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AbstractAbstract
[en] The most important relations are assessed of refractoriness, creep plasticity and the character of damage at long-term creep exploitation of two alternatives of austenitic steel type AISI 316 with variable carbon and nitrogen levels. The single-axis tensile creep tests were performed in the temperature range 600 to 750 degC. Examples are shown of stress and temperature dependence of the time before fracture, of the temperature and time dependence of fracture ductility at creep, and the calculated values of creep tensile strength. For selected melt specimens, microhardness inside austenitic grains was assessed. An electron scanning microscope was used in the study of fracture surfaces. The conclusions were arrived at that the increase in creep plasticity due to restricted formation and proliferation of cavitation damage resulted in increased long-term refractoriness. For cavitation damage proliferation, the most significant factor is the distribution of intergranular precipitate, i.e., M23C6 and M6C particles and of intermetallic phases of sigma, chi and eta, and the strength of their interface to the matrix. (J.B.). 9 figs., 5 tabs., 41 refs
Original Title
Mikrostrukturni aspekty plasticity a lomu pri creepu nestabilizovanych austenitickych CrNiMo oceli
Primary Subject
Source
English translation available from Nuclear Information Center, 156 16 Prague 5-Zbraslav, Czechoslovakia at US$ 10 per page.
Record Type
Journal Article
Journal
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, FAILURES, HARDNESS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Felsen, M.F.; Mottot, M.; Petrequin, P.
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] Structure materials for nuclear reactors undergo different types of mechanical and thermal stresses for period reaching 300 000 hours. Rapid change of temperature, stress, frequency can occurs in case of accident. Determination of mechanical properties (elongation, creep, fatigue...) of materials for structure dimensioning requires extrapolation of fatigue and creep tests. The comparison of results obtained on steel 316 shows that for creep forecastings agreement is good between the different methods but it is not the case for creep fatigue. For creep in variable conditions, agreement between experiments and calculus is good only in some cases. For fatigue test with samples previously tested for creep, or vice versa, results depend upon the damage evaluation
[fr]
Les materiaux de structure des reacteurs nucleaires sont soumis a divers types de sollicitations mecaniques et thermiques pendant des durees pouvant atteindre 300 000 heures. Les conditions de ces sollicitations: temperature, contrainte, frequence... sont de plus susceptibles d'evoluer tres rapidement en cas d'incident ou d'accident. Par consequent, la determination des caracteristiques classiques de traction, fluage, fatigue... de ces materiaux pour les calculs de dimensionnement des structures est inaccessible en echelle reelle du temps. Ceci conduit a extrapoler la duree des temps de maintien en fatigue fluage et celle des essais de fluage jusqu'a des valeurs representatives de celles atteintes en fonctionnement. Ceci conduit egalement a calculer le comportement en fluage en conditions variables a partir de celui etabli a temperature et contrainte constantes en utilisant un modele de calcul de dommages. Des methodes de calcul analogues permettent de prevoir la duree de vie residuelle d'un materiau apres differentes sequences successives de sollicitations. La comparaison des resultats obtenus, montre que si dans le cas du fluage, on obtient souvent des predictions en bon accord entre elles quelle que soit la methode utilisee, il n'en est pas toujours de meme en fatigue fluage. Quant au fluage en conditions variables, on obtient dans certains cas, un excellent accord entre previsions du calcul et resultats experimentaux. Enfin, la prediction des resultats obtenus apres des sequences successives de solliciation, depend de la maniere dont on evalue le dommageOriginal Title
Fatigue et fluage a temperature variable. Prevision dans le temps; steel 316 and 316L
Primary Subject
Source
Mar 1984; 28 p; 5. Mechanics and metallurgy colloquium; Tarbes (France); 14-16 Mar 1984
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NUMERICAL SOLUTION, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Widespread intergranular stress corrosion cracking has occurred at welds in BWR piping systems. ASME Section XI requires that these service flaws be fully evaluated against fatigue crack growth. This paper discusses a data analysis model aimed at developing a correlation for available crack-growth data for stainless steel in PWR as well as BWR environments. Useful presentations of fatigue crack-growth data are obtained by plotting the time rate of crack growth for water environments as a function of the predicted time rate for air environments. The analysis suggests that fatigue crack growth in some stainless/water systems is a time-dependent, corrosion-related phenomenon. However, data for deoxygenated water environment do not indicate time-dependent characteristics. The data also indicate that the ASME Section XI Task Group recommendation for estimating corrosion fatigue crack-growth rates in austenitic piping materials may be unreasonable under certain loading conditions. Additional data are needed to confirm this conclusion. (author)
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
International Journal of Pressure Vessels and Piping; ISSN 0308-0161;
; CODEN PRVPA; v. 31(1); p. 55-68

Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION, CORROSION RESISTANT ALLOYS, ENRICHED URANIUM REACTORS, FATIGUE, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, POWER REACTORS, REACTORS, STAINLESS STEELS, STEELS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Reverse bending creep/fatigue tests have been performed on Type 316 steel at temperatures of 550 and 6000C for test durations of up to 12,000 h. It is shown that endurances obtained are comparable to those observed under push-pull conditions and that the introduction of a hold period can significantly reduce the endurance. Detailed fractography indicates that creep/fatigue in tension is more damaging than creep/fatigue in compression. The crack initiation behaviour is shown to be temperature dependent and may result from the combination of tensile and shear stresses, the relative importance of which will depend on the precise conditions of temperature, stress level and possibly microstructure. (author)
Primary Subject
Record Type
Journal Article
Journal
Fatigue and Fracture of Engineering Materials and Structures; ISSN 8756-758X;
; CODEN FFESE; v. 13(6); p. 551-561

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Rojas-Calderon, E.L.
Universidad Nacional Autonoma de Mexico, Mexico City (Mexico). Facultad de Ciencias1989
Universidad Nacional Autonoma de Mexico, Mexico City (Mexico). Facultad de Ciencias1989
AbstractAbstract
[en] Ion nitriding is a glow discharge process that is used to induce surface modification in metals. It has been applied to 316-L austenitic stainless steel looking for similar benefits already obtained in other steels. An austenitic stainless steel was selected because is not hardenable by heat treatment and is not easy to nitride by gas nitriding. The samples were plastically deformed to 10, 20, 40, 50 AND 70% of their original thickness in order to obtain bulk hardening and to observe nitrogen penetration dependence on it. The results were: an increase of one to two rockwell hardness number (except in 70% deformed sample because of its thickness); an increase of even several hundreds per cent in microhardness knoop number in nitrided surface. The later surely modifies waste resistance which would be worth to quantify in further studies. Microhardness measured in an internal transversal face to nitrided surface had a gradual diminish in its value with depth. Auger microanalysis showed a higher relative concentration rate CN/CFe near the surface giving evidence of nitrogen presence till 250 microns deep. The color metallography etchant used, produced faster corrosion in nitrited regions. Therefore, corrosion studies have to be done before using ion nitrited 316-L under these chemicals. (Author)
Original Title
Nitruracion ionica de acero inoxidable 316=L
Primary Subject
Source
1989; 102 p; Thesis (Bach. Sci.).
Record Type
Miscellaneous
Literature Type
Thesis/Dissertation
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The phenomenological description of the material was a series of interrupted tensile loading with strain-rate change from quasi-static to dynamic. These data clearly showed that the material strength, although strain-rate sensitive, is not affected by the strain-rate history, indicating that a mechanical equation of state could be applied. The Bodner-Partom constitutive theory is first calibrated by the monotonic stress-strain curves collected at steady constant strain rates, then used to predict the response under various types of interrupted strain-rate change tests. (orig./HP)
Primary Subject
Source
8. international conference on high energy rate fabrication; San Antonio, TX (USA); 17-20 Jun 1984
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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AbstractAbstract
[en] In order to produce Tritium by neutron irradiation in a fusion reactor the use of Li or of Lithium bearing materials is essential. The Breeding materials most commonly considered are liquid metals or alloys (Li, Pb-17Li) and ceramics (Li2O, LiAlO2, Li2SiO3, Li4SiO4, Li2ZrO3). The coolants are H2O, the liquid metals for alloys (self cooled concepts) or He. The structural materials envisaged comprise austenitic stainless steels (AISI 316, Cr-Mn steels), ferritic or martensitic steels (HT9, 1.4914). In this paper the main corrosion/compatibility effects are described and the results obtained critically reviewed. Special emphasis is placed on the compatibility between liquid metal or alloy and structural materials relevant to NET (Next European Torus). (author)
Primary Subject
Secondary Subject
Source
European Federation of Corrosion, Brussels (Belgium); European Federation of Corrosion Publications; no. 1; 56 p; ISBN 0-901462-73-X;
; 1989; p. 35-46; The Institute of Metals; London (UK); EUROCORR '87: 1. meeting of the E.F.C. Working Party on nuclear corrosion; Frankfurt am Main (Germany, F.R.); 1987

Record Type
Book
Literature Type
Conference
Country of publication
ALKALI METALS, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CLOSED PLASMA DEVICES, CORROSION RESISTANT ALLOYS, ELEMENTS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LEAD ALLOYS, LOW CARBON-HIGH ALLOY STEELS, METALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, STEELS, THERMONUCLEAR DEVICES, TOKAMAK DEVICES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Hausen, H.; Cundy, M.R.; Schuele, W.
Commission of the European Communities, Luxembourg (Luxembourg)1991
Commission of the European Communities, Luxembourg (Luxembourg)1991
AbstractAbstract
[en] Irradiation creep rates were determined for annealed and cold-worked AMCR- and 316-type steel alloys in the high flux reactor at Petten, for various irradiation temperatures, stresses and for neutron doses up to 4 dpa. Primary creep elongations were found in all annealed materials. A negative creep elongation was found in cold-worked materials for stresses equal to or below about 100 MPa. An increase of the negative creep elongation is found for decreasing irradiation temperatures and decreasing applied stresses. The stress exponent of the irradiation creep rate in annealed and cold-worked AMCR alloys is n = 1.85 and n = 1.1, respectively. The creep rates of cold-worked AMCR alloys are almost temperature independent over the range investigated (573-693 K). The results obtained in the HFR at Petten are compared with those obtained in ORR and EBR II. The smallest creep rates are found for cold-worked materials of AMCR- and US-PCA-type at Petten which are about a factor two smaller than the creep rates obtained of US-316 at Petten or for US-PCA at ORR or for 316L at EBR II. The scatter band factor for US-PCA, 316L, US-316 irradiated in ORR and EBR II is about 1.5 after a temperature and damage rate normalization
Primary Subject
Secondary Subject
Source
1991; 12 p
Record Type
Report
Report Number
Country of publication
ALLOYS, AUSTENITIC STEELS, BARYONS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DEFORMATION, ELEMENTARY PARTICLES, FABRICATION, FERMIONS, HADRONS, HEAT RESISTING ALLOYS, HEAT TREATMENTS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LOW CARBON-HIGH ALLOY STEELS, MATERIALS WORKING, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NUCLEONS, RADIATION EFFECTS, STAINLESS STEELS, STEELS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The present work has been carried out to evaluate the usefulness of the DC methods for corrosion monitoring, and to determine the correlation between results from extrapolation method of cathodic and/or anodic Tafel lines, polarization resistance method and the 3 point method. A comparison has been made between these results and by solution analysis using atomic absorption spectroscopy
Primary Subject
Source
Iraq Atomic Energy Commission, Baghdad (Iraq). Nuclear Research Centre; Annual Report; (1989 issue); [200 p.]; 1989; p. 80; ISSN 1023-6295;
; Available from Information Center-Iraqi Atomic Energy Commission, Tuwaitha-Baghdad, P.O. Box 765, IRAQ

Record Type
Miscellaneous
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CHROMIUM-NICKEL-MOLYBDENUM STEELS, CORROSION RESISTANT ALLOYS, ELEMENTS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, METALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, SPECTROSCOPY, STAINLESS STEELS, STEELS, TRANSITION ELEMENTS
Reference NumberReference Number
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AbstractAbstract
No abstract available
Original Title
Projeto de um coletor de amostra de sodio
Primary Subject
Source
Anon.; Instituto de Engenharia Nuclear, Rio de Janeiro (Brazil); 240 p; 1983; p. 157-158; Published in summary form only.
Record Type
Miscellaneous
Report Number
Country of publication
LanguageLanguage
Reference NumberReference Number
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