MCNP-PoliMi Simulation of Neutron Radiography

Publication Date
Volume
36
Issue
1
Start Page
27
Author(s)
B. R. Grogan - Oak Ridge National Laboratory
John T. Mihalczo - Oak Ridge National Laboratory
J.A. Mullens - Oak Ridge National Laboratory
File Attachment
V-36_1.pdf1.08 MB
Abstract
The Nuclear Materials Identification System (NMIS) with adeuterium–tritium neutron source has been used to image fissilematerial inside containers to determine geometry. This paperinvestigates the possibility that the NMIS could be used todetermine the mass of UO3 powder of variable shape or densityin a container of arbitrary but known shape. The MCNPPoliMicomputer code was used to model measurements of severalfill scenarios of a trough-shaped container by the NMIS toestimate how accurately the mass of the UO3 powder could bedetermined.
Additional File(s) in Volume
V-36_1.pdf1.08 MB
V-36_2.pdf2.92 MB
V-36_3.pdf1.09 MB
V-36_4.pdf3.16 MB