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

Bodney, I. T. ; Arimilli, R. V. ; Freels, J. D.

Technical Information Center Oak Ridge Tennessee

关键词: Hydraulics;    Fuel plates;    Research reactors;    Computerized simulation;    Defects;   

RP-ID  :  DE141147718

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

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.