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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…mehr

Produktbeschreibung
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.
Autorenporträt
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.