Eventos Anais de eventos
COBEM 2017
24th ABCM International Congress of Mechanical Engineering
Parametric Analysis of the primary circuit of the Angra 1 Nuclear Power Plant PWR type and its applications in the Naval Nuclear Propulsion
Submission Author:
Luiz Chaves , RJ
Co-Authors:
Marcos Curi, Luiz Fernando Silva Ferreira, Luiz Chaves
Presenter: Luiz Chaves
doi://10.26678/ABCM.COBEM2017.COB17-2871
Abstract
In this work we studied the primary circuit of the Angra 1 nuclear power plant, located in Rio de Janeiro, which is based on a Pressurized Water Reactor (PWR) type. A steady-state thermodynamics analysis was made to reach the operational parameters of primary circuit such as pressure, temperature, power generated among others. Previous studies available in literature of 2-loop Westinghouse Nuclear Power Plants, which is based on a PWR and similar to Angra 1, support this analysis in the sense of a correct procedure to deal with many complex processes to energy generation from a nuclear source. Temperature profiles in reactor and steam generator were studied with concepts of thermodynamics, heat transfer and fluid mechanics, showing the behavior into them. And finally, a hypothetical simulation for a nuclear submarine propulsion was made from analysis of all parameters studied from Angra 1, to fit the specifications in this kind of application based on actual designs. Using these concepts, the values of the total thermal power generated in reactor and the fuel rod average linear power presented deviations of 0.38% and 0.45%, respectively, compared with the available values of Angra 1. The maximum power and temperatures reached were lower than the safe operational limits. In the SG, the height of the tubes required to the secondary fluid reach the saturation was determined at 1.4 m for Angra 1 and 0.451 m for nuclear submarine. The results obtained in the naval propulsion simulation are similar with those found in literature.
Keywords
nuclear engineering, energy, Thermodynamics, Mechanical Engineering
