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A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

Creator:

Jackson, R. Brian

Abstract:

Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was to study core channel flow reversal susceptibility in the Gas Reactor Test Section (GRTS) at low flow conditions. The second objective was the development of...

Resource Type:

Masters Thesis

Full Text:

Jackson for the degree of Master of Science in Nuclear Engineering presented on March 17, 2008
Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

Creator:

Marcum, Wade R.

Abstract:

Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both...

Resource Type:

Masters Thesis

Full Text:

Wade R. Marcum for the degree of Master of Science in Nuclear Engineering presented on January 23