Instructor: Ronald E. Pevey, Ph.D., P.E., M.B.A.
Office: 201-A Nuclear Engineering Building
Office Hours: By appointment.
Course Description: This course covers the principal methods in used for deterministically solving the Boltzmann transport equation for neutral particles (neutrons and photons). The prime application is radiation shielding problems, with only passing reference to the treatment of fission processes. The principal emphasis will be on giving students a grounding in the numerical techniques that have shown themselves useful in solving the neutral partical transport equation and in applications of modern methods to shielding situations.
Required Text: Lewis, E.E., and Miller, W.F., Jr.; Computational Methods of Neutron Transport, American Nuclear Society, La Grange Park, IL, 1993.
Course Objectives: By taking this course, the student should gain a basic understanding of:
Multidimensional Discrete Ordinates
Integral transport theory
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