# overview
Expertise in scientific computing (solution techniques, algorithms), predictive science (uncertainty quantification, inference), and data science (machine learning, model-order reduction) applied to complex radiation / multi-physics problems in nuclear engineering (nuclear reactors, national security, radiation treatment planning).

# keywords[]
Networking And Information Technology R&d (nitrd)

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4019 Resources Engineering And Extractive Metallurgy

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4012 Fluid Mechanics And Thermal Engineering

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4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

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Discontinuous Galerkin Finite Element Method

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4019 Resources Engineering And Extractive Metallurgy

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4019 Resources Engineering And Extractive Metallurgy

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4019 Resources Engineering And Extractive Metallurgy

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4012 Fluid Mechanics And Thermal Engineering

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4012 Fluid Mechanics And Thermal Engineering

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4007 Control Engineering, Mechatronics And Robotics

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4007 Control Engineering, Mechatronics And Robotics

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4007 Control Engineering, Mechatronics And Robotics

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4019 Resources Engineering And Extractive Metallurgy

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4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4007 Control Engineering, Mechatronics And Robotics

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4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# educationAndTraining[].organization.label
Grenoble Institute of Technology - (Grenoble, France)

# educationAndTraining[].organization.label
Grenoble Institute of Technology - (Grenoble, France)

# educationAndTraining[].organization.label
Texas A&M University - (College Station, Texas, United States)

# publications[].label
Deterministic High-Fidelity Neutronics Simulation of Pebble Bed Reactors with Pebble Tracking Transport

# publications[].label
Application of proper generalized decomposition to heterogeneous diffusion-reaction problems

# publications[].label
Recent Progress In The International Initiative On The Development Of An Open Source Platform For E&T And R&D In Nuclear Applications

# publications[].label
Multi-recycling of transuranic elements in a PWR assembly with reduced fuel rod diameter

# publications[].label
An Initiative For The Development And Application Of Open-Source Multi-Physics Simulation In Support Of R&D And E&T In Nuclear Science And Technology

# publications[].label
Sweep-Net: An Artificial Neural Network for radiation transport solves

# publications[].label
Uncertainty quantification of coupled problems in reactor analysis

# publications[].label
Three-dimensional h-adaptivity for the multigroup neutron diffusion equations

# publications[].label
TAMU Nuclear safety curriculum development for a 21stcentury workforce

# publications[].label
A DFEM formulation of the diffusion equation on arbitrary polyhedral grids

# publications[].label
An algorithm for multi-mesh and multi-irregularity from adaptive mesh refinement with FEM

# publications[].label
A non-negative, non-linear, Petrov-Galerkin method for bilinear discontinuous differencing of the S<inf>N</inf> equations

# publications[].label
On the Convergence of DGFEM Applied to the Discrete Ordinates Transport Equation for Structured and Unstructured Triangular Meshes

# publications[].label
Adjoint-Based Uncer- tainty Quantification for Radiation Transport Calculations with Un- certain Cross-Section Data

# publications[].label
Assessment of proliferation resistance requirements for fast-reactor fuel-cycle facilities

# publications[].label
Accuracy Analysis Of Near Wall Thermal- Hydraulics Modeling Of Molten Salt Reactors

# publications[].label
Non-intrusive model order reduction for parametric radiation transport simulations

# publications[].label
Goal-Oriented h-Adaptivity for the Multigroup SPN Equations

# publications[].label
S2SA preconditioning for the Sn equations with strictly nonnegative spatial discretization

# publications[].label
Verification of reduced-order model subspace dimensions and minimal ranks in simple configurations

# publications[].label
Reduced-Order Modeling of fluid flows in molten salt systems

# publications[].label
Analysis of physics-based preconditioning for single-phase subchannel equations

# publications[].label
Accelerating Radiation SN Transport Solves Using Artificial Neural Networks

# publications[].label
Discontinuous diffusion synthetic acceleration for Sn transport on 2D arbitrary polygonal meshes

# publications[].label
Nonlinear Eddy Viscosity Models for the Tur- bulence Phenomena in Molten Salt Reactors

# publications[].label
Goal-based h-adaptivity of the 1-D diamond difference discrete ordinate method

# publications[].label
Plutonium and minor actinides transmutation in standard PWRs fuel assemblies

# publications[].label
Viscous Regularization for the Non-equilibrium Seven-Equation Two-Phase Flow Model

# publications[].label
Behavior assessments for UO<inf>2</inf>-BEO enhanced conductivity fuel in a PWR

# publications[].label
Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

# publications[].label
Neutronic and nonproliferation characteristics of (PuO2-UO2) and (PuO2-ThO2) as fast reactor fuels

