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AbstractAbstract
[en] Failure of systems is undesirable, but also inevitable. The consequences of failure can be reduced if the failure mode can be anticipated and repair procedures planned in advance. The fault tree analysis is one method of identifying the most probable failure modes and determining system failure rates. From these rates, repair frequency can be estimated. (author)
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Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs; p. 18-28; Feb 1976
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AbstractAbstract
[en] The calculating rules and recommendations of this standard act as guidelines for a quantitative probability analysis of failure sequences based on event trees in accodance with DIN-25419 (Pt.1)
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Source
Sep 1980; 9 p; Translated frm DIN-25419(Pt.2).
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Report
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Standard; Other
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AbstractAbstract
[en] Failure mode and effects analysis is a method to investigate the possible types of component failures and their effects on the system. The analysis is an inductive procedure. The analysis postulates failure of single components. The types of component failure are unlimited. It is a simple procedure without great mathematical efforts. Standard forms are used for systematic working, clearness, and documentation. Recommendations are given concerning the methods of failure mode and effects analysis and the design of the standard form. (orig./HP)
[de]
Die Ausfalleffektanalyse ist ein Verfahren zur Untersuchung der Ausfallarten von Komponenten eines Systems und deren Auswirkungen (Effekte) auf das System. Die Vorgehensweise der Analyse ist damit induktiv. In der Ausfalleffektanalyse werden Ausfaelle einzelner Komponenten unterstellt. Die in der Analyse erfassten Ausfallarten der Komponenten des Systems unterliegen keiner Einschraenkung. Es handelt sich um ein einfaches Verfahren ohne mathematischen Aufwand. Zur Systematisierung, zur besseren Uebersichtlichkeit und Dokumentierung wird die Analyse mit Formblaettern durchgefuehrt. Es werden Empfehlungen zur Methode der Ausfalleffektanalyse und zur Gestaltung des Formblattes gegeben. (orig./HP)Original Title
Ausfalleffektanalyse
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Source
Aug 1978; 7 p; Beuth; Berlin, Germany, F.R; DIN--25448
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Book
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Standard
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Cate, C.L.; Wagner, D.P.; Fussell, J.B.
Tennessee Univ., Knoxville (USA)1977
Tennessee Univ., Knoxville (USA)1977
AbstractAbstract
[en] Common cause failure analysis, also called common mode failure analysis, is an integral part of a complete system reliability analysis. Existing methods of computer aided common cause failure analysis are extended by allowing analysis of the complex systems often encountered in practice. The methods aid in identifying potential common cause failures and also address quantitative common cause failure analysis
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Source
1977; 22 p; 8. annual conference on modeling and simulation; Pittsburgh, Pennsylvania, United States of America (USA); 21 - 22 Apr 1977; Available from NTIS., PC A02/MF A01
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Report
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Conference
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AbstractAbstract
[en] Common mode failures (CMFs) have been a serious concern in the nuclear power plant. Thereis a broad category of the failure mechanisms that can cause common mode failures. This paper is a theoretical investigation of the CMFs on the unavailability of the redundent system. It is assumed that the total CMFs consist of the potential CMFs and the dependent human error CMFs. As the human error dependency is higher, the total CMFs are more effected by the dependent human error. If the human error dependence is lower, the system unavailability strongly depends on the potential CMFs, rather than the mechanical failure or the dependent human error. And it is shown that the total CMFs are dominant factor to the unavailability of the redundent system. (Author)
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Journal Article
Journal
Journal of the Korean Nuclear Society; ISSN 0372-7327;
; v. 15(4); p. 229-235

