Computation of 3D neutron fluxes in one pin hexagonal cell

ARRC: A random ray neutron transport code for nuclear reactor simulation

“…The Random Ray Method (TRRM) is a recently developed hybrid neutron transport method [1] based on the Method of Characteristics (MOC) [18,20,21,22]. MOC solves a partial differential equation (PDE) by defining characteristic lines (or curves) along which the PDE is reduced to an ordinary differential equation (ODE).…”

The Random Ray Method for neutral particle transport

“…While 2D MOC has long been used in reactor design and engineering as an efficient simulation method for smaller problems, the transition to 3D has only begun recently, and to our knowledge no 3D MOC based codes are currently used in industry. The delay of the onset of full 3D codes can be attributed to the impossibility of "naively" scaling current 2D codes into 3D due to prohibitively high memory requirements, though there is ongoing work into more optimal 3D MOC methods [1,16,17,18,19,20].…”