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:
- 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:
- 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 = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Nov 20 00:00:00 EST 2001},
month = {Tue Nov 20 00:00:00 EST 2001}
}