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...
Accident management procedures associated with nuclear power plant beyond design basis accidents s...
The Fukushima Daiichi Nuclear Power Plant accident and its consequences have led to some rethinking ...
If the Total Loss of Feedwater (TLFW) accident occurs in a VVER reactor, the primary side Feed & Ble...
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage woul...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
Removal of decay heat from an operating reactor during a prolonged station blackout condition is a b...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
CANDU reactors have a large number of active and passive systems which help to mitigate events such ...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor...
Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failu...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
AbstractThe new safety analysis methodology for the CANDU-6 nuclear power plant (NPP) moderator syst...
A design for a large, passive, light water reactor has been developed. The proposed concept is a pre...
Accident management procedures associated with nuclear power plant beyond design basis accidents s...
The Fukushima Daiichi Nuclear Power Plant accident and its consequences have led to some rethinking ...
If the Total Loss of Feedwater (TLFW) accident occurs in a VVER reactor, the primary side Feed & Ble...
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage woul...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
During a station blackout (SBO), the initiating event is a loss of Class IV and Class III power, cau...
Removal of decay heat from an operating reactor during a prolonged station blackout condition is a b...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
CANDU reactors have a large number of active and passive systems which help to mitigate events such ...
In a postulated severe core damage accident in a PHWR, multiple failures of core cooling systems may...
Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor...
Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failu...
In this paper, we report on the core cooling effect by natural circulation cooling of the primary co...
AbstractThe new safety analysis methodology for the CANDU-6 nuclear power plant (NPP) moderator syst...
A design for a large, passive, light water reactor has been developed. The proposed concept is a pre...
Accident management procedures associated with nuclear power plant beyond design basis accidents s...
The Fukushima Daiichi Nuclear Power Plant accident and its consequences have led to some rethinking ...
If the Total Loss of Feedwater (TLFW) accident occurs in a VVER reactor, the primary side Feed & Ble...