# 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}

}