Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors

Author

Isaac Thomas Bodey, University of Tennessee - KnoxvilleFollow

Date of Award

5-2014

Degree Type

Dissertation

Degree Name

Doctor of Philosophy

Major

Mechanical Engineering

Major Professor

Rao V. Arimilli

Committee Members

Majid Keyhani, Kivanc Ekici, Arthur Ruggles, James D. Freels, David H. Cook

Abstract

Turbulent flow coupled with heat transfer is investigated for a High Flux Isotope Reactor (HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics and the transfer of heat from a thermal nuclear fuel plate using the Multi-physics code COMSOL. Simulation outcomes are compared with experimental data from the Advanced Neutron Source Reactor Thermal Hydraulic Test Loop. The computational results for the High Flux Isotope Reactor core system provide a more physically accurate simulation of this system by modeling the turbulent flow field in conjunction with the diffusion of thermal energy within the solid and fluid phases of the model domain. Recommendations are made regarding Nusselt number correlations and material properties for future thermal hydraulic modeling efforts.

Recommended Citation

Bodey, Isaac Thomas, "Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors. " PhD diss., University of Tennessee, 2014.
https://trace.tennessee.edu/utk_graddiss/2680