Comparison of nested geometry treatments within GPU-based Monte Carlo neutron transport simulations of fission reactors
The International Journal of High Performance Computing Applications
Published online on September 30, 2025
Abstract
The International Journal of High Performance Computing Applications, Volume 40, Issue 4, Page 466-486, July 2026.
Monte Carlo (MC) neutron transport provides detailed estimates of radiological quantities within fission reactors. This involves tracking individual neutrons through a computational geometry. CPU-based MC codes use multiple polymorphic tracker types with ...
Monte Carlo (MC) neutron transport provides detailed estimates of radiological quantities within fission reactors. This involves tracking individual neutrons through a computational geometry. CPU-based MC codes use multiple polymorphic tracker types with ...