Cooled Fast Reactors (LFR) has in some cases advantages from a safety point of view compare...
The status of the development of a coupled neutronic/thermal-hydraulic model for the stability and s...
The increasing worldwide interest in Lead-cooled Fast Reactors (LFRs) substantiates the need to vali...
The paper presents the results of the efforts concerned with expanding the verification database and...
The demand for new and advance nuclear systems are widely studied all over the world. By the late 20...
Lead cooled fast reactors (LFRs) are among next generation of safer nuclear reactors. Molten lead (P...
%PS211 %title \\ \\The purpose of PS211 is to determine how neutrons, produced by spallation inside ...
It is well known, that lead coolant, highly enriched by 208Pb, has some advantages over other coolan...
The paper presents the results of a comparative analysis of criticality calculations using a Monte-C...
The purpose of the present study is the justification of the possibility of improving fast reactor s...
In this paper, neutronics and severe safety characteristics of Lead-cooled Fast Reactor (LFR) and So...
The next generation of nuclear energy systems, also known as Generation IV reactors, are being devel...
An Italian effort has been initiated under a cooperation between ENEA and CIRTEN for the investigati...
The next generation of nuclear energy systems, also known as Generation-IV reactors are being develo...
In the coming future, the electric energy production from nuclear power plants will be provided by b...
The Lead-Cooled Fast Reactors (LFR) has in some cases advantages from a safety point of view compare...
The status of the development of a coupled neutronic/thermal-hydraulic model for the stability and s...