# publications[].label
Projection-based Parametric Model Order Reduction for Transport Simulation Based on Affine Decomposition of the Operators

# publications[].label
Discontinuous  Galerkin  methods  for  the radiative transport equation

# publications[].label
A high-order discontinuous Galerkin method for the SN transport equations on 2D unstructured triangular meshes

# publications[].label
Non-intrusive reduced-order modeling of radiation transport in the atmosphere

# publications[].label
RESIDUAL MONTE CARLO FOR THE ONE-DIMENSIONAL PARTICLE TRANSPORT EQUATION

# publications[].publisher
Society for Industrial & Applied Mathematics (SIAM)

# publications[].label
Diffusion Synthetic Acceleration for High-Order Discontinuous Finite Element SN Transport Schemes and Application to Locally Refined Unstructured Meshes

# publications[].label
Characterization of high order spatial discretizations and lumping techniques for discontinuous finite element SN transport

# publications[].label
Cross section inference based on PDE-constrained optimization

# publications[].label
High temperature super-critical CO<inf>2</inf>-cooled integrated multi-modular thermal reactor

# publications[].label
Model Order Reduction for Sn Radiation Transport

# publications[].label
Discontinuous finite element solution of the radiation diffusion equation on arbitrary polygonal meshes and locally adapted quadrilateral grids

# publications[].label
Improving the Performance of Transport Sweeps with Thermal Upscattering Acceleration at Massively  Parallel  Scale

# publications[].label
Introducing a high thermal conductivity UO<inf>2</inf>-BeO nuclear fuel concept

# publications[].label
Reduced-Order Modeling of Parameterized Transient Flows in Closed-Lloop Systems

# publications[].label
Direct  Numerical  Simulations  of  Turbulence  in Molten Salts Coolants

# publications[].label
High-order solution methods for grey discrete ordinates thermal radiative transfer

# publications[].label
Method of Manufactured Solutions for a 2-D neutronics/heat conduction test case with adaptive multimesh hp-FEM

# publications[].label
Xuthos: A discontinuous galerkin transport solver for NEWT based on unstructured triangular meshes

# publications[].label
Space-energy separated representations for multigroup neutron diffusion using proper generalized decompositions

# publications[].label
A Least-Squares Transport Equation Compatible with Voids

# publications[].label
Application of the reactor system code RELAP-7 to single-and two-phase flow water-hammer problems

# publications[].label
Lattice Boltzmann solidification modeling of forced convection internal flows applied to Gen-IV nuclear reactor coolants

# publications[].label
Editorial : progress in the science and technology of nuclear reactors using molten salts

# publications[].label
A ROBUST MULTIGRID PRECONDITIONER FOR SNDG APPROXIMATION OF MONOCHROMATIC, ISOTROPIC RADIATION TRANSPORT PROBLEMS

# publications[].publisher
Society for Industrial & Applied Mathematics (SIAM)

# publications[].label
Asymptotic PN-Equivalent SN+1 Equations

# publications[].label
Progress on coarse-mesh solidification modeling through an upscaling physics-based data-driven calibration

# publications[].label
Adaptive mesh refinement applied to the multi-dimensional, multi-group, SP<inf>N</inf> equations with marshak boundary condition treatment

# publications[].label
Goal-oriented h-type adaptive mesh refinement for the SN neutron transport equation solved with DGFEM

# publications[].label
Application of proper generalized decomposition to multigroup neutron diffusion eigenvalue calculations

# publications[].label
Parametric Model-Order Reduction for Radiation Transport Simulations Based on an Affine Decomposition of the Operators

# publications[].label
Reduced-Order Modeling of Parametrized Multi-Physics Computations for the Molten Salt Fast Reactor

# publications[].label
Quadratic serendipity discontinuous finite element discretization for SN transport on arbitrary polygonal grids

# publications[].label
Adaptive automated solution of the multi-group diffusion equations

# publications[].label
Analysis of a CRDM Nozzle Break LOCA Without Scram Using the U.S. NRC Coupled Code TRAC-M/PARCS

# publications[].label
Improved quasi-static method with step doubling time adaptation

# publications[].label
Data-Driven Reduced-Order Modeling of Convective Heat Transfer in Porous Media

# publications[].label
Multiphysics simulations for LWR analysis

# publications[].label
Analysis of advanced fuel assemblies for the LWRs

# publications[].label
Uncollided-Flux Treatment for Discrete-Ordinate Radiation Transport Solutions in the Rattlesnake Code System

