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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.:
US Department of Energy (US)
OSTI Identifier:
782828
Patent Number(s):
PATENTS-US-A9259418
Application Number:
9-259,418; TRN: AH200128%%4
Assignee:
DOEGC; EDB-01:070222
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Patent Application
Resource Relation:
Patent File Date: 1999 Feb 26; Other Information: PBD: 26 Feb 1999
Country of Publication:
United States
Language:
English
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; DIAGNOSTIC TECHNIQUES; ALGORITHMS; ATTENUATION; CROSS SECTIONS; NEUTRON BEAMS; TARGETS; GAMMA RADIATION; CHEMICAL COMPOSITION

Citation Formats

Morrison, John L, Stephens, Alan G, and Grover, Blaine S. Method for Non-Intrusively Identifying a Contained Material Utilizing Uncollided Nuclear Transmission Measurements. United States: N. p., 1999. Web.
Morrison, John L, Stephens, Alan G, & Grover, Blaine S. Method for Non-Intrusively Identifying a Contained Material Utilizing Uncollided Nuclear Transmission Measurements. United States.
Morrison, John L, Stephens, Alan G, and Grover, Blaine S. Fri . "Method for Non-Intrusively Identifying a Contained Material Utilizing Uncollided Nuclear Transmission Measurements". United States. https://www.osti.gov/servlets/purl/782828.
@article{osti_782828,
title = {Method for Non-Intrusively Identifying a Contained Material Utilizing Uncollided Nuclear Transmission Measurements},
author = {Morrison, John L and Stephens, Alan G and Grover, Blaine S},
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/782828}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {2}
}

Patent Application:

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