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Filtering by: 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:

serve as a justifiably-scaled version of the Westinghouse AP1000 reactor as part of the light water
Dynamic simulation of a Westinghouse PWR four-loop plant during steam generator tube rupture event

Creator:

Sui, Yueh Chun

Abstract:

This study addresses the application of a full reactor system computer code to simulate the reactor primary and secondary loop thermal hydraulics, plant control and protection systems during the steam generator tube rupture (SGTR) events. The Trojan nuclear plant which is owned and operated by the Portland General Electric (PGE)...

Resource Type:

Masters Thesis

Full Text:

thermal-hydraulic behavior of a light-water reactor. It is designed to provide best the estimate