Applied Math Seminar: David Millman on "Some Geometric Problems in Monte Carlo Transport Solvers"
- Thursday, February 7, 2019 from 3:10pm to 4:00pm
- Wilson Hall, 1-144 - view map
Applied Mathematics Seminar:
Dr. David Millman (MSU Computer Science)
Title: Some Geometric Problems in Monte Carlo Transport Solvers
Monte Carlo (MC) codes for solving the Neutron Transport Equation often represent a domain using a Constructive Solid Geometry (CSG) representation. In particular, the geometry of the domain is many "components" defined by set operations on half-spaces defined by quadrics. While a CSG representation is excellent for an engineer modeling a nuclear reactor, it can add substantial complexity into a solver. For example, many MC solvers spend as much as 1/3 of their total computation performing point location and distance to surface calculations or use an entire super computer to compute the volume of every component. In this talk, we will introduce some of the geometric problems that occur when solving the Transport Equation with MC methods and how we can use techniques from Computational Geometry to address these problems.