UpFlow Conversion (UFC) was implemented in NPP Krško during the last outage in order to reduce the pressure differential across baffle plates and the possibility of the fuel damage caused by flow induced vibration. The paper describes the coupled code calculation (RELAP5 and PARCS) of MSLB accident at power for pre and post-UFC configuration of reactor vessel. In the calculation, the split model of the reactor vessel was used to better describe asymmetric conditions in loops. It has been demonstrated that the basic parameters (pressure, temperatures) stayed unchanged and there was little change in the flow rates except in baffle-barrel region of the vessel where both flow direction and amount of flow were changed
A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the...
One of the transients that have received considerable attention in the safety evaluation of RBMK rea...
In the context of the lessons learned from Fukushima Daiichi NPP, the safety of a medium power resea...
UpFlow Conversion (UFC) was implemented in NPP Krško during the last outage in order to reduce the p...
Natural circulation flows can develop within a reactor coolant system (RCS) during certain severe re...
Safety analyses for RBMK reactors has to consider accident scenarios causing the lost of design boun...
Since the revision of the requirements to consider the effect of fuel burnup on emergency core cooli...
The analysis of a Station blackout (SBO) accident in the NPP Krško including thermalhydraulic behavi...
This summary presents generic results and insights from preliminary calculations performed with the ...
High neutron flux in core of a nuclear reactor can affect the material of Reactor Pressure Vessel (R...
Nuclear energy is the largest source of carbon-free electricity in the United States, making up 20 p...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
A Loss of Coolant Accident (LOCA) is initiated by damage in the primary circuit and subsequent coola...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the...
One of the transients that have received considerable attention in the safety evaluation of RBMK rea...
In the context of the lessons learned from Fukushima Daiichi NPP, the safety of a medium power resea...
UpFlow Conversion (UFC) was implemented in NPP Krško during the last outage in order to reduce the p...
Natural circulation flows can develop within a reactor coolant system (RCS) during certain severe re...
Safety analyses for RBMK reactors has to consider accident scenarios causing the lost of design boun...
Since the revision of the requirements to consider the effect of fuel burnup on emergency core cooli...
The analysis of a Station blackout (SBO) accident in the NPP Krško including thermalhydraulic behavi...
This summary presents generic results and insights from preliminary calculations performed with the ...
High neutron flux in core of a nuclear reactor can affect the material of Reactor Pressure Vessel (R...
Nuclear energy is the largest source of carbon-free electricity in the United States, making up 20 p...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
A Loss of Coolant Accident (LOCA) is initiated by damage in the primary circuit and subsequent coola...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
A power limit criterion was developed for a postulated Loss of Pumping Accident (LOPA) in one of the...
One of the transients that have received considerable attention in the safety evaluation of RBMK rea...
In the context of the lessons learned from Fukushima Daiichi NPP, the safety of a medium power resea...