The new reactor concepts proposed in the Generation IV International Forum require the development and validation of new components and new materials. Inside the Collaborative Project on the European Sodium Fast Reactor, several accidental scenario have been studied. Nevertheless, none of them coped with mechanical safety assessment of the fuel cladding under accidental conditions. Among the accidental conditions considered, there is the unprotected transient of overpower (UTOP), due to the insertion, at the end of the first fuel cycle, of a positive reactivity into the reactor core as a consequence of the unexpected runaway of one control rod. The goal of the study was the search for a detailed distribution of the fission power, in the ra...
The 4-year JASMIN collaborative project, involving 9 organizations, was launched by IRSN end of 2011...
International audienceNeutron flux monitoring system forms an integral part of the safety design of ...
All existing sodium fast reactors, built or operated, have a safety vessel around the main reactor v...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) in ...
Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability ...
International audienceThe ASTRID reactor developed by the CEA with its industrial partners, will be ...
International audienceThe nuclear safety approach has to cover accident sequences involving core deg...
The International Atomic Energy Agency (IAEA) actively supports Member States in the development and...
ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-coo...
International audienceSodium-cooled Fast Reactors (SFR) are investigated as future Generation IV rea...
The 4-year JASMIN collaborative project, involving 9 organizations, was launched by IRSN end of 2011...
International audienceNeutron flux monitoring system forms an integral part of the safety design of ...
All existing sodium fast reactors, built or operated, have a safety vessel around the main reactor v...
The new reactor concepts proposed in the Generation IV International Forum require the development a...
ISBN : 9781510872622International audienceWithin the framework of the Generation IV Sodium-cooled Fa...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) in ...
Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability ...
International audienceThe ASTRID reactor developed by the CEA with its industrial partners, will be ...
International audienceThe nuclear safety approach has to cover accident sequences involving core deg...
The International Atomic Energy Agency (IAEA) actively supports Member States in the development and...
ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-coo...
International audienceSodium-cooled Fast Reactors (SFR) are investigated as future Generation IV rea...
The 4-year JASMIN collaborative project, involving 9 organizations, was launched by IRSN end of 2011...
International audienceNeutron flux monitoring system forms an integral part of the safety design of ...
All existing sodium fast reactors, built or operated, have a safety vessel around the main reactor v...