Yousry Azmy

Distinguished Professor of Nuclear Engineering, Joint Faculty Appointment with INL

Dr. Yousry Azmy’s contributions to nuclear computational science include:

  • development of the class of Arbitrarily High Order Transport (AHOT) methods in Cartesian geometry with two flavors—nodal and characteristic;
  • Adjacent-cell Preconditioner (AP) acceleration of iterative solution algorithms for the transport equation;
  • error analysis of the Nodal Integral Method for solving the neutron diffusion equation;
  • error estimation and adaptive methods for transport methods;
  • algorithm design, analysis, and parallel performance modeling for multiprocessing schemes for the transport equation;
  • detailed modeling of nuclear systems via deterministic transport models and optimal shape design for nuclear components using search techniques.


Ph.D. 1985

Nuclear Engineering

University of Illinois, Urbana-Champaign

M.S. 1983

Nuclear Engineering

University of Illinois, Urbana-Champaign

B.S. 1978

Nuclear Engineering

Alexandria University

Research Description

Dr. Azmy's research is focused on the development, implementation, and analysis of advanced methods and solution techniques for particle transport problems. This defines an area within the broader field of nuclear computational science whose ultimate purpose is to provide the community of nuclear scientists and engineers with advanced computational codes that comprise an enabling technology for addressing a multitude of problems involving particle and radiation transport phenomena. In this regard he contributed to Oak Ridge National Laboratory's DOORS code package that includes, among others, the renowned DORT and TORT codes, serving as lead developer of the latter in the late nineties.


Hybrid approaches for accelerated convergence of block-Jacobi iterative methods for solution of the neutron transport equation
Hoagland, D. S., & Azmy, Y. Y. (2021), JOURNAL OF COMPUTATIONAL PHYSICS, 439.
On the Regularity Order of the Pointwise Uncollided Angular Flux and Asymptotic Convergence of the Discrete Ordinates Approximation of the Scalar Flux
Hu, X., & Azmy, Y. Y. (2021), NUCLEAR SCIENCE AND ENGINEERING, 195(6), 598–613.
Solution Irregularity Remediation for Spatial Discretization Error Estimation for S-N Transport Solutions
Hart, N. H., & Azmy, Y. Y. (2021, November 8), NUCLEAR SCIENCE AND ENGINEERING.
Solution of the Neutron Transport Equation on Unstructured Grids Using the Parallel Block Jacobi-Integral Transport Matrix Method via the Novel Green's Function ITMM Construction Algorithm on Massively Parallel Computer Systems
Hoagland, D. S., Yessayan, R. A., & Azmy, Y. Y. (2021, May 10), NUCLEAR SCIENCE AND ENGINEERING.
Asymptotic convergence of the angular discretization error in the scalar flux computed from the particle transport equation with the method of discrete ordinates
Hu, X., & Azmy, Y. Y. (2020), ANNALS OF NUCLEAR ENERGY, 138.
Sequential optimal positioning of mobile sensors using mutual information
Schmidt, K., Smith, R. C., Hite, J., Mattingly, J., Azmy, Y., Rajan, D., & Goldhahn, R. (2019), STATISTICAL ANALYSIS AND DATA MINING, 12(6), 465–478.
Numerical convergence and validation of the DIMP inverse particle transport model
Nelson, N., & Azmy, Y. (2017), Nuclear Engineering and Technology, 49(6), 1358–1367.
Validation and uncertainty quantification of detector response functions for a 1″×2″ NaI collimated detector intended for inverse radioisotope source mapping applications
Nelson, N., Azmy, Y., Gardner, R. P., Mattingly, J., Smith, R., Worrall, L. G., & Dewji, S. (2017), Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 410, 1–15.
Recent Studies on the Asymptotic Convergence of the Spatial Discretization for Two-Dimensional Discrete Ordinates Solutions
Barichello, L. B., Tres, A., Picoloto, C. B., & Azmy, Y. Y. (2016), JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT, 45(4), 299–313.
Comparison of spatial discretization methods for solving the S-N equations using a three-dimensional method of manufactured solutions benchmark suite with escalating order of nonsmoothness
Schunert, S., & Azmy, Y. (2015), Nuclear Science and Engineering, 180(1), 1–29.

View all publications via NC State Libraries


A Computational Tool Compatible with NEAMS Code Packages for Optimizing the Shape of Nuclear Reactor Components and of Whole Core Performance
US Dept. of Energy (DOE)(10/01/22 - 9/30/24)
Release No, 00002 NUC Contract Proposal for FY 15 (2014-2015). Formerly ACE - Academic Center for Excellence
US Dept. of Energy (DOE)(10/15/14 - 9/30/23)
Consortium for Nonproliferation Enabling Capabilities
US Dept. of Energy (DOE)(7/31/14 - 9/30/20)
Accurate Holdup Calculations with Predictive Modeling and Data Integration
US Dept. of Energy (DOE)(10/01/12 - 12/31/16)
National Academy for Nuclear Training Fellowship Program 2014-2015
National Academy for Nuclear Training(1/01/15 - 12/31/15)
National Academy for Nuclear Training Fellowship Program 2013-2014
National Academy for Nuclear Training(1/01/14 - 12/31/14)
Advanced Radiation Transport Methods on Unstructured Grids & Solution Algorithms for Multiprocessors
US Dept. of Energy (DOE)(2/17/14 - 9/30/14)
North Carolina State UNiversity's Graduate Fellowship in Nuclear Engineering (NCSU-GFINE)
US Nuclear Regulatory Commission(7/31/09 - 9/30/14)
Joint Faculty Appointment for Dr. John Mattingly
Oak Ridge National Laboratories - UT-Battelle LLC(8/16/13 - 5/15/14)
Joint Faculty Appointment Between UT-Batelle-ORNL and NC State University for John Mattingly
Oak Ridge National Laboratories - UT-Battelle LLC(10/01/11 - 5/15/14)