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Chauvet, D.
Compagnie Generale des Matieres Nucleaires (COGEMA), 26 - Pierrelatte (France)1990
Compagnie Generale des Matieres Nucleaires (COGEMA), 26 - Pierrelatte (France)1990
AbstractAbstract
[en] A computer aided scheduling applied to the maintenance of a uranium enrichment plant is presented. The plant exploits gaseous diffusion and electric power distribution plants, for which the operating conditions must be satisfied. The management and the execution of the maintenance actions are computer aided. Concerning the techniques, the cost, the safety and the scheduling actions were optimized
[fr]
Le rapport presente le programme d'informatisation de l'ordonnancement de la maintenance applique au service d'enrichissement de l'uranium. Ce service exploite les usines de diffusion gazeuse et les installations de distribution electrique, qui doivent etre operationnelles. Les procedures informatiques mises en oeuvre assurent la gestion et l'execution des actions de maintenance. L'informatisation a permis d'optimiser les actions d'ordonnancement, sous le point technique, economique et de la securiteOriginal Title
Ordonnancement de la maintenance des usines de diffusion gazeuse et de la distribution electrique
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Source
1990; 15 p; Technology Outlook Meeting; Pierrelatte (France); 18-19 Apr 1990
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Report
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Conference
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INIS IssueINIS Issue
Post, B.E.; Sikorski, P.A.; Fankell, R.; Johnson, O.; Ferryman, D.S.; Miller, R.L.; Gearhart, E.C.; Rafferty, M.J.
Goodyear Atomic Corp., Piketon, OH (USA)1981
Goodyear Atomic Corp., Piketon, OH (USA)1981
AbstractAbstract
[en] A reliability study of the maintenance facilities at the Portsmouth Gaseous Diffusion Plant has been completed. The reliability study team analyzed test data and made visual inspections of each component contributing to the overall operation of the facilities. The impacts of facilities and equipment failures were given consideration with regard to personnel safety, protection of government property, health physics, and environmental control. This study revealed that the maintenance facilities are generally in good condition. After evaluating the physical condition and technology status of the major components, the study team made several basic recommendations. Implementation of the recommendations proposed in this report will help assure reliable maintenance of the plant through the year 2000
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Source
Aug 1981; 45 p; Available from NTIS., PC A03/MF A01 as DE82010517
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Report
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AbstractAbstract
[en] The nuclear material safeguards system at the Portsmouth Gaseous Diffusion Plant is currently being improved. A new material control system will provide computerized monitoring and accountability, and a new physical protection system will provide upgraded perimeter and portal entry monitoring. The control system incorporates remote computer terminals at all processing, transfer and storage areas throughout the plant. Terminal equipment is interfaced to a computer through teletype equipment. A typical terminal transaction would require verification that the particular activity (material movement or process operation) is authorized, identifying the container involved, weighing the container, and then verifying the enrichment with non-destructive assay instrumentation. The system, when fully operational, will provide near real-time accountability for each eight-hour work shift for all items in process. (author)
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; v. 2 p. 491-504; ISBN 92-0-070179-5;
; 1979; v. 2 p. 491-504; IAEA; Vienna; Symposium on nuclear material safeguards; Vienna, Austria; 2 - 6 Oct 1978; IAEA-SM--231/76

Record Type
Book
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Conference
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Murrell, J.S.
Goodyear Atomic Corp., Piketon, OH (USA)1978
Goodyear Atomic Corp., Piketon, OH (USA)1978
AbstractAbstract
[en] The nuclear material safeguards system at the Portsmouth Gaseous Diffusion Plant is currently being improved. A new material control system will provide computerized monitoring and accountability, and a new physical protection system will provide upgraded perimeter and portal entry monitoring. The control system incorporates remote computer terminals at all processing, transfer, and storage areas throughout the plant. Terminal equipment is interfaced to a computer through teletype equipment. A typical terminal transaction would require verification that the particular activity (material movement or process operation) is authorized, identifying the container involved, weighing the container, and then verifying the enrichment with non-destructive assay instrumentation. The system, when fully operational, will provide near real-time accountability for each eight-hour work shift for all items in process
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Secondary Subject
Source
17 Aug 1978; 20 p; IAEA symposium on nuclear material safeguards; Vienna, Austria; 2 - 6 Oct 1978; IAEA-SM--231/76; CONF-781007--18; Available from NTIS., PC A02/MF A01
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Report
Literature Type
Conference
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In the framework of a partnership between Cogema and I.R.S.N. a study of food consumption of populations living near the site of Pierrelatte-Tricastin has been realised in the commune of Bollene. This inquiry took place in four steps in order to describe correctly the seasons evolutions of the food consumption and auto consumption of families. The aim of this present report is to present the comparison realised of data issued from the inquiry of Pierrelatte to these ones from other recent food inquiries. (N.C.)
