A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has been analyzed. This event is characterized as an intermediate break loss-of-coolant accident (IBLOCA). Most of the insights regarding the response of the AP600 safety systems to the postulated accident are derived from calculations performed with the TRAC-PFl/MOD2 code. However, complementary insights derived from a scaled experiment conducted in the ROSA facility, as well as insights based upon calculations by other codes, are also presented. The key processes occurring in an AP600 during a IBLOCA are primary coolant system depressurization, inventory depletion, inventory replacement via emergency core coolant injection, continuous core cooli...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipowe...
The Westinghouse AP1000 main characteristic that distinguish it with respects to the modern PWRs is ...
A postulated double-ended guillotine break of an AP600 direct-vessel-injection line has been analyze...
The AP600 is a simplified advanced pressurized water reactor (PWR) design incorporating passive safe...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]Reports on a series of small-break LOCA analyses for a typical Westinghouse 3-loop PWR, ...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems ...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
none3noThe Westinghouse AP1000 main characteristic that distinguish it with respects to the modern P...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipowe...
The Westinghouse AP1000 main characteristic that distinguish it with respects to the modern PWRs is ...
A postulated double-ended guillotine break of an AP600 direct-vessel-injection line has been analyze...
The AP600 is a simplified advanced pressurized water reactor (PWR) design incorporating passive safe...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]Reports on a series of small-break LOCA analyses for a typical Westinghouse 3-loop PWR, ...
Operation of pressurised water reactors involves shutdown periods for refuelling and maintenance. In...
The Westinghouse AP600 reactor is an advanced pressurized water reactor with passive safety systems ...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
none3noThe Westinghouse AP1000 main characteristic that distinguish it with respects to the modern P...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipowe...
The Westinghouse AP1000 main characteristic that distinguish it with respects to the modern PWRs is ...