Course Description
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.
Spring 2025
Instructors
Meeting Patterns
Classes Start:
January 6, 2025
Classes End:
April 22, 2025
Location:
00327 111 Lampe Drive
Class Days:
M W
Class Start Time:
10:15am
Class End Time:
11:30am
Class Type:
Lecture
Credits:
3.00
Restrictions:
NE 401/501: Reactor Analysis and Design Advanced math & moderate programming skills are necessary. Permissible programming languages: Fortran or C++
