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Showing 1 to 4 of 4 for “"GSI-191"”.
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A Study on the Mechanical Characteristics of a Fiberglass Bed Formed During a Loss-of-Coolant-Accident at a PWR Nuclear Facility
… re-circulation pumps from operating correctly. GSI-191 is a Nuclear Regulatory Commission (NRC) initiative to understand the effects a sump blockage would have on emergency cooling systems. Recently, the focus has been on understanding how the fiberglass bed will behave during an accident. An …
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Spatio-temporal probabilistic methodology to estimate location-specific loss-of-coolant accident frequencies for risk-informed analysis of nuclear power plants
… risk-informed resolution of generic Safety Issue 191 (GSI-191). The essence of the risk-informed resolution of GSI-191 is that location-specific LOCA frequencies drive the risk. The most recent NRC-sponsored estimations of LOCA frequencies were developed through an expert elicitation approach, …
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EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR
Generic Safety Issue-191 (GSI-191) was developed by the United States Nuclear Regulatory Commission (U.S. NRC) to assess the effect of debris loading on pressurized water reactor (PWR) emergency core cooling systems (ECCS) sump strainers during a Loss-of-Coolant Accident (LOCA). Potential …
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Investigation of calcium orthophosphate chemical effects in a post-LOCA nuclear reactor containment
Calcium leached from NUKON fiberglass in containment following a Loss of Coolant Accident (LOCA) could lead to the formation of chemical precipitates that in turn cause head-loss increase due to filtering through a fibrous debris accumulation at the sump pump screens. Experiments conducted on the …