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

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

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

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

Material Security and Counterproliferati

Research output: Contribution to journal › Article › peer-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 language	English
Pages (from-to)	27-32
Number of pages	6
Journal	Journal of Nuclear Materials Management
Volume	36
Issue number	1
State	Published - Sep 2007

Cite this

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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.",

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N2 - 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.

AB - 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.

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

Abstract

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