# 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}

}