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Filtering by: Creator French, Rod A. Committee Member Woods, Brian Subject Nuclear reactors -- Fluid dynamics

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:

surround each heater rod in a hexagonal configuration for a total of 114 coolant channels in the GRTS
Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

Creator:

Wuth, Bradyn J.

Abstract:

Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to model the Korean Atomic Energy Research Institute's SMART reactor, the Žukauskas...

Resource Type:

Masters Thesis

Full Text:

circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to