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Filtering by: Subject Weight loss -- Risk assessment Subject Nuclear power plants -- Thermodynamics -- Mathematical models

1. 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:: ) facility experiencing a Loss-of-Feedwater Accident (LOFA). The statistical advantages of the Bayesian