# publications[].label
Entropy viscosity method applied to euler equations

# publications[].label
Goal-oriented mesh adaptivity for multi-dimension SP<inf>N</inf> equations

# publications[].label
A simple Hessian-based 3D mesh adaptation technique with applications to the multigroup diffusion equations

# publications[].label
Uncertainty Quantification of Plu- tonium Inventory Calculations through Xenon Gas Sampling of Underground Waste Tanks containing High-Level Radioactive Waste from Uranium Reprocessing

# publications[].label
Model Error Estimation for the Simplified PN Radiation Transport Equations

# publications[].label
ADVANCED MOX AND IMF FUEL ASSEMBLY DESIGNS FOR MULTI-RECYCLING TRANSURANICS

# publications[].label
Physics-Informed Neural Network with Fourier Features for Radiation Transport in Heterogeneous Media

# publications[].label
A non-negative moment-preserving spatial discretization scheme for the linearized Boltzmann transport equation in 1-D and 2-D Cartesian geometries

# publications[].label
Implementation of the improved quasi-static method in rattlesnake/moose for time-dependent radiation transport modelling

# publications[].label
Uncollided-Flux Treatment in Arbitrary Polyhedral Grids

# publications[].label
3-D block incomplete preconditioner for the primal and mixed-primal finite element solvers of CRONOS-2

# publications[].label
Asymptotic theory of the linear transport equation in anisotropic media

# publications[].label
Proliferation Resistance Analysis and Evaluation Tool for Observed Risk (PRAETOR) Methodology

# publications[].publisher
The Institute of Nuclear Materials Management

# publications[].label
A diffusion synthetic acceleration scheme for rectangular geometries based on bilinear discontinuous finite elements

# publications[].label
Goal-Based Error Estimation, Functional Correction, h, p and hp Adaptivity of the 1-D Diamond Difference Discrete Ordinate Method

# publications[].label
S2SA preconditioning for the S<inf>n</inf>equations with strictly positive spatial discretization

# publications[].label
Consistent and accurate schemes for coupled neutronics thermal-hydraulics reactor analysis

# publications[].label
Standard and goal-oriented adaptive mesh refinement applied to radiation transport on 2D unstructured triangular meshes

# publications[].label
Thermal Upscattering Acceleration Schemes for Parallel Transport Sweeps

# publications[].label
Adaptive hp- Mesh refinement applied to 1-D, one-group diffusion problems

# publications[].label
Spatial adaptivity for time-dependent diffusion problems

# publications[].label
Application of the entropy viscosity method to the 1-D 7-equation model for two-phase flows

# publications[].label
Exponentially-convergent Monte Carlo for the 1-D transport equation

# publications[].label
Axially Quadratic Discontinuous Finite Elements for Neutron Transport Reactor Simulations

# publications[].label
Simulations of single- and two-phase shock tubes and gravity-driven wave problems with the RELAP-7 nuclear reactor system analysis code

# publications[].label
Development of a joint US-RF educational program in advanced energy technologies

# publications[].label
Evaluation of high thermal conductivity oxide nuclear fuel concept containing beryllium

# publications[].label
Entropy-based viscous regularization for the multi-dimensional Euler equations in low-Mach and transonic flows

# publications[].label
Methodology for public safety, proliferation, and economics assessment of SMRs

# publications[].label
GeN-ROM-An OpenFOAM(R)-based multiphysics reduced-order modeling framework for the analysis of Molten Salt Reactors

# publications[].label
Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing

# publications[].label
Affine reduced-order model for radiation transport problems in cylindrical coordinates

# publications[].label
An Approach for Load Balancing  Massively  Parallel  Transport Sweeps on Unstructured Grids

# publications[].label
Reduced-order modeling of parameterized multi-group diffusion -eigenvalue problems

# publications[].label
A P1 conforming DSA scheme for DGFEM SN transport

# publications[].label
S2SA preconditioning for the Sn equations with strictly nonnegative spatial discretization

# publications[].label
Galerkin-quadratures for the S<inf>N</inf>method in 2D cartesian geometries and application to forward-peaked scattering particle transport problems

# publications[].label
A robust SN-DG-approximation for radiation transport in optically thick and diffusive regimes

# publications[].label
Multiphysics reactor-core simulations using the improved quasi-static method

# publications[].label
Verification of multiphysics software: Space and time convergence studies for nonlinearly coupled applications

