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Title: 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 Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1459003
Patent Number(s):
10001571
Application Number:
14/515,321
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
Resource Relation:
Patent File Date: 2014 Oct 15
Country of Publication:
United States
Language:
English

Citation Formats

Rowland, Mark S., and Snyderman, Neal J. Fission meter and neutron detection using poisson distribution comparison. United States: N. p., 2018. 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/1459003.
@article{osti_1459003,
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 = {Tue Jun 19 00:00:00 EDT 2018},
month = {Tue Jun 19 00:00:00 EDT 2018}
}

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