[[abstract]]This paper reports on a small-break loss-of-coolant accident (LOCA) analysis for Taipower's Kuosheng Unit 1 plant. The target plant is a boiling water reactor-6/MARK III design with a rated power of 2895 MW(thermal). The event sequences were first analyzed using the MAAP2.0 and MAAP3.0 codes. Detailed phenomena pertaining to burnings and containment failure were studied through varying values of two input parameters, TZOOFF and TCFLAM, in MAAP2.0. The major differences between these two versions of the MAAP code are in the description of the primary system, core melt model, H/sub 2/ burning mode, and fission product transport mechanism. In both versions, the Mark III containment areas include pedestal cavity, dry well, wet well,...
AbstractIn this study, the large break loss of coolant accident (LBLOCA) analysis model is establish...
Calculations of a large-break loss-of-coolant accident (LOCA) in a 15 {times} 15 generic four-loop W...
As a latest developed computational code, TRACE is expected to be useful and effective for analyzing...
[[abstract]]Reports on a series of small-break LOCA analyses for a typical Westinghouse 3-loop PWR, ...
[[abstract]]According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-o...
[[abstract]]The long-term responses of the reactor coolant system and the containment of a boiling w...
In this study the parameter identification tool (PIT) for the loss-of-coolant accident (LOCA) of a B...
In this study the parameter identification tool (PIT) for the loss-of-coolant accident (LOCA) of a B...
[[abstract]]A TpSLB accident analysis for Taipower's Maanshan Unit 1 plant is reported. The plant is...
To secure high efficiency and temperature margin of nuclear power plant system, most of nuclear reac...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]A series of MAAP3.0 calculations was made with varying parameters to simulate a postulat...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...
A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has b...
AbstractIn this study, the large break loss of coolant accident (LBLOCA) analysis model is establish...
Calculations of a large-break loss-of-coolant accident (LOCA) in a 15 {times} 15 generic four-loop W...
As a latest developed computational code, TRACE is expected to be useful and effective for analyzing...
[[abstract]]Reports on a series of small-break LOCA analyses for a typical Westinghouse 3-loop PWR, ...
[[abstract]]According to Maanshan Unit 1 plant probabilistic risk assessment (PRA), the small loss-o...
[[abstract]]The long-term responses of the reactor coolant system and the containment of a boiling w...
In this study the parameter identification tool (PIT) for the loss-of-coolant accident (LOCA) of a B...
In this study the parameter identification tool (PIT) for the loss-of-coolant accident (LOCA) of a B...
[[abstract]]A TpSLB accident analysis for Taipower's Maanshan Unit 1 plant is reported. The plant is...
To secure high efficiency and temperature margin of nuclear power plant system, most of nuclear reac...
Debris generated during the blowdown phase of a Loss of Coolant Accident (LOCA) is a big concern in ...
[[abstract]]A series of MAAP3.0 calculations was made with varying parameters to simulate a postulat...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...
A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has b...
AbstractIn this study, the large break loss of coolant accident (LBLOCA) analysis model is establish...
Calculations of a large-break loss-of-coolant accident (LOCA) in a 15 {times} 15 generic four-loop W...
As a latest developed computational code, TRACE is expected to be useful and effective for analyzing...