In this paper, we report on the results using the BWR plant simulator about the plant behavior under the condition of the two types of severe accidents that LOCA occurs but ECCS fails the water irrigation into the reactor core and SBO occurs and at the same time the reclosed failure of SRV occurs. The simulation experiments were carried out for the cases that LOCA has occurred in the main feed-water piping. As for the results about the relationship between the LOCA area and the time from LOCA occurs until the fuel temperature rise start, the effect that RCIC operated was extremely big for small and middle LOCA area. In the case of main feed-water system LOCA, the core water level suddenly decreased for large LOCA of 2000cm2 area, however, i...
Severe water ingress accidents in the 200-MW HTR-module were assessed to determine the safety margin...
This report analyzes severe water ingress accidents in the SIEMENS 200MW Modular Pebble-Bed High Tem...
In this study, thermal–hydraulic parameters inside the containment of a WWER-1000/v446 nuclear power...
In this paper, we report on the results using the BWR plant simulator about the plant behavior under...
In this paper, we report on the results using the PWR plant simulator about the plant behavior under...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated ...
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated ...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
After the Fukushima accident, beyond design basis accidents (BDBA), even though their frequency is p...
The reexamination argument on nuclear power has arisen after the Fukushima accident. When nuclear po...
4siIn this study, thermal-hydraulic parameters inside the containment of a WWER-1000/v446 nuclear po...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor...
Severe water ingress accidents in the 200-MW HTR-module were assessed to determine the safety margin...
This report analyzes severe water ingress accidents in the SIEMENS 200MW Modular Pebble-Bed High Tem...
In this study, thermal–hydraulic parameters inside the containment of a WWER-1000/v446 nuclear power...
In this paper, we report on the results using the BWR plant simulator about the plant behavior under...
In this paper, we report on the results using the PWR plant simulator about the plant behavior under...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated ...
Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated ...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
After the Fukushima accident, beyond design basis accidents (BDBA), even though their frequency is p...
The reexamination argument on nuclear power has arisen after the Fukushima accident. When nuclear po...
4siIn this study, thermal-hydraulic parameters inside the containment of a WWER-1000/v446 nuclear po...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor...
Severe water ingress accidents in the 200-MW HTR-module were assessed to determine the safety margin...
This report analyzes severe water ingress accidents in the SIEMENS 200MW Modular Pebble-Bed High Tem...
In this study, thermal–hydraulic parameters inside the containment of a WWER-1000/v446 nuclear power...