Published 2004 | Version v1
Miscellaneous Open

Hydraulic modelling of the CARA Fuel element

  • 1. Comision Nacional de Energia Atomica, San Carlos de Bariloche (Argentina). Disenios Avanzados y Evaluacion Economica
  • 2. Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Materiales
  • 3. Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Ensayos no Destructivos

Description

The CARA fuel element is been developing by the National Atomic Energy Commission for both Argentinean PHWRs. In order to keep the hydraulic restriction in their fuel channels, one of CARA's goals is to keep its similarity with both present fuel elements. In this paper is presented pressure drop test performed at a low-pressure facility (Reynolds numbers between 5x104 and 1,5x105) and rational base models for their spacer grid and rod assembly. Using these models, we could estimate the CARA hydraulic performance in reactor conditions that have shown to be satisfactory. (author)

Availability note (English)

Available from INIS in electronic form

Abstract (Spanish)

Con el objeto de validar la similitud hidraulica del elemento combustible CARA con los actuales combustibles de Atucha y Embalse, se realizaron ensayos de perdida de carga en el circuito CBP del CAC con un nuevo diseno de separador de mejor desempeno hidraulico. Se presenta aqui el analisis de los mismos, de los cuales se validaron modelos de base racional para estimar las restricciones hidraulicas de los distintos componentes estructurales (separadores, grillas y barras combustibles) en funcion del flujo refrigerante. Se estimo asi la caida de presion del CARA dentro del canal combustible Embalse en condiciones nominales de reactor, siendo la misma similar al del combustible actual de 37 barras. (autor)

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Additional details

Additional titles

Original title (Spanish)
Desarrollo hidraulico del combustible CARA

Publishing Information

Publisher
AATN
Imprint Place
Buenos Aires (Argentina)
Imprint Pagination
12 p.
Report number
INIS-AR-C--461

Conference

Title
31. Annual meeting of the Argentine Association of Nuclear Technology
Original Conference Title
AATN 2004: 31. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN)
Acronym
AATN 2004
Dates
23-25 Nov 2004
Place
Buenos Aires (Argentina)

INIS

Country of Publication
Argentina
Country of Input or Organization
Argentina
INIS RN
37052869
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLUID FLOW; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; FUEL RODS; NUCLEAR FUELS; PHWR TYPE REACTORS; PRESSURE DROP; SIMULATION
Descriptors DEC
ENERGY SOURCES; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS

Optional Information

Notes
8 refs., 10 figs., 1 tab.