2 papers
cs.DC2025
GPU Acceleration of Monte Carlo Tallies on Unstructured Meshes in OpenMC with PUMI-Tally
Fuad Hasan, Cameron W. Smith, Mark S. Shephard +5
Unstructured mesh tallies are a bottleneck in Monte Carlo neutral particle transport simulations of fusion reactors. This paper introduces the PUMI-Tally library that takes advanta…
physics.plasm-ph2024
Demonstration of OpenMC as a framework for atomic transport and plasma interaction
George J. Wilkie, Paul K. Romano, R. Michael Churchill
Modern tooling is demanded for predicting the transport and reaction characteristics of atoms and molecules, especially in the context of magnetic confinement fusion. DEGAS2, among…