| Revista: | Journal of the Brazilian Society of Mechanical Sciences |
| Base de datos: | PERIÓDICA |
| Número de sistema: | 000312039 |
| ISSN: | 0100-7386 |
| Autores: | Franco, Carlos Bastos1 Carajilescov, Pedro2 |
| Instituciones: | 1Centro Tecnológico da Marinha em Sao Paulo, Sao Paulo. Brasil 2Universidade Federal Fluminense, Departamento de Engenharia Mecanica, Niteroi, Rio de Janeiro. Brasil |
| Año: | 2000 |
| Volumen: | 22 |
| Número: | 4 |
| Paginación: | 599-612 |
| País: | Brasil |
| Idioma: | Inglés |
| Tipo de documento: | Artículo |
| Enfoque: | Analítico |
| Resumen en inglés | Fuel elements of PWR type nuclear reactors consist of rod bundles, arranged in a square array, and held by spacer grids. The coolant flows, mainly, axially along the rods. Although such elements are laterally open, experiments are performed in closed type test sections, originating the appearance of subchannels with different geometries. In the present work, utilizing a test section of two bundles of 4x4 pins each, experiments were performed to determine the friction and the grid drag coefficients for the different subchannels and to observe the effect of the grids in the crossflow, in cases of inlet flow maldistribution |
| Disciplinas: | Ingeniería, Física y astronomía |
| Palabras clave: | Ingeniería de energéticos, Ingeniería química, Termodinámica y física estadística, Reactores nucleares, Flujo, Distribución, Presión, Fricción, Mallas |
| Keyword: | Engineering, Physics and astronomy, Chemical engineering, Energy engineering, Thermodynamics and statistical physics, Nuclear reactors, Flow, Distribution, Pressure, Friction, Grids |
| Texto completo: | Texto completo (Ver HTML) |
