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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:
;
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1163979
Patent Number(s):
8,891,720
Application Number:
12/712,040
Assignee:
Lawrence Livermore National Security, LLC (Livermore, CA) OAK
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}
}

Patent:

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