Filters
Results 1 - 10 of 102
Results 1 - 10 of 102.
Search took: 0.033 seconds
Sort by: date | relevance |
Roche, R.L.; Moulin, D.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques1981
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. des Etudes Mecaniques et Thermiques1981
AbstractAbstract
[en] The new method allows to compute effective primary stress Peff with the help of an efficiency diagram. Distortion of the structure under cyclic loading is near the distortion obtained by the static application of this effective stress. At elevated temperature, the limitation of the value of this effective primary stress at St, insures the limitation of strain at 1%. Therefore it is recommended to use for Peff the same allowable value than for conventional primary stress. Such a recommendation is very different from the current practice at low temperature. It has been pointed out that this current practices tolerates very much larger elongation under cyclic load than under static load
Original Title
progressive distortion
Primary Subject
Source
Aug 1981; 14 p; 6. International conference on structural mechanics in reactor technology (6. SMIRT); Paris, France; 17 - 21 Aug 1981
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Moulin, D.; Roche, R.L.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
AbstractAbstract
[en] This paper presents a simplified method of analysis of buckling of thin structures like those of L.M.F.B.R.'s. The edification of the method is very similar to methods used for buckling of beams and columns having initial geometric imperfections and buckling in the plastic range. Particular attention is paid to the stress hardening of material involved (austenitic steel) and to possible unstable post buckling of thin structures. The analysis method is based on elastic calculation and diagrams that take into account various initial geometric defects
Primary Subject
Secondary Subject
Source
Jun 1984; 22 p; 4. US national conference on pressure vessel and piping technology; San Antonio, TX (USA); 17-21 Jun 1984; 21 refs.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Roche, R.; Moulin, D.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
AbstractAbstract
[en] Fatigue behaviour is essentially dependent on the real strain range, but the current practice is the use of elastic analysis. In low cycle fatigue conditions where inelastic strains predominate, elastic analysis never gives the real value of the strain range. In order to use these results some corrections are necessary. One of these corrections is due to the Poisson's effect (the Poisson ratio in inelastic behaviour is higher than in elastic behaviour). In this paper a method of correction of this effect is proposed. It consists in multiplying the results of the elastic analysis by a coefficient called Kν. A method to draw curves giving this coefficient Kν as a function of results of elastic analysis is developped. Only simple analytical computations using the unixial cyclic curve are needed to draw these curves. Examples are given. The proposed method is very convenient and low cost effective
[fr]
Le dommage de fatigue depend fortement de la variation de deformation reelle. La pratique courante est de faire appel a une analyse elastique pour evaluer ce dommage. Dans les conditions de fatigue oligocyclique ou les deformations inelastiques sont predominantes, l'analyse elastique sous-estime la valeur reelle de la variation de deformation. Pour neanmoins utiliser les resultats de cette analyse, diverses corrections doivent etre faites. L'une d'entre elles concerne l'effet de Poisson (le coefficient de Poisson ν est plus grand quand le comportement est inelastique que lorsqu'il est elastique). Dans cette note une methode de correction de l'effet de Poisson en plasticite est proposee. Elle consiste simplement a multiplier le resultat du calcul elastique par un coefficient baptise Kν. Une methode de determination de ce coefficient Kν en fonction du resultat de calcul elastique est developpee. Elle repose sur de simples calculs analytiques et utilise la courbe cyclique uniaxiale du materiau. Des exemples sont donnes. La procedure proposee est facile d'emploi et tres peu couteuseOriginal Title
Correction de l'effet de Poisson dans une analyse elastique de la fatigue oligocyclique
Primary Subject
Source
May 1984; 41 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Moulin, D.; Maury, A.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
AbstractAbstract
[en] Many investigators tried to reproduce by inelastic calculations the experimentally observed behavior. Unfortunately, the material characteristics used in the computer code were established from monotonic tensile tests performed with specimens extracted from the plate product itself (1,45 mm thick) employed to construct the ratchetting specimen. It seems that, at the present time, cyclic behavior of the material is much more relevant to the observed phenomenon. So the need is expressed to make this of characterization. Nevertheless, the practical problem is to produce cyclic stresses, i.e. tensile and compressive stresses, with very thin specimen. The main difficulty is, in particular, to present buckling effect. It is described a new special device set up for this particular purpose. The adopted solution was to create uniformly distributed alternative pure