3 Credit Hours

YA

Yousry Azmy

Duke Energy Distinguished Professor

919-515-3385 [email protected]

Derivation of the nonlinear Boltzmann equation for a rarefied gas and linearization to the equation of transport of neutral particles. Deterministic methods for solving the neutron transport equation: Multigroup energy discretization; Discrete Ordinates angular discretization; various spatial discretization methods. Convergence of numerical solutions with discretization refinement. Iterative solution algorithms: inner, outer, and power iterations. Spectral analysis of inner iterations convergence and acceleration. Selection of advanced topics.

Prerequisites

• NE 401/501: Reactor Analysis and Design.
• Advanced math & moderate programming skills are necessary. Permissible programming languages: Fortran or C++

Course Learning Outcomes

• Explain the physics foundation of the neutron transport equation (NTE) and its underlying assumptions
• Identify relationships among various numerical methods employed in solving the NTE
• Analyze and justify discretization methods in energy, angle, and space for computationally solving the NTE
• Apply spectral analysis to predict performance of iterative algorithms for solving the NTE
• Implement new Fortran or C++ code or maintain existing code for solving the NTE

Course Requirements

Policy on late submission of Homework & Code Assignments:

• Up to one week past due date
• Grade reduced by 50%
• No credit for homework submitted more than one week past the due date

Textbook

E. E. Lewis and W. F. Miller, Computational Methods of Neutron Transport, American Nuclear Society (1993) – $70

Created: 10/05/2026.