Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors
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
- Authors:
-
- ORNL
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1147718
- Report Number(s):
- ORNL/TM-2014/273
- DOE Contract Number:
- AC05-00OR22725
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- COMSOL LEU HFIR
Citation Formats
Bodey, Isaac. Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors. United States: N. p., 2014.
Web. doi:10.2172/1147718.
Bodey, Isaac. Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors. United States. https://doi.org/10.2172/1147718
Bodey, Isaac. 2014.
"Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors". United States. https://doi.org/10.2172/1147718. https://www.osti.gov/servlets/purl/1147718.
@article{osti_1147718,
title = {Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors},
author = {Bodey, Isaac},
abstractNote = {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},
doi = {10.2172/1147718},
url = {https://www.osti.gov/biblio/1147718},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu May 01 00:00:00 EDT 2014},
month = {Thu May 01 00:00:00 EDT 2014}
}