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Schedule: Sunday May 9, 2010 8:00 AM - Noon, #2
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| Subject |
Scope |
| Introduction to Neutron Transport Equations |
Several equivalent forms of the neutron transport equation are presented along with the common integro-differential form. |
| Neutron Slowing Down |
The neutron slowing down equation in an infinite medium is solved using a Laplace transform for the constant cross section approximation in addition to the multigroup form with analytically generated group parameters. |
| 1D Monoenergetic Neutron Transport |
The 1D monoenergetic transport equation is derived and solved using Fourier transforms for an infinite medium. Then, the singular integral form of the transport equation is solved numerically with the FN method. |
| 1D Multigroup Neutron Transport |
Using the Fourier transform, the multigroup neutron transport equation is solved in plane and spherical geometries. |
| Infinite Medium 3D Multigroup Neutron Transport |
A multigroup 3D solution is derived in an infinite medium using the point kernel method.
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| GUI Demonstrations |
Several benchmarks are demonstrated using recently developed GUIs. |
| The future of Benchmarking |
Convergence acceleration, characterizing “benchmarking in place”, is presented as the future of benchmarking in transport theory. |
| The Workshop is scheduled for 4 hours. Please check later for a final schedule. |
