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AbstractAbstract
[en] The hydride embrittlement in ZIRCALOY-4 was studied at room temperature and 350 C. Sheet tensile specimens of two fabrication routes in the stress-relieved, recrystallized, and β-treated states were hydrided with or without tensile stress. It was found generally that the effect on strength of increasing hydrogen content was not important. However, for the tensile tests at room temperature, there is a ductile-brittle transition when the hydrogen content is higher than a certain threshold. The prior thermomechanical treatment shifts this transition considerably. In situ scanning electron microscopy (SEM) tests, fractography, and fracture profile observations were carried out to determine the fracture micromechanisms and the microscopic processes. At 20 C, the fracture surfaces are characterized by voids and secondary cracks for low and medium hydrogen contents and by intergranular cracks and decohesion through the continuous hydride network for high hydrogen contents. This phenomenon disappears at 350 C, and the hydrogen seems to exert no more influence on the fracture micromechanism even for very high hydrogen contents (up to 1,500 wt ppm). A full-coverage model is proposed to estimate the critical hydrogen content that makes ZIRCALOY-4 totally brittle. The effect of microstructure on hydride embrittlement in different metallurgical states is thus explained according to the modeling. Special attention is devoted to relating the micromechanisms and the modeling in order to propose the possible measures needed to limit the hydride embrittlement effect
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Journal Article
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Numerical Data
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Metallurgical Transactions. A, Physical Metallurgy and Materials Science; ISSN 0360-2133; ; CODEN MTTABN; v. 25(6); p. 1185-1198
Country of publication
ALLOYS, ALLOY-ZR98SN-4, CHROMIUM ADDITIONS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, DATA, EMBRITTLEMENT, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, INFORMATION, IRON ADDITIONS, MATERIALS, MECHANICAL PROPERTIES, NUMERICAL DATA, REACTOR COMPONENTS, TIN ALLOYS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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AbstractAbstract
[en] Studies results concerning the ageing of zirconium alloys (zircaloy 2 and 4, Zr Nb alloys, and Zr Fe alloys) and its effects on mechanical properties, are presented: after a review of the static and dynamic ageing phenomena and the Portevin Le Chatelier effect, the case of zirconium-oxygen is more especially examined, with emphasis on the tensile and creep properties: interstitial oxygen appears to be the source of a rapid bonding of dislocations which leads to important effects on mechanical properties. Irradiation effects on ageing are also studied. (A.B.)
Original Title
Le vieillissement dynamique dans les alliages de zirconium. Consequences sur les proprietes mecaniques
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Cailletaud, G.; Lemoine, P. (eds.); Institut National des Sciences et Techniques Nucleaires (INSTN), Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France); 317 p; ISBN 2-86883-271-7; ; 1996; p. 25-34; Editions de Physique; Les Ulis (France); Zirconium Meeting: Properties-Microstructures; Gif-sur-Yvette (France); 25-26 Apr 1995; 46 refs.
