In the unlikely event of a Loss of Coolant Accident (LOCA) in a pressurized water reactor (PWR), break jet impingement would dislodge thermal insulation from nearby piping, as well as other materials within the containment, such as paint chips, concrete dust, and fire barrier materials. Steam/water flows induced by the break and by the containment sprays would transport debris to the containment floor. Subsequently, debris would likely transport to and accumulate on the suction sump screens of the emergency core cooling system (ECCS) pumps, thereby potentially degrading ECCS performance and possibly even failing the ECCS. In 1998, the U. S. Nuclear Regulatory Commission (NRC) initiated a generic study (Generic Safety Issue-191) to evaluate ...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...
International audienceDuring a severe accident in a nuclear power plant, the degradation of fuel rod...
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...
During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water...
The purpose of the Generic-Safety-Issue (GSI) 191 study is to determine if the transport and accumul...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
The Nuclear Regulatory Commission has issued a Regulatory Bulletin and accompanying Regulatory Guide...
This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated th...
The investigation of insulation debris generation, transport and sedimentation becomes more importan...
During the initial stage of a Loss of Coolant Accident (LOCA), known as the blowdown phase, the high...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Melt fragmentation, quenching and long term coolability in a deep pool of water under reactor vessel...
In a world where climatic and environmental issues are questioning the energy policies every day, th...
A series of controlled experiments were conducted to obtain head loss and filtration characteristics...
Particulate debris beds may form during different stages of a severe accident; e.g. in the degrading...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...
International audienceDuring a severe accident in a nuclear power plant, the degradation of fuel rod...
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...
During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water...
The purpose of the Generic-Safety-Issue (GSI) 191 study is to determine if the transport and accumul...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
The Nuclear Regulatory Commission has issued a Regulatory Bulletin and accompanying Regulatory Guide...
This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated th...
The investigation of insulation debris generation, transport and sedimentation becomes more importan...
During the initial stage of a Loss of Coolant Accident (LOCA), known as the blowdown phase, the high...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Melt fragmentation, quenching and long term coolability in a deep pool of water under reactor vessel...
In a world where climatic and environmental issues are questioning the energy policies every day, th...
A series of controlled experiments were conducted to obtain head loss and filtration characteristics...
Particulate debris beds may form during different stages of a severe accident; e.g. in the degrading...
In the aftermath of the Fukushima Dai-Ichi nuclear accident, the issue of corium coolability has rec...
International audienceDuring a severe accident in a nuclear power plant, the degradation of fuel rod...
The possible failure of an Emergency Core Cooling System (ECCS) train due to a large amount of entra...