NE 723 Neutron Transport Theory
3 Credit Hours
Advanced theory of neutron transport and computational methods of solving particle transport (linear Boltzmann) equation for reactor physics problems. Principle topics: models of neutron transport; analytic methods for solving transport equation; asymptotic diffusion limit; PN and SPN methods, homogenization methodology; numerical methods for multidimensional problems; computational methods for multiphysics problems. Objective is to enable students to read literature and perform relevant analysis of neutron transport and reactor-physics problems.
Prerequisite
NE 401 / NE 501 Reactor Analysis and Design or NE 520 Radiation and Reactor Fundamentals.
Course Objectives
By the end of the course, the students will be able to:
- formulate advanced mathematical and physical models of neutron transport in nuclear reactors;
- identify domain of applicability of these models and their approximations;
- formulate computational methods for solving neutron transport problems;
- apply neutron transport models and numerical methods for nuclear reactor analysis;
- read advanced literature and perform relevant analysis of neutron transport and reactor physics problems.
Course Requirements
- Homeworks: 30%
- Computational projects: 30%
- Paper presentation: 10%
- Final project: 30%
The instructor reserves an option to give class and final examinations.
Textbook
Lecture notes
List of recommended books:
- Nuclear Reactor Theory, G. Bell & S. Glasstone, Krieger, 1985.
- Computational Methods of Neutron Transport, E.E. Lewis & W.F. Miller, Jr., ANS, 1993.