[[abstract]]Thermal-hydraulic calculations using RELAP5/MOD2 are performed to simulate the responses of the Maanshan pressurized water reactor (PWR) power plant when the secondary heat sink is lost. The loss of heat sink transient of primary interest in this study is the loss of off-site power coincident because it is one of the risk-dominant sequences leading to core damage for the Maanshan PWR power plant. The major purpose of this study is to identify the effectiveness of the bleed-and-feed (B&F) operation in mitigating the consequences of the event. Therefore, both with and without B&F, calculations are performed to investigate the system responses under different assumptions[[fileno]]2060134010048[[department]]工程與系統科學
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PW...
[[abstract]]Due to the potential threat of reactor coolant system (RCS) overpressurization, loss-of-...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive r...
This paper discusses the results of the thermal-hydraulic investigations of the Total Loss of Feed W...
[[abstract]]Using a typical Westinghouse 3-loop PWR plant (with a large, dry containment) as the obj...
AbstractThe advanced passive pressurized water reactor (PWR) is being constructed in China and the p...
[[abstract]]A TpSLB accident analysis for Taipower's Maanshan Unit 1 plant is reported. The plant is...
The existing fleet of nuclear power plants is in the process of extending its lifetime and increasin...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
The lack of full understanding of complex mechanisms connected with the interaction between thermal-...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
[[abstract]]Hydrogen combustion is an important phenomenon that may occur during severe accidents of...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PW...
[[abstract]]Due to the potential threat of reactor coolant system (RCS) overpressurization, loss-of-...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive r...
This paper discusses the results of the thermal-hydraulic investigations of the Total Loss of Feed W...
[[abstract]]Using a typical Westinghouse 3-loop PWR plant (with a large, dry containment) as the obj...
AbstractThe advanced passive pressurized water reactor (PWR) is being constructed in China and the p...
[[abstract]]A TpSLB accident analysis for Taipower's Maanshan Unit 1 plant is reported. The plant is...
The existing fleet of nuclear power plants is in the process of extending its lifetime and increasin...
In nuclear power plants the design extension conditions are more complex and severe than those postu...
The lack of full understanding of complex mechanisms connected with the interaction between thermal-...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
[[abstract]]Hydrogen combustion is an important phenomenon that may occur during severe accidents of...
This report gives an account on the development and validation of the RELAP5/Mod3.3 model of the Rin...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PW...