The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU 6 nuclear power plants in case of LOCA accidents, using Flowmaster calculation code, by delimiting models and setting calculation assumptions, input data for hydraulic analysis and input data for calculating thermal performance check for heat exchangers that are part of this system
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
A success criteria map defining successful implementation of a cooldown procedure to mitigate small-...
This document focuses on the procedure and results of creating a thermohydraulic model of the second...
The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU ...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
The objective of the work presented in this report was to evaluate the possibility to make an accura...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
As a latest developed computational code, TRACE is expected to be useful and effective for analyzing...
none3noThe Westinghouse AP1000 main characteristic that distinguish it with respects to the modern P...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Stricter requirements on licenses for operating nuclear power plants in Sweden have resulted in a ne...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Eight main circulation pumps (MCPs) are employed for the cooling of water forced circulation through...
The passive safety systems of the AP1000® nuclear reactor are based on natural phenomena to ensure c...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
A success criteria map defining successful implementation of a cooldown procedure to mitigate small-...
This document focuses on the procedure and results of creating a thermohydraulic model of the second...
The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU ...
In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the n...
The objective of the work presented in this report was to evaluate the possibility to make an accura...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
As a latest developed computational code, TRACE is expected to be useful and effective for analyzing...
none3noThe Westinghouse AP1000 main characteristic that distinguish it with respects to the modern P...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
Stricter requirements on licenses for operating nuclear power plants in Sweden have resulted in a ne...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Eight main circulation pumps (MCPs) are employed for the cooling of water forced circulation through...
The passive safety systems of the AP1000® nuclear reactor are based on natural phenomena to ensure c...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
A success criteria map defining successful implementation of a cooldown procedure to mitigate small-...
This document focuses on the procedure and results of creating a thermohydraulic model of the second...