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). | Thermal hydraulic simulations of the Angra 2 PWR EPJ Nuclear Sci. Technol. 1 5 2015 Nuclear Sciences J. González-Mantecón et al. published by EDP Sciences 2015 amp Technologies DOI epjn e2015-50034-2 Available online at http REGULAR ARTICLE Thermal hydraulic simulations of the Angra 2 PWR Javier González-Mantecón Antonella Lombardi Costa Maria Auxiliadora Fortini Veloso Claubia Pereira Patrícia Amélia de Lima Reis Adolfo R. Hamers and Maria Elizabeth Scari Departamento de Engenharia Nuclear Universidade Federal de Minas Gerais Av. Antônio Carlos 6627 Escola de Engenharia Pampulha CEP 31270-901 Belo Horizonte Brazil Received 11 May 2015 Received in final form 15 July 2015 Accepted 17 August 2015 Published online 05 December 2015 Abstract. 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 demonstrates that the developed RELAP5-3D model is capable of reproducing the thermal hydraulic behavior of the Angra 2 PWR and it can contribute to the process of the plant safety analysis. 1 Introduction piping of one of the reactor loops. A variety of break sizes in the cold-leg and hot-leg piping and other parts of the As the global population increases the demand for energy reactor coolant system representing a typical range and and the benefits that it provides also grow up. With the
