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- Title
STC-MOX-Th: Um Novo Código Termo-Hidráulico para Pesquisa e Ensino.
- Authors
dos Santos, Thiago Augusto; de Stefani, Giovanni Laranjo
- Abstract
STC-MOX-Th (Simplified Thermal - Hydraulics Code-Mixed Oxide Thorium) is a program developed in a MATLAB environment that calculates the thermal design limits of a typical Pressurized Water Reactor (PWR), which is the temperature fuel pellet center and the Nuclear Boiling Ratio (DNBR). In addition, other temperature distributions and hydrodynamic coolant quantities such as enthalpy and pressure drop are also calculated. The present work presents the code and shows its peculiarities, such as the fact that it allows calculations with fuels of pure UO2 and proportions of mixed oxide of Uranium / Thorium - MOX (U, Th). These, besides its user-friendly interface, among other characteristics to be presented later, prove that the code can be used in research projects, as well as in disciplines focused on the study of thermohydraulics of nuclear reactors in engineering courses, as in the case of the undergraduate course in Energy Engineering at the Federal University of ABC, where it is an elective course. For data validation, data from Westinghouse's AP-1000 reactor were used. The program showed physical behavior as expected for the model, generating reliable results for any reactor projects (validated with experimental data and other codes), as well as providing students with a more complete experience in the learning of the concepts employed in the area.
- Subjects
NUCLEAR engineering; NUCLEAR reactors; WOOD pellets; THORIUM dioxide; TEMPERATURE distribution; PRESSURIZED water reactors
- Publication
Revista Internacional de Ciências, 2020, Vol 10, Issue 2, p3
- ISSN
2316-7041
- Publication type
Article
- DOI
10.12957/ric.2020.46816