Revista: | Journal of the Brazilian Society of Mechanical Sciences |
Base de datos: | PERIÓDICA |
Número de sistema: | 000312038 |
ISSN: | 0100-7386 |
Autores: | Lima, Rita de Cassia Fernandes de1 Carajilescov, Pedro2 |
Instituciones: | 1Universidade Federal de Pernambuco, Departamento de Engenharia Mecanica, Recife, Pernambuco. Brasil 2Universidade Federal Fluminense, Departamento de Engenharia Mecanica, Niteroi, Rio de Janeiro. Brasil |
Año: | 2000 |
Volumen: | 22 |
Número: | 4 |
Paginación: | 613-622 |
País: | Brasil |
Idioma: | Inglés |
Tipo de documento: | Artículo |
Enfoque: | Experimental |
Resumen en inglés | In nuclear reactors, the occurrence of critical heat flux leads to fuel rod overheating with clad fusion and radioactive products leakage. To predict the effects of such phenomenon, experiments are performed using electrically heated rods to simulate operational and accidental conditions of nuclear fuel rods. In the present work, it is performed a theoretical analysis of the drying and rewetting front propagation during a critical heat flux experiment, starting with the application of an electrical power step from steady state condition. After the occurrence of critical heat flux, the drying front propagation is predicted. After a few seconds, a power cut is considered and the rewetting front behavior is analytically observed. Studies performed with various values of coolant mass flow rate show that this variable has more influence on the drying front velocity than on the rewetting one |
Disciplinas: | Ingeniería, Física y astronomía |
Palabras clave: | Ingeniería de energéticos, Termodinámica y física estadística, Termohidráulica, Flujo de calor, Rehumedecimiento, Secado, Simulación numérica |
Keyword: | Engineering, Physics and astronomy, Energy engineering, Thermodynamics and statistical physics, Thermalhydraulics, Heat flow, Rewetting, Drying, Numerical simulation |
Texto completo: | Texto completo (Ver HTML) |