Original Title
Enquete alimentaire de Pierrelatte: etude des consommations alimentaires des populations a proximite du site Pierrelatte-Tricastin: rations journalieres et autoconsommation
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2005; 29 p
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Miscellaneous
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AbstractAbstract
[en] With the development of micro-modules and micro-processors, those in instrumentation are challenged to employ the principles of the Incremental Power Demand Computer (IPDC) to better utilize electric power in many applications. The IPDC was developed at the Portsmouth Gaseous Diffusion Plant in 1959 for measuring 2,000,000 Kw demand and to better utilize electric power in the production of enriched uranium. Two generations of the instruments have been used during the past 17 years to aid in the measurement and control of power usage and will be similarly used in the future when the plant load will be increased to 2,260,000 Kw. The second generation IPDC measures in and out flow on 26 meters to accurately account for transfer of power through the plant substations from one power system to the other, as well as for the power utilized by the plant. This system also prints out the hourly load on each of the meters and is utilized for calculating the multi-million dollar electric power bill each month. The second-generation IPDC uses solid-state components mounted on printed circuit boards for reliability. Pulses from the special pickups in the billing watt-hour meters are used by the IPDC to determine and display accurate plant power usage every six minutes. Application of these IPDC principles to many existing watt-hour meters would result in the better utilization of electric power. 4 refs
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Record Type
Journal Article
Journal
Advances in Instrumentation; v. 31 p. 1-11
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Krichinsky, Alan M.; Bell, Lisa S.; Conchewski, Curtis A.; Peters, Benjamin R.; Pickett, Chris A.; Richardson, Dave; Rowe, Nathan C.; Younkin, James R.
Oak Ridge National Laboratory (United States). Funding organisation: NNSA USDOE - National Nuclear Security Administration (United States)2010
Oak Ridge National Laboratory (United States). Funding organisation: NNSA USDOE - National Nuclear Security Administration (United States)2010
AbstractAbstract
[en] Continuous load cell monitoring (CLCM) has been implemented and tested for use as a safeguards tool during a 2009 field trial in an operating UF6 transfer facility. The transfer facility is part of the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio, operated by the United States Enrichment Corporation. During the field trial, two process scales for UF6 cylinders were continuously monitored for a 6-month period as cylinders were being filled. The collected CLCM data were used in testing an event processor serving as a filter for highlighting measurements representing significant operational activities that are important in verifying declared operations. The collection of CLCM data, coupled with rules-based event processing, can provide inspectors with knowledge of a facility's feed and withdrawal activities occurring between site visits. Such process knowledge promises to enhance the effectiveness of safeguards by enabling inspectors to quantitatively compare declared activities directly with process measurements. Selected results of the field trial and event processing will be presented in the context of their value to an independent inspector and a facility operator.
Primary Subject
Source
1 Jan 2010; 10 p; 51. Annual meeting of the Institute of Nuclear Materials Management (INMM); Baltimore, MD (United States); 11-15 Jul 2010; NN4003010; MDGA517; AC05-00OR22725; Available from http://info.ornl.gov/sites/publications/files/Pub24671.pdf; PURL: https://www.osti.gov/servlets/purl/1033974/
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Miscellaneous
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Conference
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AbstractAbstract
No abstract available
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ANS winter meeting; San Francisco, CA (USA); 29 Nov - 4 Dec 1981; CONF-811103--; Published in summary form only.
Record Type
Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 39 p. 522-524

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Feuerbacher, J.L.
Goodyear Atomic Corp., Piketon, OH (USA)1981
Goodyear Atomic Corp., Piketon, OH (USA)1981
AbstractAbstract
[en] Safe geometrical, mass, and concentration limits are presented, together with the criticality control methods currently in use at the Portsmouth Gaseous Diffusion Plant. Basic information presented includes technical background, experimental data, and the best values inferred from experiments. Various tables and graphs are included. Design criteria include basic assumptions, fundamentals, concepts, applicable methods, and maintenance of safe geometry. Operating criteria include the operating philosophy at the Goodyear Atomic Corporation Gaseous Diffusion Plant and applied operating techniques. The appendices contain graphs, figures, a chart showing Goodyear organization for nuclear safety, a glossary, tables of critical values, methods for calculating solid angles, and the bases for safe handling of high-uranium-density compounds and uranium metal in various forms
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15 Mar 1981; 105 p; Available from NTIS., PC A06/MF A01 as DE82006068
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Report
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AbstractAbstract
[en] The Department of Energy has primary responsibility for the safety of operations at DOE-owned nuclear facilities. The guidelines for the analysis of credible accidents are outlined in DOE Order 5481.1. DOE has requested that existing plant facilities and operations be reviewed for potential safety problems not covered by standard industrial safety procedures. This review is being conducted by investigating individual facilities and documenting the results in Safety Study Reports which will be compiled to form the Existing Plant Final Safety Analysis Report which is scheduled for completion in September, 1984. This Safety Study documents the review of the Plant Nitrogen System facilities and operations and consists of Section 4.0, Facility and Process Description, and Section 5.0, Accident Analysis, of the Final Safety Analysis Report format. The existing nitrogen system consists of a Superior Air Products Company Type D Nitrogen Plant, nitrogen storage facilities, vaporization facilities and a distribution system. The system is designed to generate and distribute nitrogen gas used in the cascade for seal feed, buffer systems, and for servicing equipment when exceptionally low dew points are required. Gaseous nitrogen is also distributed to various process auxiliary buildings. The average usage is approximately 130,000 standard cubic feet per day
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Jul 1982; 55 p; Available from NTIS., PC A04/MF A01 as DE82020571
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