Fission meter and neutron detection using poisson distribution comparison
Abstract
A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material.
- Inventors:
- Issue Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1163979
- Patent Number(s):
- 8891720
- Application Number:
- 12/712,040
- Assignee:
- Lawrence Livermore National Security, LLC (Livermore, CA)
- Patent Classifications (CPCs):
-
G - PHYSICS G01 - MEASURING G01T - MEASUREMENT OF NUCLEAR OR X-RADIATION
G - PHYSICS G01 - MEASURING G01V - GEOPHYSICS
- DOE Contract Number:
- W-7405-ENG-48
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
Citation Formats
Rowland, Mark S, and Snyderman, Neal J. Fission meter and neutron detection using poisson distribution comparison. United States: N. p., 2014.
Web.
Rowland, Mark S, & Snyderman, Neal J. Fission meter and neutron detection using poisson distribution comparison. United States.
Rowland, Mark S, and Snyderman, Neal J. Tue .
"Fission meter and neutron detection using poisson distribution comparison". United States. https://www.osti.gov/servlets/purl/1163979.
@article{osti_1163979,
title = {Fission meter and neutron detection using poisson distribution comparison},
author = {Rowland, Mark S and Snyderman, Neal J},
abstractNote = {A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2014},
month = {11}
}
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