Published 1974
| Version v1
Report
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Model for determining stresses in the structure of a fast reactor fuel assembly
Description
Deformations in a reactor core are due to two metallurgical phenomena, swelling of the steel under irradiation and irradiation creep when the structure is under stress. The first step is to determine the deformation of each sub-assembly supposed free, subjected to a neutron flux or temperature gradient, and the second is to study the interactions amongst most of the sub-assemblies. Under the influence of the deformations the interaction value will change with time, and this development must be determined. Calculation methods were developed for the purpose. A number of computing codes already exist and it is necessary to complete them, modify them if necessary, create new ones as the case arises and form a coherent whole
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
Les deformations dans un coeur de reacteur proviennent de deux phenomenes metallurgiques, le gonflement de l'acier sous irradiation et le fluage d'irradiation dans le cas ou la structure est contrainte. Une premiere etape consiste a determiner la deformee de chacun des assemblages supposes libres, soumis a un gradient de flux neutronique ou de temperature et la deuxieme etape a etudier les interactions entre la plupart des assemblages. Sous l'effet de ces deformations la valeur des interactions va se modifier dans le temps, et il est necessaire de determiner cette evolution. Pour cela on a mis au point des methodes de calcul. Un certain nombre de codes de calcul existent deja, et il faut les completer, les modifier s'il y a lieu, en creer de nouveau eventuellement, et articuler l'ensembleFiles
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Additional details
Additional titles
- Original title (French)
- Etablissement d'un modele de determination des contraintes dans la structure d'un assemblage combustible de reacteur de puissance de la filiere a neutrons rapides
Publishing Information
- Imprint Pagination
- vp.
- Report number
- FRNC-TH--601
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 7242704
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- BENDING; CREEP; FINITE ELEMENT METHOD; FUEL ASSEMBLIES; H CODES; HEXAGONAL CONFIGURATION; LMFBR TYPE REACTORS; PHYSICAL RADIATION EFFECTS; REACTOR CORES; STRAINS; STRESS ANALYSIS
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; CONFIGURATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS