The Experts below are selected from a list of 474 Experts worldwide ranked by ideXlab platform
P Zhang - One of the best experts on this subject based on the ideXlab platform.
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experimental simulation of liquid entrainment in ads 4 depressurization line in ap1000
Progress in Nuclear Energy, 2016Co-Authors: Yan Xiang, Yingwei Wu, W X Tian, P Zhang, G H SuAbstract:Abstract The fourth stage Automatic Depressurization System is an important Passive Safety Feature in Westinghouse AP1000 which enables controlled depressurization of reactor coolant system in small break LOCA. However, large amount of coolant can be carried to the containment via the ADS-4 branch entrainment and the upper plenum entrainment during the depressurization process, which poses great threats to core uncovering and melting. The automatic Depressurization and Entrainment TEst Loop (ADETEL) modeled after AP1000 with a scaling ratio of 1:5.6 was constructed to investigate the entrainment and depressurization behavior after the actuation of ADS-4 valves. The entrainment and depressurization Features were investigated under different initial pressure, mixture liquid level in the pressure vessel and heating power. The entrainment deposition effect of the reactor internals was also investigated. The test data reveals that large amount of water are entrained through the ADS-4 branch line within a short period of time. The liquid entrainment rate and the reduced rate of the mixture liquid level in the pressure vessel increase with the initial system pressure. It is notable that the core uncovery was experienced when the initial pressure was set to 0.5 MPa in current experimental conditions. The reactor internals have little effect on the entrained mass and the mixture liquid levels in the pressure vessel.
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Scaling analysis of AP1000 ADS-4 entrainment and depressurization
Progress in Nuclear Energy, 2014Co-Authors: D.c. Sun, P Zhang, Wen Xi Tian, S.z. Qiu, J.c. LiuAbstract:Abstract ADS-4 is an important Passive Safety Feature in AP1000 design which provides a controlled depressurization. In this paper, reduced diameter and height scaling analysis with identical fluid properties was conducted on AP1000 ADS-4 blowdown and depressurization process. The scaling analysis consisted of ADS-4 branch line entrainment scaling, system depressurization scaling and upper plenum entrainment scaling. Reasonable dimensionless criteria of related thermal hydraulic phenomena were chosen and developed by analyzing conservation equations. Experimental geometric dimensions and operating conditions for the scaled test facility were obtained.
G H Su - One of the best experts on this subject based on the ideXlab platform.
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experimental simulation of liquid entrainment in ads 4 depressurization line in ap1000
Progress in Nuclear Energy, 2016Co-Authors: Yan Xiang, Yingwei Wu, W X Tian, P Zhang, G H SuAbstract:Abstract The fourth stage Automatic Depressurization System is an important Passive Safety Feature in Westinghouse AP1000 which enables controlled depressurization of reactor coolant system in small break LOCA. However, large amount of coolant can be carried to the containment via the ADS-4 branch entrainment and the upper plenum entrainment during the depressurization process, which poses great threats to core uncovering and melting. The automatic Depressurization and Entrainment TEst Loop (ADETEL) modeled after AP1000 with a scaling ratio of 1:5.6 was constructed to investigate the entrainment and depressurization behavior after the actuation of ADS-4 valves. The entrainment and depressurization Features were investigated under different initial pressure, mixture liquid level in the pressure vessel and heating power. The entrainment deposition effect of the reactor internals was also investigated. The test data reveals that large amount of water are entrained through the ADS-4 branch line within a short period of time. The liquid entrainment rate and the reduced rate of the mixture liquid level in the pressure vessel increase with the initial system pressure. It is notable that the core uncovery was experienced when the initial pressure was set to 0.5 MPa in current experimental conditions. The reactor internals have little effect on the entrained mass and the mixture liquid levels in the pressure vessel.
Yan Xiang - One of the best experts on this subject based on the ideXlab platform.
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experimental simulation of liquid entrainment in ads 4 depressurization line in ap1000
Progress in Nuclear Energy, 2016Co-Authors: Yan Xiang, Yingwei Wu, W X Tian, P Zhang, G H SuAbstract:Abstract The fourth stage Automatic Depressurization System is an important Passive Safety Feature in Westinghouse AP1000 which enables controlled depressurization of reactor coolant system in small break LOCA. However, large amount of coolant can be carried to the containment via the ADS-4 branch entrainment and the upper plenum entrainment during the depressurization process, which poses great threats to core uncovering and melting. The automatic Depressurization and Entrainment TEst Loop (ADETEL) modeled after AP1000 with a scaling ratio of 1:5.6 was constructed to investigate the entrainment and depressurization behavior after the actuation of ADS-4 valves. The entrainment and depressurization Features were investigated under different initial pressure, mixture liquid level in the pressure vessel and heating power. The entrainment deposition effect of the reactor internals was also investigated. The test data reveals that large amount of water are entrained through the ADS-4 branch line within a short period of time. The liquid entrainment rate and the reduced rate of the mixture liquid level in the pressure vessel increase with the initial system pressure. It is notable that the core uncovery was experienced when the initial pressure was set to 0.5 MPa in current experimental conditions. The reactor internals have little effect on the entrained mass and the mixture liquid levels in the pressure vessel.
W X Tian - One of the best experts on this subject based on the ideXlab platform.
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experimental simulation of liquid entrainment in ads 4 depressurization line in ap1000
Progress in Nuclear Energy, 2016Co-Authors: Yan Xiang, Yingwei Wu, W X Tian, P Zhang, G H SuAbstract:Abstract The fourth stage Automatic Depressurization System is an important Passive Safety Feature in Westinghouse AP1000 which enables controlled depressurization of reactor coolant system in small break LOCA. However, large amount of coolant can be carried to the containment via the ADS-4 branch entrainment and the upper plenum entrainment during the depressurization process, which poses great threats to core uncovering and melting. The automatic Depressurization and Entrainment TEst Loop (ADETEL) modeled after AP1000 with a scaling ratio of 1:5.6 was constructed to investigate the entrainment and depressurization behavior after the actuation of ADS-4 valves. The entrainment and depressurization Features were investigated under different initial pressure, mixture liquid level in the pressure vessel and heating power. The entrainment deposition effect of the reactor internals was also investigated. The test data reveals that large amount of water are entrained through the ADS-4 branch line within a short period of time. The liquid entrainment rate and the reduced rate of the mixture liquid level in the pressure vessel increase with the initial system pressure. It is notable that the core uncovery was experienced when the initial pressure was set to 0.5 MPa in current experimental conditions. The reactor internals have little effect on the entrained mass and the mixture liquid levels in the pressure vessel.
J.c. Liu - One of the best experts on this subject based on the ideXlab platform.
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Scaling analysis of AP1000 ADS-4 entrainment and depressurization
Progress in Nuclear Energy, 2014Co-Authors: D.c. Sun, P Zhang, Wen Xi Tian, S.z. Qiu, J.c. LiuAbstract:Abstract ADS-4 is an important Passive Safety Feature in AP1000 design which provides a controlled depressurization. In this paper, reduced diameter and height scaling analysis with identical fluid properties was conducted on AP1000 ADS-4 blowdown and depressurization process. The scaling analysis consisted of ADS-4 branch line entrainment scaling, system depressurization scaling and upper plenum entrainment scaling. Reasonable dimensionless criteria of related thermal hydraulic phenomena were chosen and developed by analyzing conservation equations. Experimental geometric dimensions and operating conditions for the scaled test facility were obtained.