The study of the neutron transport equation is a delicate blend of theoretical mathematics, numerical methods and computational strategies describing the interaction of neutrons and nuclei. Not only do we gain physical insight from the solution to the transport equation, but we also create new mathematics and numerical methods for the solution of equations. This short course is offered to those individuals who want to experience the elegance of analytical transport theory and how this theory can impact the development of transport methods for application.
In this course, Case Studies in Neutron Transport Theory, we shall concentrate on transforming theoretical solution representations of the neutron transport equation into numerically useable forms. The course will study reactor physics from neutron slowing down to multidimensional multigroup theory and criticality. Though the backdrop is reactor physics, our emphasis will be on analytical manipulations of the transport equation and the numerical realization of its solutions.
This course is also available remotely via live telecommunications for an additional
$600 per student ($1,895 total). The course is delivered synchronously (i.e.,
live and interactive) to the student's computer via the Internet using software
provided by the university. For more information contact Caroline Bowers at
(865) 974-8772.
COURSE OBJECTIVES
The main objective of this course is to provide a basis for understanding the fundamental concepts of neutron transport theory. This will include recent theoretical as well as numerical advances in analytical benchmarking.
Course attendees will become familiar with:
Finally, the course material may spark the imagination of those participants who are especially creative, and who seek a creative outlet.
APPLICATION OF COURSE KNOWLEDGE
The course material will find use in several areas. First, knowledge of analytical solutions increases one’s awareness of what is available for prediction. While analytical solutions to idealized transport scenarios do not necessarily apply directly to operating systems, they can provide some indication regarding operation of portions of a system. However, the most widespread use of the course material will be for the generation of standards to which one can compare proposed or legacy algorithms. This will provide operational testing of an algorithm as well as an overall algorithmic assessment. The course will include demonstrations of the analytical benchmark library accompanying the text.
COURSE PREPARATION
Participants should be familiar with reactor physics and the operation of nuclear systems. In addition, some familiarity with mathematics through vector calculus and linear algebra is helpful. The participant should also be familiar with elementary numerical methods and come with an open mind awaiting new information.
For best results, we encourage participants to bring a laptop equipped with a FORTRAN compiler and plotting package.
RESOURCE MATERIAL PROVIDED
Lecture notes including the course text: Analytical Benchmarks: Case Studies in Neutron Transport Theory by B. Ganapol, are provided. This includes computer programs for the analytical benchmark library accompanying the text.
COURSE SCHEDULE
Monday, August 11, 2008
Tuesday, August 12, 2008
Wednesday, August 13, 2008
Thursday, August 14, 2008
Friday, August 15, 2008
INSTRUCTOR
Dr. B. D. Ganapol is professor in the Aerospace and Mechanical Department at the University of Arizona and a Research Professor in the Nuclear Engineering Department at the University of Tennessee. He is a noted expert in analytical methods of solution to the transport equation, in particular, the generation of benchmark solutions for code verification. He is currently a consultant at Los Alamos National Laboratory, Idaho National Laboratory and Oak Ridge National Laboratory and also consults for NASA on satellite remote sensing of vegetation.