Parallelization of a coarse-mesh neutron transport method applied in the solution of one-dimensional neutron shielding problems

In this work, a coarse-mesh method used in the solution of neutron shielding problems slab geometry is parallelized, using memory shared environment OpenMP. The transport problem modelled linearized Boltzmann equation considering energy multigroup theory and discrete ordinate formulation ( ). numerical method, named Modified Spectral Deterministic (MSD), uses neutrons intranodal general alongside an iterative process to calculate outgoing angular fluxes on nodal interfaces. Two model-problems are solved, comparing execution time different number threads. results, which achieved around 30% 50% better time, were generated programming language C++.&nbsp