This paper aims to stimulate research and focus the attention of deterministic radiation transport code developers and users on further methodologies in transport analysis that some recent additions to the code package BOT3Ppotentially make it possible on structured Cartesian or cylindrical mesh grids simulating complex geometries. In particular, BOT3P Version 5.0 con compute possible area/volume error of material zones due to the stair-cased geometrical representation and automatically correct material densities in order to conserve masses, as described in a previous BOT3P paper published in Volume 154, Number 2 of Nuclear Science and Engineering to which tbc presentone is logically and strictly related. When calculating areas and volumes refinements, or when reducing the problem sizes of a voxelized geometry, typical of medical applications, BOT3P generates binary files that store also a finesub-mesh grid for each coarse cell at material interfaces. These files were originally conceived only for density correction computation and plotting purposes. However, the availability of such cell data intuitively suggests multi-step transport analysis approaches that may combine detailed solutions at material interfaces with acceptable problemsizes and computational times. Reaching this appealing target could let deterministic codes based on structured mesh grid successfully deal with any challenging geometry problem. That might be particularly useful in medical and reactor applications.
|Titolo:||Potential Enhanced Performances in Radiation Transport Analysis on Structured Mesh Grids Made Available by BOT3P|
|Data di pubblicazione:||1-set-2007|
|Appare nelle tipologie:||1.1 Articolo in rivista|