# publications[].label
Convergence behavior of second-order transport equations in near-void problems

# publications[].label
Adaptive mesh refinement techniques for diffusion-synthetic- accelerated discrete-ordinates neutral particle transport

# publications[].label
Novel hybrid scheme to compute several dominant eigenmodes for reactor analysis problems

# publications[].label
Flux-corrected transport techniques applied to the radiation transport equation discretized with continuous finite elements

# publications[].label
Proper Generalized Decomposition of Multigroup Neutron Diffusion with Separated Space-Energy Representation

# publications[].label
Mesh generation for transport sweeps using a piece-wise linear discontinuous discretization

# publications[].label
Chapter 4 Molten salt reactor physics: characterization, neutronic performance, multiphysics coupling, and reduced-order modeling

# publications[].label
Chapter 7 Coupled multiphysics simulations in nuclear reactor design and safety

# publications[].label
Adjoint-based sensitivity for radiation transport using an Eddington tensor formulation

# publications[].label
Application of high-order implicit schemes for nonlinear multi-physics simulations

# publications[].label
Angular Multigrid Preconditioner for Krylov-Based Solution Techniques Applied to the Sn Equations with Highly Forward-Peaked Scattering

# publications[].label
Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems

# publications[].label
Lumping Techniques for DFEM SN Transport in Slab Geometry

# publications[].label
CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change model

# publications[].label
Iterative performance of various formulations of the SPN equations

# publications[].label
A positive non-linear closure for the SN equations with linear-discontinous spatial differencing

# publications[].label
Coupled Computational Fluid Dynamics-Discrete Element Method Study of Bypass Flows in a Pebble Bed Reactor

# publications[].label
Passive Detection of Small Low-Emission Sources: Two-Dimensional Numerical Case Studies

# publications[].label
On the Construction of Galerkin Angular Quadratures

# publications[].label
Parametric neutron diffusion using proper generalized decomposition for uncertainty quantification

# publications[].label
Application of duality principles to solve inverse particle transport problem: A framework

# publications[].label
A two-mesh adaptive mesh refinement technique for SN neutral-particle transport using a higher-order DGFEM

# publications[].label
Conservative nonlinear diffusion acceleration applied to the unweighted least-squares transport equation in MOOSE

# publications[].label
Goal-Based Error Estimation for the Multi-Dimensional Diamond Difference and Box Discrete Ordinate (SN) Methods

# publications[].label
Simulation of thermo-mechanical contact between fuel pellet and cladding in UO2 nuclear fuel rods

# publications[].label
Progress  In  Thermal-Hydraulics  Modeling Of The Molten Salt Fast Reactor

# publications[].label
Application of Duality Principles to Reflector Homogenization

# publications[].label
Application of hp Adaptivity to the Multigroup Diffusion Equations

# publications[].label
Pressure Reconstruction for Reduced Order Models of Convective Heat Transfer

# publications[].label
IAEA Initiative on Open-Source Nuclear Codes for Reactor Analysis

# publications[].label
A Monte Carlo implementation of the predictor-corrector Quasi-Static method

# publications[].label
Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith

# publications[].label
Noninvasive cross section reconstruction with tranport theory constraints

# publications[].label
Viscous regularization of the full set of nonequilibrium-diffusion Grey Radiation-Hydrodynamic equations

# publications[].label
Separated Representation of Spatial Dimensions in SN Neu- tron Transport using the Proper Generalized Decomposition

# publications[].label
Multi-dimensional automatic mesh refinement for the multigroup SPN equations

# publications[].label
Adaptive solution of the multigroup diffusion equation on irregular structured grids using a conforming finite element method formulation

# publications[].label
Parametric dynamic mode decomposition for reduced order modeling

# publications[].label
POSITIVE AND ASYMPTOTIC PRESERVING APPROXIMATION OF THE RADIATION TRANSPORT EQUATION

# publications[].publisher
Society for Industrial & Applied Mathematics (SIAM)

# publications[].label
Multiphysics Core Dynamics Simulation Using the Improved Quasi-Static Method

# publications[].label
Consistent accelerated schemes for nonlinear coupling problems in reactor analysis

# publications[].label
Hp-FEM automatic-mesh adaptivity applied to two dimensional neutron diffusion

# publications[].label
APPLICATION OF h-, p-, and hp-MESH ADAPTATION TECHNIQUES TO THE SP 3 EQUATIONS

# publications[].label
Application of multiphysics model order reduction to doppler/neutronic feedback

# publications[].label
Goal-oriented hp-Mesh adaptation for 1-D multigroup diffusion equations

# publications[].label
Deep learning for 2D passive source detection in presence of complex cargo

# publications[].label
Uncollided flux techniques for arbitrary finite element meshes

# publications[].label
Parametric uncertainty quantification using proper generalized decomposition applied to neutron diffusion

