Use of local approach for predicting fatigue cracks in sleeves subjected to repeated thermal shocks
Creators
- Masson, Jean-Claude1
- Centre National de la Recherche Scientifique - CNRS (France)
- Commissariat a l'Energie Atomique - CEA (France)
- Direction des Recherches, Etudes et Techniques - DRET (France)
- Electricite de France - EDF, Centre de Recherches Les Renardieres, Moret-sur-Loing (France)
- Framatome, Courbevoie (France)
- Ministere de la Recherche et de la Technologie - MAT (France)
- National Science Foundation - NSF (United States)
- 1. Electricite de France - EDF, Service Reacteurs Nucleaires et Echangeurs, Les Renardieres, BP 1, F-77250 Moret-sur-Loing (France)
Description
In pressurized-water nuclear plants, certain parts of the circuits have special zone where, for construction reasons, there is a slot that causes a high concentration of stresses. This is the case in particular of nozzles, protected by sleeves, which are subjected to numerous transients and thermal shocks. Loop tests have been carried out on models to evaluate the risk of the initiation or propagation of cracks in these structures. These appear after a few hundred cycles (500) of 210 deg. C amplitude and attain a depth of the order of one millimetre at 3000 cycles. To analyse how these fatigue cracks begin, an original method based on local approach has been developed in France. A law giving the number of cycles to initiate a crack in terms of the stress σθθ has been determined experimentally by numerous rupture mechanics tests on samples. Concordance of calculation and tests has been very satisfactory and has validated this method for thermal shocks on axisymmetrical structures. It is however desirable that an analogous method should be developed and validated for situations in which the plasticity is not confined. (author)
Abstract (French)
Dans les centrales nucleaires a eau pressurisee, certaines parties des circuits comportent des zones singulieres ou, par construction, un effet d'entaille provoque de fortes concentrations de contraintes. C'est le cas notamment des piquages, proteges par des manchettes, qui sont soumis a de nombreux transitoires et chocs thermiques. Des essais sur boucle ont ete effectues sur des maquettes pour evaluer le risque d'amorcage et de propagation de fissures dans ces structures. Celles-ci apparaissent apres quelques centaines de cycles (500) d'amplitude 210 deg. C et atteignent une profondeur de l'ordre du millimetre a 3000 cycles. Pour analyser l'amorcage des fissures de fatigue, une methode originale basee sur l'approche locale a ete developpee en France. Une loi donnant le nombre de cycles a l'amorcage en fonction de la contrainte σθθ a ete determinee exper iment1;1lement par de no111breux essais d'eprouvettes de mecanique de la rupture. L'accord calcul-experience est tres satisfaisant et permet de valider cette methode dans le cas de chocs thermiques sur des structures axisymetriques. Il est souhaitable cependant de developper et de valider une methode analogue pour les situations ou la plasticite n'est pas confinee. (auteur)Files
52064535.pdf
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Additional details
Additional titles
- Original title (French)
- Utilisation de l'approche locale pour la prevision de la fissuration par fatigue de manchettes soumises a des chocs thermiques repetes
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-FR--21-0881
Conference
- Title
- International seminar on local approach of fracture
- Original Conference Title
- Seminaire international sur l'approche locale de la rupture
- Dates
- 3-5 Jun 1986
- Place
- Moret-sur-Loing (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52064535
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AMPLITUDES; CRACKS; FINITE ELEMENT METHOD; NUMERICAL SOLUTION; PLASTICITY; PWR TYPE REACTORS; RUPTURES; SLEEVES; STRESSES; THERMAL CYCLING; THERMAL SHOCK
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; FAILURES; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses