This course provides an in-depth review of modern computational techniques used for solving the linear boltzmann equation, with specific applications to neutron and photon radiation transport problems. Topics to be covered include: an introduction to the physical processes that govern radiation transport through materials, monte carlo methods for the simulation of radiation transport, a first-principles derivation of the boltzmann radiation transport equation for multiplying and non-multiplying systems, the multi-group, diffusion, and discrete ordinates approximations to the transport equation, expansion of the scattering kernel in legendre polynomials, and numerical methods for approximating solutions to the transport equation. In addition, the course will review many commonly used numerical methods for solving integral and differential equations, including: finite differencing, numerical quadrature, harmonic analysis, and the power method for solving eigenvalue problems. Topics covered in the class will be reinforced with weekly programming exercises designed to illustrate the different methods for solving the boltzmann radiation transport equation and demonstrate how these methods can be used to solve realistic problems related to nuclear reactor and radiation shielding analysis. The course will also places a strong emphasis on formal quality assurance methods (and best-practices) for the development, verification, and validation of scientific computer codes intended for use in engineering design calculations of record.
Grading Basis
Grad Letter Grade
Lecture - Required
ME 2118
Academic Group
Swanson School of Engineering
Academic Organization
Mechanical Engineering
Pittsburgh Campus
Enrollment Requirements
PROG: Swanson School of Engineering
Typically Offered