2018
DOI: 10.1016/j.anucene.2018.01.001
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Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code

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Cited by 17 publications
(8 citation statements)
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“…In order to show how such a DBN structure can be used to provide joint prognostics and diagnostic capabilities aimed at assessing CES health and their potential failures following an accident event, the remainder of this paper will present a sample DBN for modeling and monitoring an SFR reactor in a transient overpower event. This case study is a simplified exercise conducted by Groth et al [1] with the data modifications made by Jankovsky et al [24]. This section will begin with a description of both the SFR and the TOP scenario that the model is designed to monitor.…”
Section: Case Study: Transient Overpower Event (Top) In a Sodium Fastmentioning
confidence: 99%
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“…In order to show how such a DBN structure can be used to provide joint prognostics and diagnostic capabilities aimed at assessing CES health and their potential failures following an accident event, the remainder of this paper will present a sample DBN for modeling and monitoring an SFR reactor in a transient overpower event. This case study is a simplified exercise conducted by Groth et al [1] with the data modifications made by Jankovsky et al [24]. This section will begin with a description of both the SFR and the TOP scenario that the model is designed to monitor.…”
Section: Case Study: Transient Overpower Event (Top) In a Sodium Fastmentioning
confidence: 99%
“…Such an event can be caused by external factors, e.g., an earthquake, that result in a sudden surge of power generation in the reactor. When such an event occurs, the reactor's automatic scram mechanism is expected to respond by inserting control rods into the reactor to greatly reduce power generation; common indicators for the automatic scram mechanism include large power-to-flow readings, as well as high values of reactor pressure, inlet, and outlet temperature [24]. Depending on the cause of the accident, however, scram functions may be impacted, limiting their ability to prevent core reactions from further escalating.…”
Section: Case Study Background-reactor and Accident Descriptionmentioning
confidence: 99%
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