Fuel rod computations. The COMETHE code in its CEA version
Description
The COMETHE code (COde d'evolution MEcanique et THermique) is intended for computing the irradiation behavior of water reactor fuel pins. It is concerned with steadily operated cylindrical pins, containing fuel pellet stacks (UO2 or PuO2). The pin consists in five different axial zones: two expansion chambers, two blankets, and a central core that may be divided into several stacks parted by plugs. As far as computation is concerned, the pin is divided into slices (maximum 15) in turn divided into rings (maximum 50). Information are obtained for each slice: the radial temperature distribution, heat transfer coefficients, thermal flux at the pin surface, changes in geometry according to temperature conditions, and specific burn-up. The physical models involved take account for: heat transfer, fission gas release, fuel expansion, and creep of the can. Results computed with COMETHE are compared with those from ELP and EPEL irradiation experiments
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
Le code COMETHE (COde d'evolution MEcanique et THermique) a pour objectif de decrire le comportement en cours d'irradiation de crayons combustibles pour reacteurs a eau. Il est concu pour traiter en regime permanent les crayons de geometrie cylindrique, contenant un empilement de pastilles combustibles (UO2 ou PuO2). Axialement, le crayon peut comporter au maximum 5 zones differentes: deux chambres d'expansion, deux couvertures, et un coeur central pouvant etre divise en plusieurs empilements elementaires separes par des bouchons. Pour le calcul le crayon est divise en tranches (maximum 15), elles-memes divisees en couronnes (maximum 50). Le code fournit pour chaque tranche: la distribution radiale des temperatures, les coefficients de transfert de chaleur, le flux thermique a la surface de la gaine, la geometrie a chaud et a froid, et la combustion massique. Les modeles physiques utilises dans le programme prennent en compte: le transfert de chaleur, le degagement des gaz de fission, l'expansion du combustible et le fluage de la gaine. On compare les resultats calcules a l'aide de COMETHE et ceux des programmes d'irradiation experimentaux ELP et EPELFiles
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Additional details
Additional titles
- Original title (French)
- Le calcul du combustible en barreaux. Presentation du code COMETHE dans sa version utilisee au CEA
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- CEA-CONF--3466
Conference
- Title
- French-Soviet seminar on the water-cooled reactors.
- Dates
- 18 Feb 1976.
- Place
- Saclay, France.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 8281682
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; C CODES; CREEP; FISSION PRODUCT RELEASE; FUEL DENSIFICATION; FUEL PELLETS; FUEL PINS; HEAT TRANSFER; MATHEMATICAL MODELS; PHYSICAL RADIATION EFFECTS; PLUTONIUM DIOXIDE; URANIUM DIOXIDE; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; ENERGY TRANSFER; FUEL ELEMENTS; MECHANICAL PROPERTIES; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES