Nuclear power plants (NPPs) must ensure that the emergency core cooling system (ECCS) or safety-related containment spray system (CSS) remains capable of performing its design safety function throughout the life of the plant. This requires ensuring that long-term core cooling can be maintained following a postulated loss-of-coolant accident (LOCA). Adequate safety operation can be impaired if the protective coatings which have been applied to the concrete and steel structures within the primary containment fail, producing transportable debris which could then accumulate on BWR ECCS suction strainers or PWR ECCS sump debris screens located within the containment. This document will present the data collected during the investigation of coati...
This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanis...
This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated th...
The international Phébus FP (fission product) programme investigated core degradation and radioactiv...
A research program to investigate the performance and potential for debris formation of Service Leve...
For many years, the French "Institut de Radioprotection et de Sûreté Nucléaire" has developed studie...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
Coatings for commercial nuclear power plants need to withstand humidity, radiation exposure, and LOC...
Sump clogging has been identified as a relevant issue after an accident occurred in the Barsebäck 2...
The purpose of the Generic-Safety-Issue (GSI) 191 study is to determine if the transport and accumul...
In the unlikely event of a Loss of Coolant Accident (LOCA) in a pressurized water reactor (PWR), bre...
Generic Safety Issue-191 (GSI-191) was developed by the United States Nuclear Regulatory Commission ...
A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regula...
Different areas in the nuclear facility require protecive coatings which in addition to having the n...
This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanis...
This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated th...
The international Phébus FP (fission product) programme investigated core degradation and radioactiv...
A research program to investigate the performance and potential for debris formation of Service Leve...
For many years, the French "Institut de Radioprotection et de Sûreté Nucléaire" has developed studie...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
Coatings for commercial nuclear power plants need to withstand humidity, radiation exposure, and LOC...
Sump clogging has been identified as a relevant issue after an accident occurred in the Barsebäck 2...
The purpose of the Generic-Safety-Issue (GSI) 191 study is to determine if the transport and accumul...
In the unlikely event of a Loss of Coolant Accident (LOCA) in a pressurized water reactor (PWR), bre...
Generic Safety Issue-191 (GSI-191) was developed by the United States Nuclear Regulatory Commission ...
A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regula...
Different areas in the nuclear facility require protecive coatings which in addition to having the n...
This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanis...
This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated th...
The international Phébus FP (fission product) programme investigated core degradation and radioactiv...