Sauzay, M.; Mottot, M.; Noblecourt, M.; Allais, L.; Monnet, I.; Perinet, J.
CEA Saclay, Dept. d'Etudes du Comportement des Materiaux, DECM, Service de Recherche en Metallurgie Appliquee, 91 - Gif sur Yvette (France)2003
CEA Saclay, Dept. d'Etudes du Comportement des Materiaux, DECM, Service de Recherche en Metallurgie Appliquee, 91 - Gif sur Yvette (France)2003
AbstractAbstract
[en] This paper aims to simulate the behavior of some alloys in high temperature fatigue-relaxation (creep), for a long hold time (one month for each cycle) when laboratory experiments are difficult to realize. The first part presents an estimation of the internal intergranular stresses. The second part deals with the recovery occurring during the hold time. (A.L.B.)
Original Title
Modelisation de l'ecrouissage intragranulaire en fatigue des metaux a haute temperature avec temps de maintien
Primary Subject
Source
2003; 1 p; Colloquium of the GFAC on the high temperature intergranular strain hardening simulation in fatigue of materials with hold time; Colloque du GFAC sur la Modelisation de l'ecrouissage intragranulaire en fatigue des metaux a haute temperature avec temps de maintien; Metz (France); 9-10 Apr 2003
Record Type
Miscellaneous
Literature Type
Conference
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Sauzay, M.; Mottot, M.; Noblecourt, M.; Allais, L.; Monnet, I.; Perinet, J.
CEA Saclay, Dept. des Materiaux pour le Nucleaire, DMN, 91 - Gif-sur-Yvette (France)2003
CEA Saclay, Dept. des Materiaux pour le Nucleaire, DMN, 91 - Gif-sur-Yvette (France)2003
AbstractAbstract
[en] This study aims at foreseeing the behaviour of some alloys during high temperature fatigue-relaxation (creep) conditions when the maximum deformation is maintained during long times (about a month for each cycle). Such experiments can hardly be performed with laboratory tests. A simple modeling of the restoration occurring during the keeping of the conditions of deformation can explain the absence of dislocation microstructures. Abstract only. (J.S.)
Original Title
Modelisation de l'ecrouissage intragranulaire en fatigue des metaux a haute temperature avec temps de maintien
Primary Subject
Source
2003; 1 p; GFAC colloquium; Colloque du GFAC; Metz (France); 9-10 Apr 2003; 6 refs.
Record Type
Miscellaneous
Literature Type
Conference
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Gilbon, D.; Seran, J.L.; Maillard, A.; Touron, H.; Rivera, C.; Lorant, H.; Perinet, J.; Rabouille, O.
Materials for nuclear reactor core applications. 2 v1987
Materials for nuclear reactor core applications. 2 v1987
AbstractAbstract
[en] The aim of this work is to give a general comparison of the swelling behaviours of two Ti-stabilized austenitic steels (type 316 and 15 Cr-15 Ni). The irradiation of samples at 5000C shows that 15-15Ti SS swells less than 316 Ti SS only when irradiated in the cold-worked state. The irradiation of these two cold-worked alloys as fuel pin cladding shows that the higher swelling resistance of 15-15 Ti steels is only clearly established in the temperature range 450-5500C. Moreover this steel may exhibit large swelling variability from cast to cast. Transmission electron microscopy examinations are used to understand the origin of the swelling variability of cold worked 15-15 Ti steel and its difference of behaviour with cold worked 316 Ti steel in the upper range of irradiation temperature. (author)
Primary Subject
Source
British Nuclear Energy Society, London; 454 p; ISBN 0 7277 1306 X; ; 1987; v. 1 p. 307-312; British Nuclear Energy Society; London (UK); International conference on materials for nuclear reactor core applications; Bristol (UK); 27-29 Oct 1987; Price Pound 60.00
Record Type
Book
Literature Type
Conference; Numerical Data
Country of publication
ALLOYS, AUSTENITIC STEELS, BARYONS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, DATA, DEFORMATION, ELECTRON MICROSCOPY, ELEMENTARY PARTICLES, FABRICATION, FERMIONS, HADRONS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS WORKING, MICROSCOPY, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NUCLEONS, NUMERICAL DATA, RADIATION EFFECTS, STAINLESS STEELS, STEELS
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Sauzay, M.; Mottot, M.; Allais, L.; Noblecourt, M.; Monnet, I.; Perinet, J., E-mail: sauzay@cea.fr2004
AbstractAbstract
[en] In the past, a lot of experimental studies have been devoted to creep-fatigue interactions in austenitic stainless steels. Tests have been carried mainly at temperatures of at least 600 deg. C and at high applied strains, which are supposed to be the most damaging. The present work is dedicated to mechanical tests, TEM observations and lifetime predictions at 550 deg. C which corresponds to the real industrial temperature in Liquid Metal Fast Breeder Reactors. It is shown that if pure fatigue test results are close to those performed at 600 deg. C, some of the creep-fatigue results are different, particularly for small applied strains which correspond once more to the industrial conditions. In the 0.25-0.3% strain amplitude range, the stress is larger with hold time than without whatever is the hold time up to 5 h. The numbers of cycles to failure are greatly reduced and no saturation with the hold time is observed, contrary to higher temperature results. The stress-strain behaviour is discussed considering several high temperature mechanisms such as ageing, recovery and viscoplasticity and using TEM observations and stress partitioning into kinematic, isotropic and thermal stresses. Finally, a simple linear damage accumulation model is applied to the 550 deg. C and 600 deg. C tests, using the measured stresses. The stress dependence on hold time can partly explain the observed failure results on fatigue life
Primary Subject
Secondary Subject
Source
S0029-5493(04)00189-X; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, ELECTRON MICROSCOPY, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, IRON ALLOYS, IRON BASE ALLOYS, LIFETIME, LIQUID METAL COOLED REACTORS, MATERIALS TESTING, MECHANICAL PROPERTIES, MICROSCOPY, REACTORS, STEELS, STRESSES, TEMPERATURE RANGE, TESTING, TRANSITION ELEMENT ALLOYS
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