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Book
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Conference
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ALLOYS, ALLOY-ZR98SN-2, ALLOY-ZR98SN-4, CHALCOGENIDES, CHROMIUM ADDITIONS, CORROSION RESISTANT ALLOYS, CRYSTAL DEFECTS, CRYSTAL STRUCTURE, ELEMENTS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, IRON ADDITIONS, LINE DEFECTS, MATERIALS, MECHANICAL PROPERTIES, METALS, NICKEL ADDITIONS, NONMETALS, OXIDES, OXYGEN COMPOUNDS, POINT DEFECTS, RADIATION EFFECTS, TENSILE PROPERTIES, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENT COMPOUNDS, TRANSITION ELEMENTS, ZIRCALOY, ZIRCONIUM, ZIRCONIUM BASE ALLOYS, ZIRCONIUM COMPOUNDS
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AbstractAbstract
[en] C-Mn steels and associated welds can be susceptible to dynamic strain aging (DSA). In this case, fracture toughness passes through a minimum when the temperature increases from 20 to 300 deg. C. Since Charpy V-Notch data are not affected by the DSA phenomenon, the method for predicting the evolution of J0.2 and dJ/da in the temperature domain where DSA occurs is still an open question. The purpose of the present study is the assessment of this decrease in fracture toughness using a local approach method. The results of J-R tearing resistance tests, characterized by crack initiation resistance J0.2 and tearing modulus dJ/da relative to a base metal (A48 French standard steel) and manual metal arc deposited metals are presented and discussed. The local approach determination of J0.2 was performed using the Rice and Tracey model. Comparisons between experimental results and the results of local approach modelling indicate that both J0.2 and dJ/da decreases with DSA can be correctly predicted
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Source
S0022311501007462; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: Israel
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Journal Article
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Onimus, F.; Monnet, I.; Bechade, J.L.; Prioul, C.; Pilvin, P., E-mail: fabien.onimus@cea.fr2004
AbstractAbstract
[en] Plastic deformation in irradiated zirconium alloys occurs in a very heterogeneous manner at the grain scale by the clearing up of radiation-induced prismatic loops by gliding dislocations and the channeling of these dislocations inside narrow bands of the grain. A statistical TEM investigation of this mechanism has been performed on neutron irradiated recrystallized Zr alloys tested at 350 deg. C. Due to the strong anisotropy of plastic deformation, different loading conditions have been investigated. It is shown that for transverse tensile tests and closed end burst tests, only basal channels are observed, whereas for axial tensile tests, prismatic and pyramidal channels are observed. This phenomenon can be understood in terms of texture and interactions between dislocations and irradiation induced loops. From Schmid factor calculations, we have also been able to prove that irradiation leads to a higher increase of critical resolved shear stresses for prismatic and pyramidal slip systems than for basal slip system
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S0022311504004702; Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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AbstractAbstract
[en] In weakly killed C-Mn steels, the dynamic strain aging (DSA) phenomenon induces an increase in the ultimate tensile strength associated with a ductility loss, usually measured in the 100-200 C temperature range. This phenomenon, which induces large toughness reductions, is not well characterized in the heat affected zones (HAZ) of the welds, since the sensitivity to DSA cannot be directly determined due to the very abrupt microstructure gradients existing in these zones. In order to study the influence of microstructure on DSA, tensile tests were performed on simulated HAZ, resulting from various quenching conditions of C-Mn steels. These results are interpreted through correlations with internal friction results on the same microstructures. It is concluded that the materials which have been submitted to the more severe quenching conditions appear to be less sensitive to DSA. This trend is attributed to the larger density of dislocations which can trap most of the interstitial atoms in these microstructures. Whatever the microstructure, the intensity of DSA, characterized by the ductility loss, is proportional to the Snoek peak height measured by internal friction. This result allows the evaluation of the sensitivity of C-Mn steels to DSA from a unique internal friction test. (orig.)
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38 refs.
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Journal Article
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CARBON STEELS, DISLOCATIONS, ELONGATION, HEAT AFFECTED ZONE, INTERNAL FRICTION, INTERSTITIALS, MANGANESE STEELS, METALLOGRAPHY, MICROSTRUCTURE, QUENCHING, SECONDARY COOLANT CIRCUITS, STRAIN AGING, STRAIN HARDENING, TEMPERATURE DEPENDENCE, TEMPERATURE RANGE 0273-0400 K, TEMPERATURE RANGE 0400-1000 K, TEMPERATURE RANGE 1000-4000 K, TENSILE PROPERTIES, WELDED JOINTS
AGING, ALLOYS, CARBON ADDITIONS, COOLING SYSTEMS, CRYSTAL DEFECTS, CRYSTAL STRUCTURE, DEFORMATION, FRICTION, HARDENING, HEAT TREATMENTS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, LINE DEFECTS, MANGANESE ALLOYS, MECHANICAL PROPERTIES, POINT DEFECTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
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AbstractAbstract
