NE 723 Neutron Transport Theory

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. 3 credit hours.


• 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.

• Computer and Internet Requirements

NCSU and Engineering Online have recommended minimum specifications for computers. For details, click here.

• Instructor

Dr. Dmitriy Anistratov, Associate Professor
Nuclear Engineering
Burlington Laboratory 2105, Box 7909
NCSU Campus
Raleigh, NC 27695

Phone: 919-513-4353
Fax: 919-515-5115
Web Site: