Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant is a pressurized water reactor (PWR) type with electrical output of about 1350 MW. In the present work, the thermal hydraulic RELAP5-3D code was used to develop a model of this reactor. The model was performed using geometrical and material data from the Angra 2 final safety analysis report (FSAR). Simulations of the reactor behavior during steady state and loss of coolant accident were performed. Results of temperature distribution within the core, inlet and outlet coolant temperatures, coolant mass flow, and other parameters have been compared with the reference data and demonstrated to be in good agreement with each other. This study demo...
[EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. Th...
Many power utilities worldwide are applying for power uprates, i.e. for increasing the power output ...
Passive systems are being implemented in several advanced reactors already constructed, under constr...
Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant...
The safety analysis of research reactors includes simulations of selected cases classified by the In...
The present paper porposes a study of a loss of coolant accident of a PWR reactor through a Full Sco...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
The RELAP5/MOD3.3 code has been applied for thermal hydraulic analysis of power reactors as well as ...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear rea...
BAGIRA - a thermal-hydraulic program complex was primarily developed for using it in nuclear power p...
The purpose of this work is to develop a Severe Accident (SA) analysis in Angra 2 Nuclear Power Plan...
Este trabalho visa verificar a integridade da contenção do reator de Angra 2, com uma abordagem mais...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PW...
[EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. Th...
Many power utilities worldwide are applying for power uprates, i.e. for increasing the power output ...
Passive systems are being implemented in several advanced reactors already constructed, under constr...
Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant...
The safety analysis of research reactors includes simulations of selected cases classified by the In...
The present paper porposes a study of a loss of coolant accident of a PWR reactor through a Full Sco...
In Nuclear power plants, simulation of the thermal hydraulic systems at loss of flow, accidents is c...
The RELAP5/MOD3.3 code has been applied for thermal hydraulic analysis of power reactors as well as ...
Due to the character of the original source materials and the nature of batch digitization, quality ...
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear rea...
BAGIRA - a thermal-hydraulic program complex was primarily developed for using it in nuclear power p...
The purpose of this work is to develop a Severe Accident (SA) analysis in Angra 2 Nuclear Power Plan...
Este trabalho visa verificar a integridade da contenção do reator de Angra 2, com uma abordagem mais...
AbstractThis paper describes the approach to model Loss of Coolant Accident (LOCA) in the 900MWe Nuc...
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PW...
[EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. Th...
Many power utilities worldwide are applying for power uprates, i.e. for increasing the power output ...
Passive systems are being implemented in several advanced reactors already constructed, under constr...