[en] The effect of an applied tensile stress on the hydrides morphology in ZIRCALOY-4 was studied. To this end, the residual stresses around the hydride caused by the hydride precipitation was first evaluated. Considering the disability to predict hydride transformation stresses by ordinary macroscopical mechanical calculation in previous studies, X-ray diffraction (XRD) profile analysis and transmission electron microscopy (TEM) observations were carried out to quantify the microstructural evolution in hydrided ZIRCALOY-4. The residual microstrains and microstresses in the matrix and around the hydride were thus estimated. The big discrepancy between the results and the existing studies were explained by the major self-accommodation of phase transformation deformation remaining inside the hydrides and the local plastic accommodation of ZIRCALOY-4. In order to study the stress effect on hydride orientation and to estimate the hydride orientation threshold stresses, hydrogen was introduced into the specimens under tensile stress. A quantitative technique was used to evaluate the susceptibility to perpendicular hydride formation under the influence of texture, residual stresses, and externally applied tensile stresses, following an improved approach that had been first developed by Sauthoff and then applied to Zr-H system by Puls. Both analytical and experimental results indicate that the threshold stress for producing perpendicular hydrides varies with the microstructural features, the yield strength, and the residual stresses
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Journal Article
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Numerical Data
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Metallurgical Transactions. A, Physical Metallurgy and Materials Science; ISSN 0360-2133; ; CODEN MTTABN; v. 25(6); p. 1199-1208
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AbstractAbstract
[en] A comparative experimental and FEM study has been carried out, in order to investigate dynamic and constraint aspects of the Charpy test. Standard V-notch Charpy specimens were tested under dynamic and static loading conditions. 2-D plane strain and 3-D models were employed in numerical analysis. In order to incorporate strain-rate effects, an elastic-viscoplastic constitutive equation has been applied, based on actual test data obtained for a low-alloy structural steel. Fully dynamic analysis clearly indicated inertial effects. Modal analysis enabled the confirmation of the origin of the oscillations on the load-displacement curve as beam vibration of the specimen resulting from interaction with the elastic striker. (orig.)
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ECF 11: 11. European conference on fracture; Poitiers (France); 1997; 27 refs.
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Journal Article
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Conference
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AbstractAbstract
[en] Stress-strain behavior of 316 LN at 4 K is interpreted in terms of transformation induced plasticity and adiabatic shearing. This interpretation is supported by microscopy observations. Fatigue behavior at 4 K of wrought and weld metal is compared. This study shows that the mechanical properties of the TF coil casings of the TORE SUPRA tokamak are controlled by the mechanical properties of the 316 LN weldments
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Anon; p. 1051-1056; 1987; p. 1051-1056; Pergamon Books Inc; Elmsford, NY (USA); 14. SOFT - symposium on fusion technology; Avignon (France); 8-12 Sep 1986
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Book
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Conference
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CLOSED PLASMA DEVICES, CORROSION RESISTANT ALLOYS, ELECTRIC COILS, ELECTRICAL EQUIPMENT, EQUIPMENT, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEELS, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTOR WALLS, TOKAMAK DEVICES
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Pelchat, J.; Barcelo, F.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction des Technologies Avancees1991
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction des Technologies Avancees1991
AbstractAbstract
[en] This paper is concerned with the influence of δ-hydrides on the mechanical properties of three heat treated cold-rolled Zircaloy-4 sheets (stress-relieved, recrystallized and β treated), tested at room temperature and 3500C. Smooth tensile specimens of two thicknesses: 0.5 and 3.1 mm, containing different hydride volume fractions, up to 18% (about 1400 ppm H), have been tested. Metallographic and fractographic analysis were carried out in order to examine the fracture morphology near and on the fracture surface, and to determine the evolution of the fracture mechanism of hydrides as a function of temperature, hydride orientation and volume fraction
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1991; 6 p; International Topical Meeting on LWR Fuel Performance; Avignon (France); 21-24 Apr 1991
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Report
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Conference
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AbstractAbstract
No abstract available
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Association Euratom-CEA, Centre d'Etudes Nucleaires de Cadarache, 13 Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee; 297 p; 1986; p. DP18; Commissariat a l'Energie Atomique; Cadarache (France); 14. Symposium on fusion technology; Avignon (France); 8-12 Sep 1986; Published in summary form only.
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Book
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Conference
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, FABRICATION, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, JOINING, LOW CARBON-HIGH ALLOY STEELS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, PHASE TRANSFORMATIONS, STAINLESS STEELS, STEELS
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