MCNP-PoliMi simulation of neutron radiography measurements of mass determination for a trough of UO3

B. R. Grogan, J. T. Mihalczo, J. A. Mullens

Research output: Contribution to journalArticlepeer-review

Abstract

The Nuclear Materials Identification System (NMIS) with a deuterium-tritium neutron source has been used to image fissile material inside containers to determine geometry This paper investigates the possibility that the NMIS could be used to determine the mass of UO3 powder of variable shape or density in a container of arbitrary but known shape. The MCNP-PoliMi computer code was used to model measurements of several fill scenarios of a trough-shaped container by the NMIS to estimate how accurately the mass of the UO3 powder could be determined.

Original languageEnglish
Pages (from-to)27-32
Number of pages6
JournalJournal of Nuclear Materials Management
Volume36
Issue number1
StatePublished - Sep 2007

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