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Atabek, R.; Contenson, G. de; Houdaille, B.; Lestiboudois, G.; Vignesoult, N.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1979
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1979
AbstractAbstract
[en] The two principal types of fuel elements studied are unstable oxide elements in 15x15 geometry and stable oxide elements in 17x17. Semi-statistical processing of the fission gas amounts released was performed on different fuel elements at specific burn-up varying between 2000 and 40,000 MWd/t U and linear powers between 250 and 600 W/cm. This study enabled the following essential points to be stated at this burn-up level: the swelling of the oxide appears to be less than predicted by the linear law (S=0.75 %/10,000 MWd/t U); the migration of volatile fission products is relatively low and without effect on the behavior of the fuel element; strong zircaloy 4 claddings exhibit little creep and their hydriding is insignificant. On a more general level, the analyses of the fission gases performed in the fuel elements after irradiation show an increase of the fraction released with specific burn-up at a given linear power or central temperature
[fr]
Les deux principaux types d'elements combustibles etudies sont des elements a oxyde instable en geometrie 15x15 et des elements a oxyde stable en geometrie 17x17. Un traitement semi statistique des quantites de gaz de fission degagees a ete realise sur differents elements combustibles a des combustions massiques variant de 2000 a 40000 MWj/t U et des puissances lineaires comprises entre 250 et 600 W/cm. Cette etude a permis de preciser a ce niveau de combustion massique les points essentiels suivants: le gonflement de l'oxyde semble inferieur a celui prevu par la loi lineaire (G=0,75 %/10000 MWj/t d'U); la migration des produits de fission volatils est relativement faible et sans consequence sur la tenue de l'element combustible; les gaines en zircaloy 4 fort presentent peu de fluage et leur hydruration est negligeable. Sur un plan plus general les analyses des gaz de fission effectuees dans les elements combustibles apres irradiation mettent en evidence une augmentation de la fraction degagee avec la combustion massique a puissance lineaire ou temperature centrale donneeOriginal Title
Comportement d'elements combustibles UO2-Zy pour centrales de puissance jusqu'a 40000 MWj/t U
Primary Subject
Source
1979; 10 p; 2. European nuclear conference (ENC 79); Hamburg, Germany, F.R; 6 - 11 May 1979
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHEMICAL REACTIONS, DATA, DATA FORMS, DEFORMATION, FLUIDS, INFORMATION, ISOTOPES, MECHANICAL PROPERTIES, NUMERICAL DATA, OXIDES, OXYGEN COMPOUNDS, RADIATION EFFECTS, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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