Understanding the distribution of neutrons inside a reactor core is essential for nuclear engineering tasks. The interaction of these neutrons determine optimal fuel rod placement and geometry. Using MCNP 6.2, we can generate a Monte Carlo simulation of the position of neutrons given various fuel rod designs.
In this example project, we take the point cloud data from MCNP6.2 and generate a scalar field, using Delaunay triangulation to create a geometry. From here, we can use OpenGL to visualize this data. Our visualization technique uses RGB color mapping and height mapping to demonstrate neutron density at various level sets.
Requires Visual Studio. To run, load learnply.sln solution file and execute learnply.cpp.
Project was completed as a part of CS-553 Scientific Visualization @ OSU. Template code provided by Dr. Eugene Zhang. Thanks to Massimo Larsen for providing simulation data and subject matter advice.