A new uncertainty methodology for not only nuclear engineering but also other disciplines is developed. This uncertainty methodology is analyzed by OECD/US-NRC Full Size Fine Mesh Bundle Tests (BFBT). Void distribution and critical power data for Boiling Water Reactor (BWR)bundles are utilized for the sensitivity and uncertainty analyses. Cumulative Distribution Functions for commonly used in two phase flow thermal hydraulic problems are developed and used as the inputs for the methodology. In addition Spanning Algorithm selects the limiting experimental cases to bound the experimental database. Finally, uncertainty methodology's feedback mechanism and flexibility provides a powerful tool for analyzers.
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A new uncertainty methodology for not only nuclear engineering but also other disciplines is developed. This uncertainty methodology is analyzed by OECD/US-NRC Full Size Fine Mesh Bundle Tests (BFBT). Void distribution and critical power data for Boiling Water Reactor (BWR)bundles are utilized for the sensitivity and uncertainty analyses. Cumulative Distribution Functions for commonly used in two phase flow thermal hydraulic problems are developed and used as the inputs for the methodology. In addition Spanning Algorithm selects the limiting experimental cases to bound the experimental database. Finally, uncertainty methodology's feedback mechanism and flexibility provides a powerful tool for analyzers.
Dr. Aydogan is an internationally recognized expert on nuclear safety, thermal hydraulics, two phase flow, uncertainty and small modular reactor design. He took his Bsc and Msc degrees from Hacettepe University and PhD degree from The Pennsylvania State University. He has more than 12 refereed articles, 1 patent and several archival reports.
Les informations fournies dans la section « A propos du livre » peuvent faire référence à une autre édition de ce titre.
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Taschenbuch. Etat : Neu. This item is printed on demand - it takes 3-4 days longer - Neuware -A new uncertainty methodology for not only nuclear engineering but also other disciplines is developed. This uncertainty methodology is analyzed by OECD/US-NRC Full Size Fine Mesh Bundle Tests (BFBT). Void distribution and critical power data for Boiling Water Reactor (BWR)bundles are utilized for the sensitivity and uncertainty analyses. Cumulative Distribution Functions for commonly used in two phase flow thermal hydraulic problems are developed and used as the inputs for the methodology. In addition Spanning Algorithm selects the limiting experimental cases to bound the experimental database. Finally, uncertainty methodology's feedback mechanism and flexibility provides a powerful tool for analyzers. 372 pp. Englisch. N° de réf. du vendeur 9783846535943
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Etat : New. Dieser Artikel ist ein Print on Demand Artikel und wird nach Ihrer Bestellung fuer Sie gedruckt. Autor/Autorin: Aydogan FatihDr. Aydogan is an internationally recognized expert on nuclear safety, thermal hydraulics, two phase flow, uncertainty and small modular reactor design. He took his Bsc and Msc degrees from Hacettepe University and PhD d. N° de réf. du vendeur 5497417
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Taschenbuch. Etat : Neu. Development of an Uncertainty Methodology for Nuclear Applications | Analyzed for COBRA-TF Void Distribution and Critical Power Predictions | Fatih Aydogan | Taschenbuch | 372 S. | Englisch | 2011 | LAP LAMBERT Academic Publishing | EAN 9783846535943 | Verantwortliche Person für die EU: BoD - Books on Demand, In de Tarpen 42, 22848 Norderstedt, info[at]bod[dot]de | Anbieter: preigu. N° de réf. du vendeur 106763185
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Taschenbuch. Etat : Neu. This item is printed on demand - Print on Demand Titel. Neuware -A new uncertainty methodology for not only nuclear engineering but also other disciplines is developed. This uncertainty methodology is analyzed by OECD/US-NRC Full Size Fine Mesh Bundle Tests (BFBT). Void distribution and critical power data for Boiling Water Reactor (BWR)bundles are utilized for the sensitivity and uncertainty analyses. Cumulative Distribution Functions for commonly used in two phase flow thermal hydraulic problems are developed and used as the inputs for the methodology. In addition Spanning Algorithm selects the limiting experimental cases to bound the experimental database. Finally, uncertainty methodology's feedback mechanism and flexibility provides a powerful tool for analyzers.Books on Demand GmbH, Überseering 33, 22297 Hamburg 372 pp. Englisch. N° de réf. du vendeur 9783846535943
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Taschenbuch. Etat : Neu. nach der Bestellung gedruckt Neuware - Printed after ordering - A new uncertainty methodology for not only nuclear engineering but also other disciplines is developed. This uncertainty methodology is analyzed by OECD/US-NRC Full Size Fine Mesh Bundle Tests (BFBT). Void distribution and critical power data for Boiling Water Reactor (BWR)bundles are utilized for the sensitivity and uncertainty analyses. Cumulative Distribution Functions for commonly used in two phase flow thermal hydraulic problems are developed and used as the inputs for the methodology. In addition Spanning Algorithm selects the limiting experimental cases to bound the experimental database. Finally, uncertainty methodology's feedback mechanism and flexibility provides a powerful tool for analyzers. N° de réf. du vendeur 9783846535943
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