ne.gif (2791 bytes)     NE583 Radiation Transport Methods

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Course Syllabus

Instructor:       Ronald E. Pevey, Ph.D., P.E., M.B.A.

Office:             201-A Nuclear Engineering Building

Office Hours:   By appointment.

Telephone:       974-7573

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: 

  • The derivation of the Boltzmann transport equation in its various forms.
  • Legendre scattering treatment
  • Numerical treatments of space, energy, and direction dimensions
  • Derivation and use of the adjoint Boltzmann Equation
  • The principal deterministic techniques in use to solve the Boltzmann Equation:
    • 1D Discrete Ordinates
      Multidimensional Discrete Ordinates
      Integral transport theory
Grading: The final grade will be based on four criteria: 
  • Test#1                    25% 
  • Test#2                    25%
  • Final                       25%
  • Homework             25%
A ten-point scale will be used to assign grades.


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