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Rodeman, R.; Priddy, T.G.
Sandia National Labs., Albuquerque, NM (USA)1985
Sandia National Labs., Albuquerque, NM (USA)1985
AbstractAbstract
[en] A centrifuge test at a constant acceleration level that bounds from above the closure that would be experienced by a normally open switch subjected to a stationary random excitation of fixed duration is derived. The bound is probabilistic in that the induced displacement will be exceeded with a certain selectable probability. The bound was formulated in terms of the system modal properties. Because the spatial distribution of the excitation is smooth and the frequency content is wide band the response is dominated by the first few lowest modes of the structure. It is further shown that the bound is relatively insensitive to the selected desired reliability. Experiments which verify the validity of the bound have been performed
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1985; 18 p; 3. international modal analysis conference; Orlando, FL (USA); 28-31 Jan 1985; CONF-850118--3-DRAFT; Available from NTIS, PC A02/MF A01; 1 as DE85002003
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AbstractAbstract
No abstract available
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American Nuclear Society 1975 winter meeting; San Francisco, CA, USA; 16 Nov 1975; Published in Summary Form Only.
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Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; v. 22 p. 476-477
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Antonov, A.V.; Luneva, A.E.; Sadovnikova, A.V.; Chepurko, V.A.
Scientific session of NRNU MEPHI-2013. Abstracts. In three volumes. Volume 1. Innovative nuclear technologies. High technologies in medicine2013
Scientific session of NRNU MEPHI-2013. Abstracts. In three volumes. Volume 1. Innovative nuclear technologies. High technologies in medicine2013
AbstractAbstract
No abstract available
Original Title
O raschete pokazatelej nadezhnosti v usloviyakh neodnorodnykh potokov NFF-modeli
Primary Subject
Source
Ministerstvo Obrazovaniya i Nauki Rossijskoj Federatsii, Moscow (Russian Federation); Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii Rosatom, Moscow (Russian Federation); Natsional'nyj Issledovatel'skij Yadernyj Univ. MIFI, Moscow (Russian Federation); 300 p; ISBN 978-5-7262-1786-4;
; 2013; p. 241; Scientific session of NRNU MEPHI-2013; Nauchnaya sessiya NIYaU MIFI-2013; Moscow (Russian Federation); 2013

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AbstractAbstract
[en] Parametric models for common cause failure (CCF) analysis (e.g., multiple Greek letter, reference 1, and alpha factor model, reference 2), require statistical information about the number of failures and component or system exposure; e.g., number of demands. In general, development of these statistics from raw data (i.e., failure event reports and system testing procedures) involves considerable judgment. In the case of common cause failures, the problem is amplified, mainly because of the rarity of the CCF events and the fact that, for a proper analysis of those events, more detailed information needs to be extracted from the failure reports. Proper treatment of uncertainties in the estimation of CCF frequencies therefore require a methodology that can accurately represent uncertain data. This paper presents such a methodology and discusses the appropriateness of the approximate methods that have been suggested and used. (orig./HSCH)
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Source
European Nuclear Society, Petit-Lancy (Switzerland); Schweizerische Gesellschaft der Kernfachleute (SGK), Bern (Switzerland); American Nuclear Society, La Grange Park, IL (USA); Risk and safety; 424 p; ISBN 3-88585-417-1;
; 1987; p. 67-73; Verl. TUEV Rheinland; Koeln (Germany, F.R.); International topical conference on probabilistic safety assessment and risk management (PSA '87); Zurich (Switzerland); 31 Aug - 4 Sep 1987

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Book
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Link, T.M.; Motta, A.T.; Koss, D.A.
Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging1997
Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging1997
AbstractAbstract
[en] During reactor exposure, Zircaloy cladding undergoes various microstructural changes including irradiation damage, oxidation, and hydrogen pick-up. There is a concern that the combination of these changes in high burnup cladding will cause failure during a reactivity-initiated accident (RIA) at an energy deposition level significantly lower than that of fresh cladding. In RIA conditions, the cladding must withstand loading at high strain rates and under deformation paths close to transverse plane-strain extension. Thus to assess cladding failure it is necessary to examine the failure mechanism of unirradiated Zircaloy cladding under RIA-like loading conditions. The authors present here a theoretical analysis of a possible failure mode of Zircaloy cladding due to localized necking. The results of the analysis suggest that high-burnup cladding is susceptible to pronounced losses of ductility under a combination of plane strain loading deformation and the presence of thickness imperfections. Such imperfections may be caused by hydride embrittlement of the cladding or non-uniform oxidation such that an axial thickness change is created
Primary Subject
Source
Monteleone, S. (comp.) (Brookhaven National Lab., Upton, NY (United States)); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States); 372 p; Jan 1997; p. 141-149; 24. water reactor safety information meeting; Bethesda, MD (United States); 21-23 Oct 1996; Also available from OSTI as TI96014720; NTIS; GPO
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