Excellence in Research and Innovation for Humanity

Assist. Prof. Dr. Imane Khalil

University

University of San Diego

Department

Mechanical Engineering Department

Research Fields

Heat Transfer, Computational Fluid Dynamics, Nuclear Engineering

Publications

1

Publications

1
10008633
Two-Dimensional Modeling of Spent Nuclear Fuel Using FLUENT
Abstract:
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zircalloy is the heat source for a thermodynamic cycle of energy conversion from heat to electricity. After fuel is used in a nuclear reactor, the assemblies are stored underwater in a spent nuclear fuel pool at the nuclear power plant while heat generation and radioactive decay rates decrease before it is placed in packages for dry storage or transportation. A computational model of a Boiling Water Reactor spent fuel assembly is modeled using FLUENT, the computational fluid dynamics package. Heat transfer simulations were performed on the two-dimensional 9x9 spent fuel assembly to predict the maximum cladding temperature for different input to the FLUENT model. Uncertainty quantification is used to predict the heat transfer and the maximum temperature profile inside the assembly.
Keywords:
Spent nuclear fuel, conduction, heat transfer, uncertainty quantification.

Abstracts

2
86958
Two-Dimensional Modeling of Spent Nuclear Fuel Using FLUENT
Abstract:
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zircalloy is the heat source for a thermodynamic cycle of energy conversion from heat to electricity. After fuel is used in a nuclear reactor, the assemblies are stored underwater in a spent nuclear fuel pool at the nuclear power plant while heat generation and radioactive decay rates decrease before it is placed in packages for dry storage or transportation. A computational model of a Boiling Water Reactor spent fuel assembly is modeled using FLUENT, the computational fluid dynamics package. Heat transfer simulations were performed on the two-dimensional 9x9 spent fuel assembly to predict the maximum cladding temperature for different input to the FLUENT model. Uncertainty quantification is used to predict the heat transfer and the maximum temperature profile inside the assembly.
Digital Article Identifier (DAI):
1
69382
Two-Dimensional Modeling of Spent Nuclear Fuel Using FLUENT
Abstract:
In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zircalloy is the heat source for a thermodynamic cycle of energy conversion from heat to electricity. After fuel is used in a nuclear reactor, the assemblies are stored underwater in a spent nuclear fuel pool at the nuclear power plant while heat generation and radioactive decay rates decrease before it is placed in packages for dry storage or transportation. A two-dimensional computational model using FLUENT to predict the heat transfer and the maximum temperature inside a spent fuel assembly is presented in this paper along with preliminary studies for a mathematical method that combines computational fluid dynamics with MATLAB data analysis.
Digital Article Identifier (DAI):