Sartor, P.J.
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France); Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy Villacoublay (France)1988
Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France); Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy Villacoublay (France)1988
AbstractAbstract
[en] The spring is made by a strip folded into two arms gripping a plate of the grid, welds joining the arms through windows of the plate and a U-shaped section to one of the arms bearing against the other arm and of the same width as it
[fr]
Le ressort, utilisable notamment dans un asemblage de combustible pour reacteur a eau sous pression est constitue par une bande repliee pour former deux branches destinees a encadrer une plaquette de grille et a etre solidarisees l'une de l'autre par soudage a travers des fenetres menagees dans la plaquette de grille, une des branches presentant au moins une zone destinee a s'appuyer sur l'autre branche, une forme en U de largeur correspondant a la largeur de l'autre branche dans la meme zoneOriginal Title
Ressort en epingle a cheveux pour assemblage de combustible nucleaire et grille d'assemblage comportant de tels ressorts
Primary Subject
Source
5 Aug 1988; 29 Jan 1987; 11 p; FR PATENT DOCUMENT 2610445/A/; FR PATENT APPLICATION 8701085; Available from Institut National de la Propriete Industrielle, Paris (FR); Application date: 29 Jan 1987
Record Type
Patent
Country of publication
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Bourgoin, J.; Lebuffe, C.; Cazus, A.; Thibault, X.; Monchanin, M.; Sartor, P.J.; Couvreur, F.; Gosset, D.
Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors. Volume 21994
Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors. Volume 21994
AbstractAbstract
[en] One of the criteria for rejecting COntrol Rod Assemblies is the clad cracking linked to the diameter increase at the bottom of the rods. Examinations in Hot Cells have been performed to understand the rod behaviour under operating conditions. Swelling of absorber rod is due to transmutations which lead to modification in the chemical composition of the alloy and, further, to a new phase formation. The cold worked structure of the clad is replaced by many small dislocation loops which lead to grain hardening and low ductility. Under the combined effects of swelling under irradiation and absorber slumping because of creep and repeated shocks, the absorber comes into contact with the cladding. When the gap is closed, the absorber applies a strain to the cladding which cracks. However, the intergranular cracking cannot be only explained by the drastic decrease of cladding ductility under irradiation. As a short-term remedial action, FRAMATOME combines a reduction of diameter in the lower part of the rod with helium rod filling and, in some cases, a decrease of the spring hold down force. (authors). 6 figs., 6 tabs., 11 refs
Original Title
Contribution a la connaissance du comportement sous irradiation des crayons de grappes de commande
Primary Subject
Source
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France); 434 p; 1994; p. 715-725; Societe Francaise d'Energie Nucleaire; Paris (France); International Symposium on the Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors; Colloque International sur la Contribution des Expertises sur Materiaux a la Resolution des Problemes Rencontres dans les Reacteurs a Eau Pressurisee; Fontevraud (France); 12-16 Sep 1994
Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, DEFORMATION, ELEMENTS, ENRICHED URANIUM REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICAL PROPERTIES, NICKEL ALLOYS, NONMETALS, POWER REACTORS, RARE GASES, REACTOR COMPONENTS, REACTORS, STAINLESS STEELS, STEEL-CR19NI10, STEELS, TENSILE PROPERTIES, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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