Measurement of the in-pile core temperature of an EL-4 pencil element, first charge (can of type-347 stainless steel, 0.4 mm thick, UO2 fuel, 11 mm diameter). Determination of the apparent thermal conductivity integral of in-pile UO2
Creators
- 1. Commissariat a l'Energie Atomique, Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)
Description
The core temperature of a pencil fuel element depends on the thermal conductivity of the UO2, and on the UO2-can contact. This temperature may be known accurately only if in-pile tests using the actual geometry are carried out. The test described concerns the measurement of the core- temperature of an EL-4 fuel element, first charge, having a stainless steel can. This temperature is measured at the center of the in-pile pencil element using a high-temperature thermocouple (W-Re with Ta sheath). The element is subjected to operating conditions similar to those of EL-4, both for the specific power and the can temperature and for the pressure acting on the can. The specific power is obtained in the EL-3 reactor using a slightly higher enrichment for the UO2 than that planned for EL-4. The required can temperature and pressure are obtained using a Zircaloy-2 irradiation container filled with NaK, adapted for use in the EL-3 reactor. The core temperatures of the UO2, and that of the can surface are measured. The power is calculated from the heat exchanges in the container calibrated in the laboratory. The temperature drop at the UO2-can interface is deduced from laboratory measurements carried out under comparable heat flux conditions, and in a gas atmosphere corresponding to the beginning of the life-time of the fuel element. It is possible to draw an integral conductivity curve. It is also possible to check the temperature distribution in the oxide, as deduced from the thermal conductivity integral, by micro-graphic examination of the oxide structure. (authors)
Availability note (English)
Available from INIS in electronic formAbstract (French)
La temperature a coeur d'un crayon combustible est fonction de la conductibilite thermique de l'UO2, mais aussi du contact UO2-gaine. Les essais de mesure en geometrie reelle en pile sont les seuls qui permettent d'avoir une connaissance exacte de cette valeur. L'essai dont il est question dans ce rapport a trait a la mesure de la temperature a coeur d'un element combustible EL-4, type premier jeu, a gaine en acier inoxydable. On mesure cette temperature au coeur du crayon en pile a l'aide d'un thermocouple pour haute temperature: tungstene-rhenium a gaine tantale. Le crayon est place dans des conditions de fonctionnement analogues a celles de EL-4, tant en ce qui concerne la puissance specifique et la temperature sur gaine que la pression externe sur la gaine. La puissance specifique est obtenue dans le reacteur EL-3 avec un enrichissement de l'UO2 legerement superieur a celui normalement prevu pour EL-4. La temperature de gaine et la pression visees sont realisees a l'aide d'un conteneur d'irradiation en zircaloy-2 et a remplissage NaK, adapte, aux conditions du reacteur EL-3. - Les temperatures de l'UO2 a coeur, et de la surface de la gaine etant mesurees; - La puissance etant calculee a partir des echanges thermiques dans le conteneur etalonne en laboratoire; - La chute de temperature au contact UO2-gaine etant deduite de mesures faites en laboratoire dans des conditions de flux calorifique comparables et sous une atmosphere de gaz correspondant au debut de la vie de l'element combustible; on peut tracer la courbe integrale de conductibilite. Les examens micro-graphiques de la structure de l'oxyde permettent de verifier la repartition des temperatures dans l'oxyde, deduite de l'integrale de conductibilite thermique. (auteurs)Files
35044297.pdf
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Additional details
Additional titles
- Original title (French)
- Mesure de la temperature a coeur en pile d'un crayon EL-4 1er jeu (gaine acier inoxydable, nuance 347 - epaisseur 0,4 mm - combustible UO
Publishing Information
- Imprint Pagination
- [58 p.]
- Report number
- CEA-R--3041
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 35044297
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- EL-4 REACTOR; FUEL CANS; FUEL PINS; FUEL-CLADDING INTERACTIONS; IN CORE INSTRUMENTS; POST-IRRADIATION EXAMINATION; REACTOR CORES; STAINLESS STEELS; TEMPERATURE DISTRIBUTION; TEMPERATURE MEASUREMENT; THERMAL CONDUCTIVITY; THERMOCOUPLES; URANIUM DIOXIDE; ZIRCALOY 2
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOY-ZR98SN-2; ALLOYS; CARBON ADDITIONS; CARBON DIOXIDE COOLED REACTORS; CHALCOGENIDES; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER MODERATED REACTORS; HIGH ALLOY STEELS; HWGCR TYPE REACTORS; IRON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MEASURING INSTRUMENTS; NICKEL ADDITIONS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR INSTRUMENTATION; REACTORS; STEELS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 15 refs.