There are 1 repository under neutron-transport topic.
OpenMC Monte Carlo Code
Method of Characteristics neutral particle transport code for reactor physics written in Julia.
MC/DC: Monte Carlo Dynamic Code
High performance cyclic ray tracing algorithm for neutron transport in Julia.
An unstructured mesh library for automated method of characteristic mesh generation
GEANT4 simulation code for LCS gamma-ray sources and flat efficiency moderated He-3 counters array dedicated to photoneutron reaction studies
Isotropic Monte Carlo simulations examining thermal neutron statistics in water, lead, and graphite, including animated neutron history, delta tracking and spherical geometry adaptations.
A neutron transport mini-app with both diamond-difference and linear-discontinuous finite element spatial discretisation options
clone of diamond difference method configured to run with response matrix method for extended domains
This project aims to optimize the accuracy of critical size estimations by understanding and minimizing statistical fluctuations and transient effects. Once an optimal strategy is devised, the focus shifts to implementing a cylindrical geometry with a height equal to the radius and using the Monte Carlo code to estimate the critical length.