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Results of the irradiation of mixed UO{sub 2} - PuO{sub 2} oxide fuel elements; Resultats d'irradiation d'elements combustibles en oxyde mixte UO{sub 2} - PuO{sub 2}

Abstract

In order to study the behaviour of fuel elements used for the first charge of the reactor Rapsodie, a first batch of eleven needles was irradiated in the reactor EL3 and then examined. These needles (having a shape very similar lo that of the actual needles to be used) were made up of a stack of sintered mixed-oxide pellets: UO{sub 2} containing about 10 per cent of PuO{sub 2}. The density was 85 to 97 per cent of the theoretical, value. The diametral gap between the oxide and the stainless steel can was between 0,06 and 0,27 mm. The specific powers varied from 1230 to 2700 W/cm{sup 3} and the can temperature was between 450 and 630 C. The maximum burn-up attained was 22000 MW days/tonne. Examination of the needles (metrology, radiography and {gamma}-spectrography) revealed certain macroscopic changes, and the evolution of the fuel was shown by micrographic studies. These observations were used, together with flux measurements results, to calculate the temperature distribution inside the fuel. The volume of the fission gas produced was measured in some of the samples; the results are interpreted taking into account the temperature distribution in the oxide and the burn-up attained. Finally a study  More>>
Authors:
Mikailoff, H; Mustelier, J P; Bloch, J; Ezran, L; Hayet, L [1] 
  1. Commissariat a l'Energie Atomique, Fontenay-aux-Roses (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1966
Product Type:
Technical Report
Report Number:
CEA-R-3066
Resource Relation:
Other Information: 27 refs; PBD: 1966
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; BURNUP; FUEL ELEMENTS; GAMMA SPECTROSCOPY; MIXED OXIDE FUELS; POST-IRRADIATION EXAMINATION; SODIUM; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY; X-RAY RADIOGRAPHY
OSTI ID:
20621994
Research Organizations:
CEA Fontenay-aux-Roses, 92 (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR05R3066065645
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
[96] pages
Announcement Date:

Citation Formats

Mikailoff, H, Mustelier, J P, Bloch, J, Ezran, L, and Hayet, L. Results of the irradiation of mixed UO{sub 2} - PuO{sub 2} oxide fuel elements; Resultats d'irradiation d'elements combustibles en oxyde mixte UO{sub 2} - PuO{sub 2}. France: N. p., 1966. Web.
Mikailoff, H, Mustelier, J P, Bloch, J, Ezran, L, & Hayet, L. Results of the irradiation of mixed UO{sub 2} - PuO{sub 2} oxide fuel elements; Resultats d'irradiation d'elements combustibles en oxyde mixte UO{sub 2} - PuO{sub 2}. France.
Mikailoff, H, Mustelier, J P, Bloch, J, Ezran, L, and Hayet, L. 1966. "Results of the irradiation of mixed UO{sub 2} - PuO{sub 2} oxide fuel elements; Resultats d'irradiation d'elements combustibles en oxyde mixte UO{sub 2} - PuO{sub 2}." France.
@misc{etde_20621994,
title = {Results of the irradiation of mixed UO{sub 2} - PuO{sub 2} oxide fuel elements; Resultats d'irradiation d'elements combustibles en oxyde mixte UO{sub 2} - PuO{sub 2}}
author = {Mikailoff, H, Mustelier, J P, Bloch, J, Ezran, L, and Hayet, L}
abstractNote = {In order to study the behaviour of fuel elements used for the first charge of the reactor Rapsodie, a first batch of eleven needles was irradiated in the reactor EL3 and then examined. These needles (having a shape very similar lo that of the actual needles to be used) were made up of a stack of sintered mixed-oxide pellets: UO{sub 2} containing about 10 per cent of PuO{sub 2}. The density was 85 to 97 per cent of the theoretical, value. The diametral gap between the oxide and the stainless steel can was between 0,06 and 0,27 mm. The specific powers varied from 1230 to 2700 W/cm{sup 3} and the can temperature was between 450 and 630 C. The maximum burn-up attained was 22000 MW days/tonne. Examination of the needles (metrology, radiography and {gamma}-spectrography) revealed certain macroscopic changes, and the evolution of the fuel was shown by micrographic studies. These observations were used, together with flux measurements results, to calculate the temperature distribution inside the fuel. The volume of the fission gas produced was measured in some of the samples; the results are interpreted taking into account the temperature distribution in the oxide and the burn-up attained. Finally a study was made both of the behaviour of a fuel element whose central part was molten during irradiation, and of the effect of sodium which had penetrated into some of the samples following can rupture. (author) [French] Afin d'etudier le comportement des elements combustibles destines a la premiere charge du reacteur Rapsodie, une premiere serie de onze aiguilles a ete irradiee dans le reacteur EL3 et examinee apres irradiation. Ces aiguilles (aux caracteristiques geometriques tres proches de celles des aiguilles definitives) etaient constituees d'un empilement de pastilles frittees en oxyde mixte UO{sub 2} a 10 pour cent environ de PuO{sub 2}, dont la densite etait comprise entre 85 et 97 pour cent de la densite theorique. Le jeu diametral entre l'oxyde et la gaine en acier inoxydable etait compris entre 0,06 et 0,27 mm. Les puissances specifiques ont varie de 1230 a 2700 W/cm{sup 3} et la temperature de la gaine etait situee entre 450 et 630 C, Le taux de combustion maximal atteint a ete de 22000 MWj/t. L'examen des aiguilles (metrologie, radiographie et spectrographie {gamma}) a revele certaines modifications macroscopiques, et l'evolution du combustible a ete mise en evidence par la micrographie. On a utilise ces observations, avec les resultats des mesures de flux, pour calculer la repartition des temperatures a l'interieur du combustible. Le volume des gaz de fission degages a ete mesure dans certaines aiguilles: les resultats sont interpretes en liaison avec la repartition des temperatures dans l'oxyde et le taux de combustion atteint. Enfin on a examine d'une part, le comportement d'un element combustible dont la partie centrale etait fondue pendant l'irradiation, et d'autre part, l'action du sodium entre dans certaines aiguilles dont la gaine s'etait rompue. (auteur)}
place = {France}
year = {1966}
month = {Jul}
}