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ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Langue: anglais
Edité par LAP LAMBERT Academic Publishing, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierTaschenbuch. 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.
Langue: anglais
Edité par LAP LAMBERT Academic Publishing, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierPaperback. Etat : Like New. LIKE NEW. SHIPS FROM MULTIPLE LOCATIONS. book.
Langue: anglais
Edité par LAP LAMBERT Academic Publishing Okt 2011, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierTaschenbuch. 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.
Langue: anglais
Edité par LAP LAMBERT Academic Publishing, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierEtat : 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.
Langue: anglais
Edité par Editorial Academica Espanola, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierEtat : New. Print on Demand pp. 372 2:B&W 6 x 9 in or 229 x 152 mm Perfect Bound on Creme w/Gloss Lam.
Langue: anglais
Edité par Editorial Academica Espanola, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
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Ajouter au panierEtat : New. PRINT ON DEMAND pp. 372.
Langue: anglais
Edité par LAP LAMBERT Academic Publishing Okt 2011, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
Vendeur : buchversandmimpf2000, Emtmannsberg, BAYE, Allemagne
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Ajouter au panierTaschenbuch. 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.VDM Verlag, Dudweiler Landstraße 99, 66123 Saarbrücken 372 pp. Englisch.
Langue: anglais
Edité par LAP LAMBERT Academic Publishing, 2011
ISBN 10 : 384653594X ISBN 13 : 9783846535943
Vendeur : AHA-BUCH GmbH, Einbeck, Allemagne
EUR 79
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Ajouter au panierTaschenbuch. 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.