Eventos Anais de eventos
ENCIT 2018
Brazilian Congress of Thermal Sciences and Engineering
DEFINITION OF THERMAL HYDRAULIC PROFILE OF A STEAM GENERATOR FOR NAVAL NUCLEAR PROPULSION VIA THERMODYNAMIC ANALYSIS OF ANGRA 1 STEAM GENERATOR
Submission Author:
Luiz Chaves , RJ
Co-Authors:
Luiz Chaves, Yago Souza, Luiz Fernando Silva Ferreira, Marcos Curi
Presenter: Luiz Chaves
doi://10.26678/ABCM.ENCIT2018.CIT18-0369
Abstract
Temperature profiles of U-tubes Steam Generators, applied to nuclear power plants, were not easy to find in the available literature. In this paper, we studied the heat transferred from the primary to secondary circuit of a nuclear power plant located in Rio de Janeiro, Angra 1, which is based on a Pressurized Water Reactor (PWR) type, and a simulation for naval nuclear propulsion was obtained from previous data. A thermodynamics analysis was made to reach out the operation parameters of the Steam Generator such as pressure, temperature and the heat transferred. The temperature profiles in Angra 1 and submarine Steam Generators were determined using numerical solutions of finite differences method, applied to parallel and countercurrent heat exchangers. During the phase change, a constant variation of the enthalpy was considered, making the primary fluid temperature decreases following a linear behavior. The heat rejected from the primary circuit and the tubes length needed for making the secondary fluid reaches the saturation point, in each Steam Generator, was defined, respectively, as 943.14 MWth and 1.4 m for Angra 1 and 42.85 MWth and 0.435 m to Submarine Steam Generator. Using the developed methodology called “Enthalpy Ruler”, the encountered results were considered adequate, since the defined lengths are compatible with the constant variation of the enthalpy from the compressed liquid to saturated steam.
Keywords
nuclear engineering, energy, Thermodynamics, Mechanical Engineering, Steam Generator
