Eventos Anais de eventos
COBEM 2023
27th International Congress of Mechanical Engineering
DEVELOPMENT OF A COMPUTATIONAL CODE FOR THERMODYNAMIC ANALYSIS OF ANGRA 2 AND 3 NUCLEAR POWER PLANTS
Submission Author:
Leon Matos Ribeiro de Lima , RJ , Brazil
Co-Authors:
Tailana Souza, Leon Matos Ribeiro de Lima, Gabriely Carvalho da Silva, Su Jian
Presenter: Leon Matos Ribeiro de Lima
doi://10.26678/ABCM.COBEM2023.COB2023-1849
Abstract
With the 4th Industrial Revolution, many industry sectors are incorporating digital features, such as Internet of Things, Artificial Intelligence, Digital Twin, among others. In this context, the nuclear energy industry also demands for computational tools able to deal with design and operating data. This paper presents a thermodynamic analysis model for Angra 2 and 3 Nuclear Power Plants. It describes the development of a computational code in python that provides process data – temperature, pressure and mass flow rate – under steady state regimes. The basic mathematical models for the power plants processes are presented. The model covers the whole power generation process, including the primary circuit, which is composed by the reactor and cold and hot legs, the secondary cycle, which is the most complex one and consists on a regenerative Rankine power cycle, and the tertiary cycle, which is the sea water inlet and outlet. The three circuits are mainly composed of several heat exchangers (steam generator, pre-heaters, main condensers, coolers etc.), pumps, tanks, valves, the steam turbine and the nuclear reactor. Each one of these components is modeled by means of mass, momentum and energy integral balances, which results in a set of algebraic linear and nonlinear equations. The resulting system of equations is then numerically solved. This model is the continuation of a work started in 2019, based on a computational code developed in Visual Basic which relied on operating data for the moisture separator and some turbine stages. With the current version, a robust simulation tool is provided, able to produce heat balance diagrams for different system configurations. Results are shown for validation cases, by comparisons with heat balance diagrams of Angra 2 NPP for three different cases: (i) normal operation at 100% power load, (ii) normal operation at partial power load and (iii) preheating train bypass.
Keywords
computational model, thermodynamic analysis, Nuclear Power Plants