# publications[].label
An explicit, positivity-preserving flux-corrected transport scheme for the transport equation using continuous finite elements

# publications[].label
Discontinuous finite element discretizations for the SN neutron transport equation in problems with spatially varying cross sections

# publications[].label
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows

# publications[].label
Autonomous multi-purpose floating power system with a compact static pebble bed reactor

# publications[].label
Using Artificial Neural Networks To Accelerate Trans-  port Solves

# publications[].label
Extension of the entropy viscosity method to the Iow-Mach regime for the multi-dimensional euler equations

# publications[].label
Investigation of Misuse Potential and Detection for Homogeneous Fluoride Fast Molten Salt Reactors Based on Neutronics Signatures

# publications[].label
A Study of Various Thermal Upscat-  tering Acceleration Schemes for Massively Parallel Transport Sweeps

# publications[].label
Evaluation of pressure reconstruction techniques for Model Order Reduction in incompressible convective heat transfer

# publications[].label
Approaches to Load Balancing Massively Parallel Transport Sweeps on Unstructured Grids

# publications[].label
Parametric model-order reduction for radiation transport using multi-resolution proper orthogonal decomposition

# publications[].label
Nonnegative Methods for Bilinear Discontinuous Differencing of the SN Equations on Quadrilaterals

# publications[].label
A verification exercise in multiphysics simulations for coupled reactor physics calculations

# publications[].label
Progress in the integration of the 2d dg-fem s <inf>n</inf> transport solver xuthus into SCALE

# publications[].label
PWR fuel assembly optimization using simulated annealing with translat

# publications[].label
Neutronic evaluation of high thermal conductivity UO2-BeO fuel

# publications[].label
Some advances on inverse particle transport problems with applications to homeland security

# publications[].label
Local doppler broadening effects from thermal neutrons during transient testing

# publications[].label
Massively Parallel Transport Sweeps on Meshes with Cyclic Dependencies

# researcherOn[].label
CERT (Center for Exascale Radiation Transport)

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Texas A&M University Undergraduate Scholarship Nuclear Program

# researcherOn[].awardedBy.label
United States Nuclear Regulatory Commission - (Rockville, Maryland, United States)

# researcherOn[].label
TAMU Nuclear Engineering Graduate Fellowship Program

# researcherOn[].awardedBy.label
United States Nuclear Regulatory Commission - (Rockville, Maryland, United States)

# researcherOn[].label
Texas Engineering Experiment Station Fellowship and Scholarship Support

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Models with Multiple Levels of Fidelity, Tractability, and Computational Cost for Nuclear Weapon Radiation Effects

# researcherOn[].awardedBy.label
United States Department of Defense - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
NuSTEM: Nuclear Science, Technology and Education for Molten Salt Reactors

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# streetAddress
Texas A&M University; Nuclear Engineering; 3133 TAMU

# etdChairOf[].label
Rogers, Timothy James (2008-08). Pwr fuel assembly optimization using adaptive simulated annealing coupled with translat. Master's Thesis.

# etdChairOf[].label
Turcksin, Bruno 1985- (2012-11). Acceleration Techniques for Discrete-Ordinates Transport Methods with Highly Forward-Peaked Scattering. Doctoral Dissertation.

# etdChairOf[].label
Webster, Jennifer B (2013-07). Cost-Sensitive Classification Methods for the Detection of Smuggled Nuclear Material in Cargo Containers. Doctoral Dissertation.

# etdChairOf[].label
Bruss, Donald (2012-05). DSA Preconditioning for the S_N Equations with Strictly Positive Spatial Discretization. Master's Thesis.

# etdChairOf[].label
Ghaddar, Tarek Habib (2016-05). Load Balancing Unstructured Meshes for Massively Parallel Transport Sweeps. Master's Thesis.

# etdChairOf[].label
Fredette, Nathaniel (2011-12). Imaging Heterogeneous Objects Using Transport Theory and Newton's Method. Master's Thesis.

# etdChairOf[].label
McDermott, Patrick 1987- (2012-11). Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01. Master's Thesis.

# etdChairOf[].label
Delchini, Marc Olivier (2010-05). A Preliminary Study to Assess Model Uncertainties in Fluid Flows. Master's Thesis.