bending stresses in the thin plate specimen. The bending moments are produced by two end-grips fixed to the specimen, and these grips are mounted on a conventional test machine which is displacement-controlled. In order to reduce tensile and compressive membrane stresses inside the specimen, the grips have two parallel axles of rotation. Forces produced by the machine and displacements of a few points of the specimen are continuously recorded during the test, so that cyclically stabilisized bending moment can be easily evaluated for each variation of curvature imposed. It is furnished the very first experimental cyclic data obtained for the material of the sodium test specimen, a 316 type stainless steel, at room temperature. Finally it is worth noticing that the specimen are of very simple fabrication and are for this reason not expansive
Primary Subject
Secondary Subject
Source
Aug 1983; 13 p; 7. Conference on structural mechanics in reactor technology; Chicago, IL (USA); 22-26 Aug 1983
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALKALI METALS, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DIMENSIONS, ELEMENTS, HARDENING, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICAL PROPERTIES, METALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEELS, TESTING
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Development of leak before break methodology in nuclear industry requires determination of conditions of crack stability in piping products. Due to tough and strain-hardening materials involved, a promising parameter to characterize such a behaviour seems to be the driving force J. An experimental program is carrying on in CEA at Saclay in order to establish and to verify analytical and experimental methods to predict conditions of crack stability. It concerns circumferentially cracked tubes. The through wall crack center angles range from 300 to 1500. Blunt end notches are considered, as well as fatigue precracked notches. Loading is imposed monotonically in displacement controlled conditions until maximal load is reached. The paper will present experimental procedure and first results obtained. Instrumentation and typical recordings (load, rotations at different distances from crack section, crack opening displacement, electric potential drop, ovalization) will be described. Experimental results are interpreted in terms of limit analysis and J estimation to predict crack initiation and maximal loads as a function of crack length. Results obtained permit the adjustment of experimental scaling functions usually employed for J evaluation with one single specimen. These functions are compared with analytical ones based on theoretical considerations of a simple limit state of the pipe cracked section
Primary Subject
Source
1989; 9 p; 2. Conference on pipework and operation; London (UK); 21-22 Feb 1989
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DEFORMATION, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INDUSTRY, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MECHANICAL PROPERTIES, MECHANICS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The paper provides a survey of the creep-fatigue design rules for the LMFBR in France. These rules are the ones currently implemented in French component manufacturing. The background of each item is discussed and the trends for improvements currently investigated are described. The creep-fatigue rules apply to elastic analysis only. (orig.)
Primary Subject
Source
1. international seminar on construction codes and engineering mechanics; Paris (France); 26-27 Aug 1985
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Moulin, D.; Roche, R.L.; Autrusson, B.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1983
AbstractAbstract
[en] During the operation of nuclear plants, components experience low-cycle fatigue due to thermal transients. A good knowledge of the local strain range is therefore highly desirable for low-cycle fatigue analysis. There are two basic discrepancies between the plastic behaviour of the material and the linear elastic model. The first is the non-linear stress/strain relationship, which mainly affects the strain range in the vicinity of stress raisers. The second is that plastic deformation shows no change in volume. This paper covers the corrective action related to this absence of volume variation. Current practice is to require that stresses are evaluated on an elastic basis, although with a P.R. (Poisson's ratio) value different from the elastic P.R. This procedure is rather inconvenient, and seldom used. It appears preferable to use an alternative rule requiring only multiplying the computed equivalent elastic strain range by a corrective factor. Under plane stress conditions (e.g., close to a wall), the actual equivalent strain range can be computed using an equivalent P.R. This permits deriving the corrective factor Ksub(ν) and plotting curves showing Ksub(ν) as a function of the elastic strain range for a given material
Primary Subject
Source
Aug 1983; 12 p; 7. Conference on structural mechanics in reactor technology; Chicago, IL (USA); 22-26 Aug 1983
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Moulin, D.; Combescure, A.; Acker, D.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Etudes Mecaniques et Thermiques1987
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Etudes Mecaniques et Thermiques1987
