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Saglio, R.
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] The PISC trials were primarily conducted to assess the capability of the ultrasonic procedure prepared by the Pressure Vessel Research Committee and based on the ASME Code Section XI (1974) to detect, locate and size flaws or discontinuities in welds in heavy section steel. However, in addition to the results using this procedure to examine three test plates participating inspection teams were invited to present, the results of an inspection using alternative ultrasonic techniques. Because of the small numbers of teams giving results for a given class of procedures neither a defect detection probability nor a correct rejection/acceptance probability could be estimated. However suitable parameters related to detection and rejection were defined to give an indication of the trend in the performance of a group of alternative procedures as compared with the PISC procedure. The criterion used for rejection/acceptance of defects was taken from the ASME Code. Many of the teams giving results for alternative procedures would not use this criterion in practice. Its use in this analysis was a symbolic one to illustrate trends
Original Title
Program of Inspection for Steel Components
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Jun 1983; 4 p; Symposium NDE reliability through round robin testing; Portland, OR (USA); 19-24 Jun 1983
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Saglio, R.
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] For the in-service inspection of nuclear generating stations, the French Atomic Commission has built up a program first to increase the defect detection probability, secondly to increase the reliability and recently to improve the characterization of defects. Focused Ultrasound and multiple frequency eddy current techniques, developped by French Atomic Energy Commission are well known. In this paper we will present the latest developments made in relation with defect characterization
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Dec 1983; 6 p; 6. International conference on non-destructive evaluation in the nuclear industry; Zurich (Switzerland); 27 Nov - 2 Dec 1983
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Report
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AbstractAbstract
No abstract available
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p. 701-713; 1973; American Society of Mechanical Engineers; New York; 2. international congress for pressure vessel and piping technology; San Antonio, Texas, USA; 1 Oct 1973
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Book
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AbstractAbstract
[en] INTERCONTROLE is predominently involved in inservice inspection of PWR pressure vessels and steam generators. This paper summarizes its experience for eight years of field applications
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Anon; p. 109-112; 1985; p. 109-112; American Society of Mechanical Engineers; New York, NY (USA); 7. international conference on nondestructive evaluation in the nuclear industry; Grenoble (France); 29 Jan - 1 Feb 1985
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Book
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Conference
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Saglio, R.; Verger, B.
4th international conference on nondestructive evaluation in nuclear industry1981
4th international conference on nondestructive evaluation in nuclear industry1981
AbstractAbstract
No abstract available
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Source
Deutsche Gesellschaft fuer Zerstoerungsfreie Pruefung e.V., Berlin (Germany, F.R.); 79 p; 1981; vp; 4. international conference on nondestructive evaluation in nuclear industry; Lindau, Germany, F.R; 25 - 27 May 1981; Available from Fachinformationszentrum Energie, Physik, Mathematik, Karlsruhe, Germany, F.R; Published in summary form only.
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Miscellaneous
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Asty, M.; Saglio, R.
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] The design of Superphenix 1 reactor vessels allows their in-service inspection. A self-propelling engine, the MIR, has been concieved for this need: it can do a visual and ultrasonic inspection. The MIR can move in the whole vessels interspace. The operating conditions are specified and the principle characteristics of the MIR engine are presented
[fr]
La conception des cuves du reacteur SUPERPHENIX 1 permet leur inspection en service. Un engin auto-moteur, le MIR, a ete specialement developpe pour ce besoin: il est capable d'effectuer une inspection visuelle et ultrasonore. Schematiquement, la structure de l'engin MIR est un tetraedre dont chaque sommet est equipe d'une roue de traction et direction, deux roues s'appuyant sur chaque cuve. Grace a un controle commande assiste par ordinateur, l'engin MIR peut se deplacer dans tout l'espace intercuve. Apres avoir precise les conditions operatoires, nous presentons brievement les caracteristiques principales de l'engin MIROriginal Title
Inspection en service de Superphenix 1 par l'espace intercuve
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Source
Mar 1983; 11 p; Meeting of the Society of Electrical, Electronic and Radio Engineers; Creys-Malville (France); 17 Mar 1983
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Report
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AbstractAbstract
No abstract available
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Journal Article
Journal
Nuclear Engineering International; v. 19(222); p. 934-937
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Verger, B.; Saglio, R.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1981
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1981
AbstractAbstract
[en] The use of focused search units in nuclear reactor vessel examinations has significantly increased the capability of flaw indication detection and characterization. These search units especially allow a more accurate sizing of indications and a more efficient follow up of their history. In this aspect, they are a unique tool in the area of safety and reliability of installations. It was this type of search unit which was adopted to perform the examinations required within the scope of inservice inspections of all P.W.R. reactors of the French nuclear program. This paper summarizes the results gathered through the 4l examinations performed over the last five years. A typical application of focused search units in automated inspections performed in accordance with ASME code requirements on P.W.R. nuclear reactor vessels is then described
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May 1981; 8 p; 4. International conference on non destructive evaluation in the nuclear industry; Lindau, Germany, F.R; 25 - 27 May 1981
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Report
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Pigeon, M.; Saglio, R.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1976
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Technologie1976
AbstractAbstract
[en] The described multifrequency device has been designed and developed for a complete testing of tubes. It is necessary to eliminate the signals given by plates, expanded parts, background noises and magnetic signals which can mask some possible defects
[fr]
L'appareil multifrequence decrit a ete concu et realise pour effectuer un controle complet des tubes. Il est necessaire d'eliminer les signaux donnes par les plaques, dudgeonnages, bruits de fond et signaux d'origine magnetique qui risquent de masquer d'eventuels defautsOriginal Title
Inspection en service des tubes de generateurs de vapeur avec un appareil a courants de Foucault multifrequence
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Source
1976; 10 p; 8. World conference on nondestructive testing; Cannes, France; 6 Sep 1976
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Report
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Saglio, R.; Prot, A.C.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Surete Nucleaire1976
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Surete Nucleaire1976
AbstractAbstract
[en] Present methods of ultrasonic non destructive testing are not convenient for nuclear safety purposes: in service inspection for instance requires the use of valuable information, that is, having sufficient ability to describe the actual state of the structure under test. Present specifications are partly, if not entirely, arbitrary. For instance the evaluation of the defect size is made from standard flaw considerations, which are far from being entirely objective, even when using sophisticated automatic scanning systems. New draft specifications will have to be written, making use of a new concept: the 'effective ultrasonic beam' related to that part of the beam which may be considered as cylindrical, and in which the sensitivity may be considered as constant within given and known margins. This concept is particularly useful when applied to 'shaped beams' like focussed beams (the focussing effect may be obtained by means of lenses, mirrors, etc..., or by electronic means: phased array of transducers for instance)
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1976; 17 p; Specialist meeting on the ultrasonic inspection of reactor components; Risley, UK; 27 - 29 Sep 1976
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