International audienceThe strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postulated severe accident relies on the presence of dedicated corium discharge tubes between the active core region and the lower plenum and an in-vessel core catcher in the lower plenum to collect and cool the molten fuel. In this situation, the corium progression from the core towards the core catcher could lead to jet impingement on the core catcher surface and a subsequent degradation of the core-catcher material(s). After a review of the existing experimental database, it appeared necessary to define a dedicated experimental R&D program related to the long-lasting jet impingement on thick material plates. A particular b...
The project on ex-vessel core melt stabilization research (ECOSTAR) started in January 2000 to be co...
VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were con...
In case of core meltdown in a sodium-cooled fast reactor (SFR), it is important to remove the corium...
International audienceThe strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the c...
International audienceThe ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demon...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
Presented is an analysis of the results of the CSTI-1, CSTI-3, and CWTI-11 reactor material experime...
International audienceThe ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demon...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
International audienceFor 20 years, CEA has developed R&D programs on several severe accident phenom...
International audienceThe ASTRID reactor developed by the CEA with its industrial partners, will be ...
International audienceIn the design of every new nuclear reactor, the possibility of a core meltdown...
To avoid settling of molten materials directly on the vessel wall in severe accident sequences, usin...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
In the sodium-cooled fast reactors (SFRs), the hypothetical energetic core disruptive accident (HCDA...
The project on ex-vessel core melt stabilization research (ECOSTAR) started in January 2000 to be co...
VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were con...
In case of core meltdown in a sodium-cooled fast reactor (SFR), it is important to remove the corium...
International audienceThe strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the c...
International audienceThe ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demon...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
Presented is an analysis of the results of the CSTI-1, CSTI-3, and CWTI-11 reactor material experime...
International audienceThe ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demon...
International audienceSevere accident with core meltdown is a threat to the containment integrity. A...
International audienceFor 20 years, CEA has developed R&D programs on several severe accident phenom...
International audienceThe ASTRID reactor developed by the CEA with its industrial partners, will be ...
International audienceIn the design of every new nuclear reactor, the possibility of a core meltdown...
To avoid settling of molten materials directly on the vessel wall in severe accident sequences, usin...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
In the sodium-cooled fast reactors (SFRs), the hypothetical energetic core disruptive accident (HCDA...
The project on ex-vessel core melt stabilization research (ECOSTAR) started in January 2000 to be co...
VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were con...
In case of core meltdown in a sodium-cooled fast reactor (SFR), it is important to remove the corium...