This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR). The motivation of this research is to improve the inherent safety of the LFR based on the China Accelerator Driven System (ADS) engineering project. Usually the plant is damaged due to the failure of the main pumps and the main heat exchangers under the Station Blackout (SBO). To prevent this accident, we proposed the DHRS based on the diathermic oil cooling for the LFR. The behavior of the DHRS and the plant was simulated using the CFD code STAR CCM+ using LFR with DHRS. The purpose of this analysis is to evaluate th...
In the context of the safety increase of the integrated sodium-cooled fast breeder reactor, we prese...
Following the Fukushima-Daiichi nuclear accident in March 2011, innovations are needed to improve th...
One of the main issues, regarding the development of Generation IV nuclear power plants, is the safe...
The generation IV lead cooled fast reactors are of particular interest for the Italian research: sev...
Abstract The generation IV lead cooled fast reactors are of particular interest for the Italian rese...
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast react...
Natural convection in enclosures have been studied numerically to provide insight into the scaling l...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
Within the field of research and development of innovative nuclear reactors, in particular Generatio...
The possibility of using natural circulation of the coolant as a way to remove decay heat is of grea...
In the last few years a number of compact designs of lead-alloy cooled systems have been promoted. M...
Abstract- With the advent of the U.S. lead Gen IV initiative to develop an entirely new generation o...
The purpose of this work was to develop and validate a design tool for the transients that are of in...
In this paper, the thermal fluid-dynamics results of the DHR pre-test calculation performed using th...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
In the context of the safety increase of the integrated sodium-cooled fast breeder reactor, we prese...
Following the Fukushima-Daiichi nuclear accident in March 2011, innovations are needed to improve th...
One of the main issues, regarding the development of Generation IV nuclear power plants, is the safe...
The generation IV lead cooled fast reactors are of particular interest for the Italian research: sev...
Abstract The generation IV lead cooled fast reactors are of particular interest for the Italian rese...
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast react...
Natural convection in enclosures have been studied numerically to provide insight into the scaling l...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
Within the field of research and development of innovative nuclear reactors, in particular Generatio...
The possibility of using natural circulation of the coolant as a way to remove decay heat is of grea...
In the last few years a number of compact designs of lead-alloy cooled systems have been promoted. M...
Abstract- With the advent of the U.S. lead Gen IV initiative to develop an entirely new generation o...
The purpose of this work was to develop and validate a design tool for the transients that are of in...
In this paper, the thermal fluid-dynamics results of the DHR pre-test calculation performed using th...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
In the context of the safety increase of the integrated sodium-cooled fast breeder reactor, we prese...
Following the Fukushima-Daiichi nuclear accident in March 2011, innovations are needed to improve th...
One of the main issues, regarding the development of Generation IV nuclear power plants, is the safe...