NE 723 Neutron Transport Theory
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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.



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
Email: anistratov@ncsu.edu
Web Site: https://www.ne.ncsu.edu/people/dyanistr

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