Method for nonintrusively identifying a contained material utilizing uncollided nuclear transmission measurements
Abstract
An improved nuclear diagnostic method identifies a contained target material by measuring onaxis, monoenergetic 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 crosssections 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 gammaray beam. Alternatively, the measurements are used to derive a minimization formula based on the macroscopic neutron crosssections for the uncollided particle radiation at the two neutron beam energies, or the linear attenuation coefficients for the uncollided particle radiation at the two gammaray beam energies. A candidate target material database, including known macroscopic neutron crosssections or linear attenuation coefficients for target materials at the selected neutron or gammaray 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:
 Issue Date:
 Research Org.:
 Idaho National Laboratory (INL), Idaho Falls, ID (United States)
 Sponsoring Org.:
 USDOE
 OSTI Identifier:
 1245966
 Patent Number(s):
 6320193
 Application Number:
 09/259,418
 Assignee:
 The United States of America as represented by the United States Department of Energy (Washington, DC)
 Patent Classifications (CPCs):

G  PHYSICS G01  MEASURING G01N  INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
 DOE Contract Number:
 AC0794ID13223
 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 nonintrusively 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 nonintrusively identifying a contained material utilizing uncollided nuclear transmission measurements. United States.
Morrison, John L., Stephens, Alan G., and Grover, S. Blaine. Tue .
"Method for nonintrusively identifying a contained material utilizing uncollided nuclear transmission measurements". United States. https://www.osti.gov/servlets/purl/1245966.
@article{osti_1245966,
title = {Method for nonintrusively 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 onaxis, monoenergetic 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 crosssections 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 gammaray beam. Alternatively, the measurements are used to derive a minimization formula based on the macroscopic neutron crosssections for the uncollided particle radiation at the two neutron beam energies, or the linear attenuation coefficients for the uncollided particle radiation at the two gammaray beam energies. A candidate target material database, including known macroscopic neutron crosssections or linear attenuation coefficients for target materials at the selected neutron or gammaray 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 = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2001},
month = {11}
}