The objective of the proposed experiments is to replicate approximately, by injecting low melting point metal alloys into Freon-11 and liquid nitrogen, the dispersal of corium streams in water. To first gain a better understanding of the corium dispersal process to be simulated, experimental data from the CCM experiments, in which the injection of streams of molten corium into water was studied, was interpreted in cooperation with Argonne National Laboratory (ANL) staff. The results of these experiments are discussed briefly below. This is followed by a description of the preparations made to date for the present simulant experiments
To avoid settling of molten materials directly on the vessel wall in severe accident sequences, usin...
International audienceIn the design of every new nuclear reactor, the possibility of a core meltdown...
In the case of a severe accident in a nuclear power plant, the molten core may flow into water and i...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
In a loss of coolant accident, the core may become uncovered, causing the fuel pins to melt. The mol...
In the sodium-cooled fast reactors (SFRs), the hypothetical energetic core disruptive accident (HCDA...
Developed mathematical model and some results of its application to the element of the passive prote...
International audienceIn the event of a hypothetical core disruptive accident in nuclear power plant...
The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postu...
In a severe accident of light water reactor (LWR), molten core material (corium) can be released int...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
The potential risk of fuel coolant interaction (FCI, steam explosions) in light water reactor severe...
The DISCO-H experiments simulate melt ejection scenarios under low system pressure in severe acciden...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
In order to predict the effect of a fuel-coolant interaction after a hypothetical core-melt-down acc...
To avoid settling of molten materials directly on the vessel wall in severe accident sequences, usin...
International audienceIn the design of every new nuclear reactor, the possibility of a core meltdown...
In the case of a severe accident in a nuclear power plant, the molten core may flow into water and i...
A postulated severe loss of coolant accident in a nuclear reactor can lead to significant core damag...
In a loss of coolant accident, the core may become uncovered, causing the fuel pins to melt. The mol...
In the sodium-cooled fast reactors (SFRs), the hypothetical energetic core disruptive accident (HCDA...
Developed mathematical model and some results of its application to the element of the passive prote...
International audienceIn the event of a hypothetical core disruptive accident in nuclear power plant...
The strategy used in ASTRID Sodium Fast Reactor Demonstrator to mitigate the consequences of a postu...
In a severe accident of light water reactor (LWR), molten core material (corium) can be released int...
Integral large-scale vessel retention experiments have been performed using up to 60 kg of prototypi...
The potential risk of fuel coolant interaction (FCI, steam explosions) in light water reactor severe...
The DISCO-H experiments simulate melt ejection scenarios under low system pressure in severe acciden...
International audienceAbstract This paper deals with ablation of a solid by a high temperature liqui...
In order to predict the effect of a fuel-coolant interaction after a hypothetical core-melt-down acc...
To avoid settling of molten materials directly on the vessel wall in severe accident sequences, usin...
International audienceIn the design of every new nuclear reactor, the possibility of a core meltdown...
In the case of a severe accident in a nuclear power plant, the molten core may flow into water and i...