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Filtering by: Subject Nuclear power plants -- Piping -- Mathematical models Rights Statement In Copyright Subject Light water reactors -- Safety measures -- Mathematical models

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

Creator:

Hallee, Brian Todd

Abstract:

The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling,...

Resource Type:

Masters Thesis

Full Text:

extrapolating results to full-scale nuclear power plants. • Develop or utilize a pre-existing sampling method

ScholarsArchive@OSU

Feed-and-bleed transient analysis of OSU APEX facility using the modern Code Scaling, Applicability, and Uncertainty method

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