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Fission Meter and Neutron Detection Using Poisson Distribution Comparison

Fission Meter and Neutron Detection Using Poisson Distribution Comparison PDF Author: Mark S. Rowland
Publisher:
ISBN:
Category : Neutron counters
Languages : en
Pages :

Book Description
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.

Fission Meter and Neutron Detection Using Poisson Distribution Comparison

Fission Meter and Neutron Detection Using Poisson Distribution Comparison PDF Author: Mark S. Rowland
Publisher:
ISBN:
Category : Neutron counters
Languages : en
Pages :

Book Description
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.

Fission Meter and Neutron Detection Using Poisson Distribution Comparison

Fission Meter and Neutron Detection Using Poisson Distribution Comparison PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
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.

Detecting Fission from Special Nuclear Material Sources

Detecting Fission from Special Nuclear Material Sources PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A neutron detector system 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. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

Science & Technology Review

Science & Technology Review PDF Author:
Publisher:
ISBN:
Category : Military research
Languages : en
Pages : 282

Book Description


Fission Meter

Fission Meter PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
A neutron detector system 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.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1298

Book Description


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Hazebrouck PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


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Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 304

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ISBN:
Category : Power resources
Languages : en
Pages : 1344

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U.S. Geological Survey Bulletin PDF Author:
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Category : Geology
Languages : en
Pages : 524

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