2020
DOI: 10.1016/j.net.2019.09.014
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Effect of critical flow model in MARS-KS code on uncertainty quantification of large break Loss of coolant accident (LBLOCA)

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Cited by 3 publications
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“…Basically, it is a limitation of the flow velocity (flow rate) due to the compressibility of the flowing media for a given pressure difference between the upstream and downstream reservoirs [8]. It occurs during several Design Basis Accidents (DBA) and, especially, for Loss of Coolant Accidents (LOCA) [11]. The thermalhydraulic system codes like RELAP, TRACE, or CATHARE [12][13][14][15][16][17] are dedicated and able to properly predict this effect, as it plays an important role in the safety assessment, regulatory process, and design of safety systems in nuclear power plants (NPP) [18].…”
Section: Introductionmentioning
confidence: 99%
“…Basically, it is a limitation of the flow velocity (flow rate) due to the compressibility of the flowing media for a given pressure difference between the upstream and downstream reservoirs [8]. It occurs during several Design Basis Accidents (DBA) and, especially, for Loss of Coolant Accidents (LOCA) [11]. The thermalhydraulic system codes like RELAP, TRACE, or CATHARE [12][13][14][15][16][17] are dedicated and able to properly predict this effect, as it plays an important role in the safety assessment, regulatory process, and design of safety systems in nuclear power plants (NPP) [18].…”
Section: Introductionmentioning
confidence: 99%