Thermohydraulics in rod bundles and critical heat flux in transient conditions in a tube
Creators
- 1. CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France). Service des Transferts Thermiques
- 2. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)
Description
After the determination of the scaling factor of Stevens's similitude for the pressure range of pressurized water vectors by comparison of critical heat flux data in from and in water, some examples of studies performed with freon are shown. The efficiency of the mixing vanes of spacer grids has been determined on the mixing phenomenon in single phase on critical heat flux. A calculation performed with the code FLICA using subchannel analysis on freon data transposed in water is in good agreement with the experiment. The influence of the number of spacer grids has been also shown. Critical heat fluxes have been determined in water at 140 bar in steady state and transient conditions on two tubular test sections. During the transient tests the flow rate was reduced by half in 0.5 seconds and the reincreased heat flux and inlet temperature remaining constant. These tests have shown the validity of the method which consists in using a critical heat flux correlation determined in steady state conditions applied with local transient conditions of enthalpy and mass velocity computed with the FLICA code
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
Apres la determination du facteur d'echelle de similitude de Steven pour le domaine de pressions des reacteurs a eau pressurisee par comparaison des flux de chaleur critique dans le freon et l'eau, on donne des exemples d'etudes faites avec le freon. L'efficacite des vannes de melange des grilles d'espacement a ete determinee par le phenomene de melange en phase simple et le flux de chaleur critique. Un calcul fait avec le code FLICA, en employant une analyse en sous-canaux sur les donnees du freon transposees a l'eau est en bon accord avec l'experience. On montre aussi l'influence des grilles d'espacement. Les flux de chaleur critique ont ete determines dans l'eau a 140 bars dans les conditions de regimes permanent et transitoire sur deux sections tubulaires test. Pendant les tests en transitoire le debit etait reduit de moitie en 0,5 seconde et le flux de chaleur et la temperature d'entree restent constants. Ces tests ont montre la validite de la methode qui consiste a employer une correlation de flux de chaleur critique determinee dans les conditions du regime permanent et appliquee dans les conditions locales transitoires d'enthalpie et de vitesse massique pour les calculs sur ordinateur avec le code FLICAFiles
7252300.pdf
Files
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Additional details
Additional titles
- Original title (French)
- Thermohydraulique des grappes et flux critique en regime transitoire sur un tube
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- CEA-CONF--3398
Conference
- Title
- thermophysics of water cooled reactors.
- Acronym
- French-Soviet colloquium
- Dates
- 07 Oct 1974.
- Place
- Moscow, USSR.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 7252300
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; F CODES; FREONS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; LIQUID FLOW; PWR TYPE REACTORS; SIMULATION; SPACERS; TRANSIENTS; TUBES
- Descriptors DEC
- BOILING; COMPUTER CODES; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; NUCLEATE BOILING; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS