ABSTRACT The purpose of this analysis was to perform Loss of Normal Feedwater reference calculations for Krško Full Scope Simulator validation. In addition, the thermal-hydraulic response of the reactor coolant system was studied in detail. The results of these calculations were used for annual ANSI/ANS validation of reactor coolant system thermal-hydraulic response predicted by Krško Full Scope Simulator. For the thermal-hydraulic analyses the RELAP5/MOD3.3 code and the input model for NPP Krško, delivered by NPP Krško, was used. The analyses performed to study the response of RCS to the Loss of FW accident consist of two scenarios, starting with the same initiating event that is loss of normal feedwater to both steam generators. In both c...
There is a widespread use of thermal hydraulic codes in nuclear industry. The codesare used to analy...
loss of feedwater accident is one of the frequently sever accidents in steam boiler facilities. It t...
The safety analysis of research reactors includes simulations of selected cases classified by the In...
ABSTRACT The purpose of this analysis was to simulate Anticipated Transient without Scram transient ...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
This paper discusses the results of the thermal-hydraulic investigations of the Total Loss of Feed W...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
Due to the character of the original source materials and the nature of batch digitization, quality ...
In accident analysis regarding nuclear power plants, it is very common to use thermal hydraulic syst...
This paper deals with the development and validation of a coupled RELAP5/PARCS model of the Swedish ...
The Darlington NGS consists of four 940 MWe CANDU reactors. A detailed RELAP5 model of a Darlington ...
Measured plant data from various abnormal events or incidents are of great importance for assessing ...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
There is a widespread use of thermal hydraulic codes in nuclear industry. The codesare used to analy...
loss of feedwater accident is one of the frequently sever accidents in steam boiler facilities. It t...
The safety analysis of research reactors includes simulations of selected cases classified by the In...
ABSTRACT The purpose of this analysis was to simulate Anticipated Transient without Scram transient ...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
This paper discusses the results of the thermal-hydraulic investigations of the Total Loss of Feed W...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
Due to the character of the original source materials and the nature of batch digitization, quality ...
In accident analysis regarding nuclear power plants, it is very common to use thermal hydraulic syst...
This paper deals with the development and validation of a coupled RELAP5/PARCS model of the Swedish ...
The Darlington NGS consists of four 940 MWe CANDU reactors. A detailed RELAP5 model of a Darlington ...
Measured plant data from various abnormal events or incidents are of great importance for assessing ...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
There is a widespread use of thermal hydraulic codes in nuclear industry. The codesare used to analy...
loss of feedwater accident is one of the frequently sever accidents in steam boiler facilities. It t...
The safety analysis of research reactors includes simulations of selected cases classified by the In...