In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside and outside. The uncovered fuel channels would heat up, deform and disassemble into core debris. Large inventories of water passively reduce the rate of progression of the accident, prolonging the time for complete loss of engineered heat sinks.The efficacy of available backup and ultimate heat sinks, available in a CANDU 6 reactor, in mitigating the consequences of a prolonged station blackout scenario was analysed using the MAAP4-CANDU code. The analysis indicated that the steam generator seco...
This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Tra...
AbstractThe new safety analysis methodology for the CANDU-6 nuclear power plant (NPP) moderator syst...
AbstractFollowing the Fukushima accident, a special safety inspection was conducted in Korea. The in...
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage woul...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
A survey of possible LOCA (Loss-of-Coolant Accident) initiating events that might take place for CAN...
CANDU reactors have a large number of active and passive systems which help to mitigate events such ...
A design for a large, passive, light water reactor has been developed. The proposed concept is a pre...
Removal of decay heat from an operating reactor during a prolonged station blackout condition is a b...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
The Fukushima Daiichi Nuclear Power Plant accident and its consequences have led to some rethinking ...
The accident at the Fukushima Dai-ichi nuclear power plant demonstrated the vulnerability of the pla...
Fukushima Daiichi NPP accident showed that plant technical support center (TSC) in an extreme and ra...
This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Tra...
AbstractThe new safety analysis methodology for the CANDU-6 nuclear power plant (NPP) moderator syst...
AbstractFollowing the Fukushima accident, a special safety inspection was conducted in Korea. The in...
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage woul...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
A survey of possible LOCA (Loss-of-Coolant Accident) initiating events that might take place for CAN...
CANDU reactors have a large number of active and passive systems which help to mitigate events such ...
A design for a large, passive, light water reactor has been developed. The proposed concept is a pre...
Removal of decay heat from an operating reactor during a prolonged station blackout condition is a b...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
The Fukushima Daiichi Nuclear Power Plant accident and its consequences have led to some rethinking ...
The accident at the Fukushima Dai-ichi nuclear power plant demonstrated the vulnerability of the pla...
Fukushima Daiichi NPP accident showed that plant technical support center (TSC) in an extreme and ra...
This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Tra...
AbstractThe new safety analysis methodology for the CANDU-6 nuclear power plant (NPP) moderator syst...
AbstractFollowing the Fukushima accident, a special safety inspection was conducted in Korea. The in...