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Simulating High Flux Isotope Reactor Core Thermal-Hydraulics via Interdimensional Model Coupling.

DE141147719

Publication Date	2014
Personal Author	Travis, A. R.; Ekici, K.; Freels, J. D.
Page Count	134
Abstract	A coupled interdimensional model is presented for the simulation of the thermal-hydraulic characteristics of the High Flux Isotope Reactor core at Oak Ridge National Laboratory. The model consists of two domainsa solid involute fuel plate and the surrounding liquid coolant channel. The fuel plate is modeled explicitly in three-dimensions. The coolant channel is approximated as a twodimensional slice oriented perpendicular to the fuel plates surface. The two dimensionally-inconsistent domains are linked to one another via interdimensional model coupling mechanisms. The coupled model is presented as a simplified alternative to a fully explicit, fully three-dimensional model. Involute geometries were constructed in SolidWorks. Derivations of the involute construction equations are presented. Geometries were then imported into COMSOL Multiphysics for simulation and modeling. Both models are described in detail so as to highlight their respective attributesin the 3D model, the pursuit of an accurate, reliable, and complete solution; in the coupled model, the intent to simplify the modeling domain as much as possible without affecting significant alterations to the solution. The coupled model was created with the goal of permitting larger portions of the reactor core to be modeled at once without a significant sacrifice to solution integrity. As such, particular care is given to validating incorporated model simplifications. To the greatest extent possible, the decrease in solution time as well as computational cost are quantified versus the effects such gains have on the solution quality. A variant of the coupled model which sufficiently balances these three solution characteristics is presented alongside the more comprehensive 3D model for comparison and validation.
Keywords	HFIR reactor Hydraulics Fuel plates Computerized simulation Coolants Coupling Dimensions Geometry Oak Ridge National Laboratory Reactor cores Thermal analysis
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants 77I - Reactor Fuels & Fuel Processing
Corporate Authors	Oak Ridge National Lab., TN.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201502

Simulating High Flux Isotope Reactor Core Thermal-Hydraulics via Interdimensional Model Coupling.

Simulating High Flux Isotope Reactor Core Thermal-Hydraulics via Interdimensional Model Coupling.
DE141147719

Publication Date	2014
Personal Author	Travis, A. R.; Ekici, K.; Freels, J. D.
Page Count	134
Abstract	A coupled interdimensional model is presented for the simulation of the thermal-hydraulic characteristics of the High Flux Isotope Reactor core at Oak Ridge National Laboratory. The model consists of two domainsa solid involute fuel plate and the surrounding liquid coolant channel. The fuel plate is modeled explicitly in three-dimensions. The coolant channel is approximated as a twodimensional slice oriented perpendicular to the fuel plates surface. The two dimensionally-inconsistent domains are linked to one another via interdimensional model coupling mechanisms. The coupled model is presented as a simplified alternative to a fully explicit, fully three-dimensional model. Involute geometries were constructed in SolidWorks. Derivations of the involute construction equations are presented. Geometries were then imported into COMSOL Multiphysics for simulation and modeling. Both models are described in detail so as to highlight their respective attributesin the 3D model, the pursuit of an accurate, reliable, and complete solution; in the coupled model, the intent to simplify the modeling domain as much as possible without affecting significant alterations to the solution. The coupled model was created with the goal of permitting larger portions of the reactor core to be modeled at once without a significant sacrifice to solution integrity. As such, particular care is given to validating incorporated model simplifications. To the greatest extent possible, the decrease in solution time as well as computational cost are quantified versus the effects such gains have on the solution quality. A variant of the coupled model which sufficiently balances these three solution characteristics is presented alongside the more comprehensive 3D model for comparison and validation.
Keywords	HFIR reactor Hydraulics Fuel plates Computerized simulation Coolants Coupling Dimensions Geometry Oak Ridge National Laboratory Reactor cores Thermal analysis
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants 77I - Reactor Fuels & Fuel Processing
Corporate Authors	Oak Ridge National Lab., TN.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201502