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Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'

Thesis/Dissertation:

Abstract

After a brief presentation of reported studies made in different countries and regarding the so-called 'reference accident', this research thesis reports the study of reactor re-flooding when the reactor is completely dried and heating elements have reached a temperature between 300 and 900 C, with a constant water flow rate entering the test section, with a constant dissipated electrical power, and by using very simple geometries. After a first part addressing the experimental study, the author reports the development of conduction calculation codes used to compute the flow extracted by the two-phase flow, present the thermal-hydraulic code used to compute local values and to study the correlation of the upstream area exchange coefficient. The author finally reports an analysis of the different existing models and the study of a re-flooding model [French] La presente etude est consacree a l'un des aspects de la surete des reacteurs a eau sous pression, et plus precisement a l'accident tres important qui consiste en une perte de fluide caloporteur (Loss of Coolant Accident - 'LOCA'). Le but de l'etude est de fournir des renseignements necessaires a l'interpretation des experiences effectuees sur des grappes, de donner une correlation de coefficient d'echange dans la zone aval,  More>>
Authors:
Publication Date:
Nov 28, 1975
Product Type:
Thesis/Dissertation
Report Number:
FRCEA-TH-7899
Resource Relation:
Other Information: 97 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: https://www.iaea.org/inis/contacts/index.html; Also available from Reseau des bibliotheques de l'Universite Grenoble Alpes et de Grenoble INP, universite Grenoble Alpes, 621 avenue Centrale 38400 Saint-Martin-d'Heres (France); This record replaces 48018502; These - Transferts Thermiques
Subject:
42 ENGINEERING; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BLOWDOWN; COMPUTER CODES; COMPUTERIZED SIMULATION; CORE FLOODING SYSTEMS; DRYOUT; FINITE DIFFERENCE METHOD; FLOW MODELS; HEAT FLUX; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; THERMAL HYDRAULICS; VARIATIONAL METHODS
OSTI ID:
22574155
Research Organizations:
Institut National Polytechnique de Grenoble, 46 Avenue Felix Viallet, 38000 Grenoble (France); CEA, DEN-DM2S, Grenoble (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR1700238018502
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
310 page(s)
Announcement Date:
Mar 22, 2017

Thesis/Dissertation:

Citation Formats

Andreoni, Daniel. Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'. France: N. p., 1975. Web.
Andreoni, Daniel. Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'. France.
Andreoni, Daniel. 1975. "Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'." France.
@misc{etde_22574155,
title = {Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'}
author = {Andreoni, Daniel}
abstractNote = {After a brief presentation of reported studies made in different countries and regarding the so-called 'reference accident', this research thesis reports the study of reactor re-flooding when the reactor is completely dried and heating elements have reached a temperature between 300 and 900 C, with a constant water flow rate entering the test section, with a constant dissipated electrical power, and by using very simple geometries. After a first part addressing the experimental study, the author reports the development of conduction calculation codes used to compute the flow extracted by the two-phase flow, present the thermal-hydraulic code used to compute local values and to study the correlation of the upstream area exchange coefficient. The author finally reports an analysis of the different existing models and the study of a re-flooding model [French] La presente etude est consacree a l'un des aspects de la surete des reacteurs a eau sous pression, et plus precisement a l'accident tres important qui consiste en une perte de fluide caloporteur (Loss of Coolant Accident - 'LOCA'). Le but de l'etude est de fournir des renseignements necessaires a l'interpretation des experiences effectuees sur des grappes, de donner une correlation de coefficient d'echange dans la zone aval, et de donner aussi un modele de progression du front de trempe pour les analyses de surete. Une etude bibliographique preliminaire nous a permis de faire le point sur les experiences entreprises concernant le refroidissement de secours. Ensuite, les chapitres suivants seront decrits: 1) Le chapitre II, consacre a l'etude experimentale (boucle, sections d'essais, resultats globaux). 2) Le chapitre III ou seront presentes les codes de calcul de conduction, necessaires au calcul du flux extrait par le melange diphasique, le code de thermohydraulique necessaire au calcul des grandeurs locales et l'etude de la correlation du coefficient d'echange de la zone aval. 3) Enfin le chapitre IV ou, apres une analyse des differents modeles existants, sera etudie un modele de remouillage.}
place = {France}
year = {1975}
month = {Nov}
}