# etdChairOf[].label
Prince, Zachary Merritt (2017-05). Improved Quasi-Static Methods for Time-Dependent Neutron Diffusion and Implementation in Rattlesnake. Master's Thesis.

# etdChairOf[].label
Sternat, Matthew Ryan (2009-12). Application of a Constrained Optimization Technique to the Imaging of Heterogeneous Objects Using Diffusion Theory. Master's Thesis.

# etdChairOf[].label
Maginot, Peter Gregory (2010-12). A Nonlinear Positive Extension of the Linear Discontinuous Spatial Discretization of the Transport Equation. Master's Thesis.

# etdChairOf[].label
Hackemack, Michael Wayne (2016-06). Higher-Order DGFEM Transport Calculations on Polytope Meshes for Massively-Parallel Architectures. Doctoral Dissertation.

# etdChairOf[].label
Zhang, Yunhuang (2014-08). Even-Parity S_(N) Adjoint Method Including SP_(N) Model Error and Iterative Efficiency. Doctoral Dissertation.

# etdChairOf[].label
Maginot, Peter G (2015-07). Higher Order Discontinuous Finite Element Methods for Discrete Ordinates Thermal Radiative Transfer. Doctoral Dissertation.

# etdChairOf[].label
Lebrun-Grandie, Damien Thomas (2014-03). Contact Detection and Constraints Enforcement for the Simulation of Pellet/Clad Thermo-Mechanical Contact in Nuclear Fuel Rods. Doctoral Dissertation.

# etdChairOf[].label
Delchini, Marc (2014-10). Extension of the Entropy Viscosity Method to the Multi-D Euler Equations and the Seven-Equation Two-Phase Model. Doctoral Dissertation.

# etdChairOf[].label
Smith, Joshua 1987- (2012-12). Enhanced Thermal Conductivity UO2-BeO Nuclear Fuel: Neutronic Performance Studies and Economic Analyses. Master's Thesis.

# etdChairOf[].label
Bruss, Donald Eugene (2016-07). Adjoint-Based Uncertainty Quantification for Neutron Transport Calculations. Doctoral Dissertation.

# etdChairOf[].label
Metcalf, Richard R. (2009-05). New Tool for Proliferation Resistance Evaluation Applied to Uranium and Thorium Fueled Fast Reactor Fuel Cycles. Master's Thesis.

# etdChairOf[].label
Wang, Yaqi (2009-05). Adaptive Mesh Refinement Solution Techniques for the Multigroup SN Transport Equation Using a Higher-Order Discontinuous Finite Element Method. Doctoral Dissertation.

# etdChairOf[].label
Naramore, Michael J (2010-08). High Thermal Conductivity UO2-BeO Nulcear Fuel: Neutronic Performance Assessments and Overview of Fabrication. Master's Thesis.

# etdChairOf[].label
Hansel, Joshua Edmund (2016-08). Application of the Entropy Viscosity Method and the Flux-Corrected Transport Algorithm to Scalar Transport Equations and the Shallow Water Equations. Doctoral Dissertation.

# etdChairOf[].label
Chambers, Alex (2011-08). Multi-Recycling of Transuranic Elements in a Modified PWR Fuel Assembly. Master's Thesis.

# etdChairOf[].label
Hansel, Joshua Edmund (2013-04). Solution Techniques for Single-Phase Subchannel Equations. Master's Thesis.

# etdChairOf[].label
Peterson, Jacob Ross (2014-04). Exponentially-convergent Monte Carlo for the One-dimensional Transport Equation. Master's Thesis.

# etdChairOf[].label
Dugan, Kevin (2013-06). Dynamic Adaptive Multimesh Refinement for Coupled Physics Equations Applicable to Nuclear Engineering. Master's Thesis.

# etdChairOf[].label
Hackemack, Michael Wayne (2013-04). Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels. Master's Thesis.

# etdChairOf[].label
Wang, Yaqi (2006-12). hp-mesh adaptation for 1-D multigroup neutron diffusion problems. Master's Thesis.

# etdChairOf[].label
Chance, Christopher (2014-09). Partial Core Blockage Simulation Using COBRA-TF. Master's Thesis.

# etdChairOf[].label
Mahadevan, Vijay Subramaniam (2010-08). High Resolution Numerical Methods for Coupled Non-linear Multi-physics Simulations with Applications in Reactor Analysis. Doctoral Dissertation.

# etdChairOf[].label
Zhang, Yunhuang (2009-12). Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies. Master's Thesis.