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Title: Method for non-intrusively identifying a contained material utilizing uncollided nuclear transmission measurements

Abstract

An improved nuclear diagnostic method identifies a contained target material by measuring on-axis, mono-energetic uncollided particle radiation transmitted through a target material for two penetrating radiation beam energies, and applying specially developed algorithms to estimate a ratio of macroscopic neutron cross-sections for the uncollided particle radiation at the two energies, where the penetrating radiation is a neutron beam, or a ratio of linear attenuation coefficients for the uncollided particle radiation at the two energies, where the penetrating radiation is a gamma-ray beam. Alternatively, the measurements are used to derive a minimization formula based on the macroscopic neutron cross-sections for the uncollided particle radiation at the two neutron beam energies, or the linear attenuation coefficients for the uncollided particle radiation at the two gamma-ray beam energies. A candidate target material database, including known macroscopic neutron cross-sections or linear attenuation coefficients for target materials at the selected neutron or gamma-ray beam energies, is used to approximate the estimated ratio or to solve the minimization formula, such that the identity of the contained target material is discovered.

Inventors:
; ;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1245966
Patent Number(s):
6,320,193
Application Number:
09/259,418
Assignee:
The United States of America as represented by the United States Department of Energy (Washington, DC)
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Patent
Resource Relation:
Patent File Date: 1999 Feb 26
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 43 PARTICLE ACCELERATORS; 97 MATHEMATICS AND COMPUTING

Citation Formats

Morrison, John L., Stephens, Alan G., and Grover, S. Blaine. Method for non-intrusively identifying a contained material utilizing uncollided nuclear transmission measurements. United States: N. p., 2001. Web.
Morrison, John L., Stephens, Alan G., & Grover, S. Blaine. Method for non-intrusively identifying a contained material utilizing uncollided nuclear transmission measurements. United States.
Morrison, John L., Stephens, Alan G., and Grover, S. Blaine. Tue . "Method for non-intrusively identifying a contained material utilizing uncollided nuclear transmission measurements". United States. https://www.osti.gov/servlets/purl/1245966.
@article{osti_1245966,
title = {Method for non-intrusively identifying a contained material utilizing uncollided nuclear transmission measurements},
author = {Morrison, John L. and Stephens, Alan G. and Grover, S. Blaine},
abstractNote = {An improved nuclear diagnostic method identifies a contained target material by measuring on-axis, mono-energetic uncollided particle radiation transmitted through a target material for two penetrating radiation beam energies, and applying specially developed algorithms to estimate a ratio of macroscopic neutron cross-sections for the uncollided particle radiation at the two energies, where the penetrating radiation is a neutron beam, or a ratio of linear attenuation coefficients for the uncollided particle radiation at the two energies, where the penetrating radiation is a gamma-ray beam. Alternatively, the measurements are used to derive a minimization formula based on the macroscopic neutron cross-sections for the uncollided particle radiation at the two neutron beam energies, or the linear attenuation coefficients for the uncollided particle radiation at the two gamma-ray beam energies. A candidate target material database, including known macroscopic neutron cross-sections or linear attenuation coefficients for target materials at the selected neutron or gamma-ray beam energies, is used to approximate the estimated ratio or to solve the minimization formula, such that the identity of the contained target material is discovered.},
doi = {},
url = {https://www.osti.gov/biblio/1245966}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2001},
month = {11}
}

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