L.R.C. Moraes

This researcher develops mathematical and computational methods for modeling how neutrons move through materials, which is central to designing and analyzing nuclear reactors. The work focuses on 'transport equations' that describe particle behavior, including advanced 'nonclassical' models for irregular or randomly structured media, and numerical techniques (such as discrete ordinates and response matrix methods) to solve these equations efficiently. Applications include reactor physics calculations, estimating neutron sources in subcritical systems, and improving computational accuracy in both simple and complex geometries.

Publication output was minimal before 2019, rose to a peak around 2021, and has since continued at a steady pace of about 3-4 papers per year through 2025.

Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026