Experimental study of the correction factor for the grid by-pass orifices inlet pressure drop for the new core of the RA 6 reactor
- 1. Instituto Balseiro, San Carlos de Bariloche (Argentina)
- 2. Comision Nacional de Energia Atomica, San Carlos de Bariloche (AR). Div. Termohidraulica
Description
It is necessary to determine the pressure drop in the different components in order to calculate the total pressure drop of RA-6 reactor core. Some of these components have simple geometries and the calculation of its pressure drop is relatively easy. But in some cases, the sub-channels where the cooling water flows have non uniform cross sections and its geometries are not in the handbook. Due to changes in the design of components of the new nucleus of the RA-6 it was necessary to perform a new set of full-scale experiments to determine the pressure drop in some affected subchannels. Different gaps between fuel elements are considered in order to take into account the design allowances. With the obtained results we calculate correction coefficients for the pressure loss coefficients. These coefficients allow fitting the model of calculation with the results obtained in the experiments and they were used to calculate the flow distribution in the core. (author)
Availability note (English)
Available from INIS in electronic formAbstract (Spanish)
Para calcular la caida de presion total del nucleo del reactor RA-6 es necesario determinar la perdida de carga en sus componentes. Algunos de estos componentes tienen geometrias simples por lo que el calculo de su caida de presion es relativamente sencillo. Pero en algunos casos, los subcanales por donde pasa el agua de refrigeracion son de secciones muy cambiantes y sus geometrias no se encuentran en los libros de calculo. Debido a cambios en el diseno de componentes del nuevo nucleo del RA-6 fue necesario realizar nuevos ensayos con un arreglo en escala 1:1 para determinar la caida de presion en algunos subcanales afectados. Para tomar en cuenta las tolerancias del diseno se variaron los espacios entre celdas y se barrio un rango de caudales dentro de los posibles a utilizar en operacion normal. Con los resultados obtenidos se calcularon coeficientes de correccion para los coeficientes de perdida concentrada que permite ajustar el modelo de calculo con los resultados obtenidos en los experimentos. Estos coeficientes de correccion fueron utilizados para calcular la distribucion de caudales en el nucleo. (autor)Files
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Additional details
Additional titles
- Original title (Spanish)
- Determinacion experimental del factor de correccion para la perdida de carga en la acometida a los agujeros de la grilla para la nueva geometria del nuevo nucleo del RA 6
Publishing Information
- Publisher
- AATN
- Imprint Place
- Buenos Aires (Argentina)
- Imprint Pagination
- 11 p.
- Report number
- INIS-AR-C--558
Conference
- Title
- 34. Annual meeting of the Argentine Association of Nuclear Technology: Nucleo electricity: the solution
- Original Conference Title
- AATN 2007: 34. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN): Nucleoelectricidad: la solucion
- Acronym
- AATN 2007
- Dates
- 19-23 Nov 2007
- Place
- Buenos Aires (Argentina)
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 40030669
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING SYSTEMS; FLOW RATE; FLUID-STRUCTURE INTERACTIONS; PRESSURE DROP; RA-6 REACTOR; REACTOR CORES
- Descriptors DEC
- ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 9 figs., 2 tabs.