AbstractAbstract
[en] This paper highlights the main items emerging from a large bibliographical survey carried out on strain-induced buckling analysis methods applicable in the building of fast neutron reactor structures. The work is centred on the practical analysis methods used in construction codes to account for the strain-buckling of thin and slender structures. Methods proposed in the literature concerning past and present studies are rapidly described. Experimental, theoretical and numerical methods are considered. Methods applicable to design and their degree of validation are indicated
Primary Subject
Source
1987; 21 p; Seminar on inelastic analysis and life prediction on high temperature environment; Lausanne (Switzerland); 24-25 Aug 1987
Record Type
Report
Literature Type
Conference; Bibliography
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Moulin, D.; Combescure, A.; Acker, D.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Inst. de Recherche Technologique et de Developpement Industriel (IRDI)1986
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Inst. de Recherche Technologique et de Developpement Industriel (IRDI)1986
AbstractAbstract
[en] This report is a State of the Art about practical methods to analyze buckling risks mainly due to thermal stresses in slender shell structures. A critical review of theoretical, numerical and experimental results available in open literature till 1986 is performed. They are particularly examined from the point of view of simplicity in the formulations and experimental validation. The final aim of this study is an attempt to propose analysis method of practical use for engineers. Most of used informations were obtained from aeronautic and nuclear (fast breeder reactors) domains
[fr]
Ce rapport presente un ''Etat de l'Art'' sur les methodes pratiques permettant de prendre en compte les risques de flambage dus en particulier aux contraintes thermiques dans les structures en coques tres souples. Une revue critique des methodes et resultats theoriques, numeriques et experimentaux disponibles dans la litterature jusqu'a l'annee 1986 est faite. L'examen porte sur le degre de developpement des methodes (formulation-validation experimentale) en vue de proposer des methodes d'analyse utilisables par l'ingenieur. La plupart des informations sont obtenues dans le domaine de l'aeronautique et du nucleaire (reacteurs a neutrons rapides)Original Title
Etat de l'art sur les methodes pratiques de dimensionnement vis-a-vis du flambage sous deformation des structures souples
Primary Subject
Secondary Subject
Source
Dec 1986; 92 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Green, D.; Moulin, D.; Hooton, D.; Drubay, B.
Principles of fracture mechanics applications in nuclear power plants1995
Principles of fracture mechanics applications in nuclear power plants1995
AbstractAbstract
[en] The purpose of this paper is to describe and compare published methodologies available in Europe to perform crack assessment in nuclear components operating at elevated temperatures and where creep can play an important role. It concerns mainly the methods proposed in UK by the R5 rules and in France by Appendix A16 of RCC-MR, and developed mainly for fast breeders reactor applications. The paper is a summary presentation of the available rules, their domain of applications and gives references to the associated validation works (experimental and numerical). The organisation of the rules is very similar in both procedures: high and low temperature domains, evaluation of different phases in the crack behavior, and initiation and propagation under normal conditions and then stability analysis under accidental loading. Both procedures use the fracture mechanics parameters KI, C*, σref. J parameter is explicitly calculated in A16 procedure whereas the R6 Failure Assessment Diagram approach, which is derived from a generalised J-estimation scheme in terms of the materials stress-strain curve, avoids J-calculation. The two methods described were considered in the writing of procedures proposed for the assessment of the design of EFR and discussed in the framework of AGT9B agreement. (J.S.). 20 refs., 7 figs
Primary Subject
Secondary Subject
Source
Acker, D.; CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie; 394 p; ISBN 2-7272-0177-X; ; May 1995; p. 59-70; Centre d'Etudes de Saclay; Gif-sur-Yvette (France); SISSI 94: International Seminar on Structural Integrity; Saclay (France); 28-29 Apr 1994
Record Type
Book
Literature Type
Conference
Country of publication
AUSTENITIC STEELS, CEA, COMPUTERIZED SIMULATION, CRACK PROPAGATION, CREEP, DEFECTS, DUCTILITY, ELASTICITY, ELECTRICITE DE FRANCE, FAILURES, FBR TYPE REACTORS, FINITE ELEMENT METHOD, FRACTURE MECHANICS, FRACTURE PROPERTIES, IN-SERVICE INSPECTION, PLASTICITY, REACTOR COMPONENTS, SERVICE LIFE, STRESS ANALYSIS, STRESS INTENSITY FACTORS, TEMPERATURE RANGE 0400-1000 K, WELDED JOINTS
ALLOYS, BREEDER REACTORS, CALCULATION METHODS, CARBON ADDITIONS, EPITHERMAL REACTORS, FAST REACTORS, FRENCH ORGANIZATIONS, INSPECTION, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, LIFETIME, MECHANICAL PROPERTIES, MECHANICS, NATIONAL ORGANIZATIONS, NUMERICAL SOLUTION, REACTORS, SIMULATION, STEELS, TEMPERATURE RANGE, TENSILE PROPERTIES, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |