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Jones, W.B.; Van Den Avyle, J.A.
Sandia National Labs., Albuquerque, NM (USA)1982
Sandia National Labs., Albuquerque, NM (USA)1982
AbstractAbstract
[en] A test program was conducted under contract to Sandia National Laboratories to investigate water/steam effects on elevated temperature low cycle fatigue and creep-fatigue of Alloy 800. This report presents interpretation and analysis of the test results. Tubular specimens with water sealed inside were cycled to failure under strain control. Tests were conducted to 616K (6500F) and 922K (12000F); some at 922K included tensile or compressive hold periods to simulate creep-fatigue conditions. The tubular specimens showed significantly lower lives than solid bar specimens cycled at equivalent strain ranges. Rough internal surfaces contributed to early crack initiation with these specimens. Inclusion of hold periods caused further large reductions in cycles to failure
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May 1982; 49 p; Available from NTIS., PC A03/MF A01 as DE82019220
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Report
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James, L.A.
Westinghouse Hanford Co., Richland, Wash. (USA)1973
Westinghouse Hanford Co., Richland, Wash. (USA)1973
AbstractAbstract
No abstract available
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Nov 1973; 22 p; Pressure vessels and piping-materials-nuclear conference; Miami Beach, Florida, USA; 24 Jun 1974; CONF-740606--7
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AbstractAbstract
[en] Alloy 800 (Sandvik-Sanicro 31) has been subjected to fully reversed push-pull strain controlled tests at 6000C. High and low strain rates were imposed by controlling the test frequency. The conditions for these strain rates were chosen on the basis of fracture analysis. The failure at the low strain rate was entirely intercrystalline whereas that at the high strain rate was completely transcrystalline and striated. Tests were carried out by mixing sequences of cyclic creep (intercrystalline) and fatigue damage. On considering the accumulation of damage in a non-linear manner, it was found that this approach gave a unified explanation to the observed results. It is shown that interaction occurs between the cyclic creep and fatigue mechanisms after a certain amount of prior damage has been imposed. (author)
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Francois, D; p. 2379-2384; ISBN 0 08 025428 4; ; 1982; p. 2379-2384; Pergamon Press; Oxford; 5. International conference on fracture; Cannes, France; 29 Mar - 3 Apr 1981
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AbstractAbstract
No abstract available
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Conference on pressure vessels and piping; Miami Beach, FL; 24 Jun 1974
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Journal Article
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Journal of Engineering Materials and Technology; v. 96(4); p. 249-254
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AbstractAbstract
No abstract available
Original Title
Der Heissdampfkreislauf fuer Korrosionsversuche unter Waermeuebergang: Entwurf, Betrieb und erste Ergebnisse
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Journal Article
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Journal of Nuclear Materials; v. 52(2); p. 204-214
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AbstractAbstract
No abstract available
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Journal Article
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Metallography; v. 7(1); p. 59-68
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Robert, G.
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France)1982
CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France)1982
AbstractAbstract
[en] The influence of precipitation (ν') on the cyclic behaviour of alloy 800 is studied with the help of the analyze of microstructures. The precipitation (ν') induces an increase of the maximum strain and the most important cyclic hardening is obtained for the material with the biggest precipitates. With the consideration of this microstructural data, the strenghtening stage of the alloy is described in the behaviour law from two different theorical concepts
[fr]
L'examen de microstructures a permis d'analyser l'influence de la precipitation (ν') sur le comportement cyclique de l'alliage 800. La precipitation ν' provoque une augmentation de la contrainte maximale et le durcissement cyclique le plus important est obtenu pour le materiau contenant les plus gros precipites. En se basant sur ces donnees microstructurales, la formulation de la loi de comportement a abouti a des descriptions de l'etape de consolidation a partir de deux approches theoriques differentesOriginal Title
Influence de la microstructure sur le comportement en fatigue oligocyclique de l'alliage 800 a 5500C
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Oct 1982; 5 p; Autumn metallurgy meeting; Paris (France); 19 - 21 Oct 1982
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Moeller, R.H.; Martin, J.M.
A status review of alloy 800. Proceedings of a British Nuclear Energy Society conference at the University of Reading on 25th and 26th September 19741975
A status review of alloy 800. Proceedings of a British Nuclear Energy Society conference at the University of Reading on 25th and 26th September 19741975
AbstractAbstract
[en] The AMSE Boiler Code development of design stresses and their optimization for alloys 800 and 800H for conventional and nuclear power plants have coincided with many successful trial installations of these grades of alloy 800. These trial installations, along with laboratory tests, have shown that alloy 800H can be used for long times with a retention of good mechanical properties, including ductility. While gamma prime can be formed, it soon loses its detrimental effect on ductility in service. Sensitization of the alloy also occurs but it, too, has a decreasing effect on corrosion resistance with time in service, especially at elevated temperatures. The authors discuss all of these aspects and conclude that alloy 800 perhaps with low carbon control in the annealed (1800 to 1950degF)(982 to 1066degC) condition gives the optimum combination of properties to 1050degF(566degC) and alloy 800H (.05 to .10%C) solution annealed at 2100 to 2200degF (1149 to 1204degC) has optimum properties above 1050degF (566degC). The effects of aluminium and titanium and the benefit of keeping these within the ASTM limits of .15 to .60% are also stressed. (author)
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Pugh, S.F. (ed.) (UKAEA Research Group, Harwell. Atomic Energy Research Establishment); British Nuclear Energy Society, London; p. 199-217; 1975; British Nuclear Energy Society; London; A status review of alloy 800; Reading, UK; 25 Sep 1974
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AbstractAbstract
[en] The evolution of the various grades of Alloy 800 is described in relation to both nuclear and non-nuclear applications, and comments are made on relevant service experience. The significance of the behavior characteristics of this alloy in relation to design and analysis methods is reviewed with particular emphasis on elevated temperature nuclear construction, where cyclic (creep-fatigue) as well as monotonic loads must be considered. The influence of fabrication factors, such as environment, on the properties of this material is also noted, and some comments on the potential applicability of probabilistic design methods are included. (Auth.)
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Betteridge, W.; Krefeld, R.; Krockel, H.; Lloyd, S.J.; Voorde, M. van de; Vivante, C. (eds.); p. 403-422; ISBN 0 444 85228 X; ; 1978; p. 403-422; North-Holland; Amsterdam, Netherlands; Petten international conference on alloy 800; Petten, Netherlands; 14 - 16 Mar 1978
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Mathern, G.; Decroix, J.; Lefevre, J.; Tricot, R.
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
AbstractAbstract
No abstract available
Original Title
Comportement au fluage et proprietes d'emploi de quelques aciers utilises dans l'industrie nucleaire
Primary Subject
Source
Lehoulier, J.; Mantega, M. (eds.); American Nuclear Society, Hinsdale, Ill.; Societe Europeenne d'Energie Nucleaire, Petit-Lancy (Switzerland); p. 48-49; 1975; Societe Francaise de l'Energie Nucleaire; Clamart, France; 1. European nuclear conference; Paris, France; 21 Apr 1975
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