Determination of thermal neutron flux by activation of a pure target with known cross section
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Authors
Kelly, John J., Jr.
Clements, Neal W.
Subjects
Advisors
Hawes, William W.
Date of Issue
1960
Date
1960
Publisher
Monterey, California: U.S. Naval Postgraduate School
Language
en_US
Abstract
The thermal neutron flux in a reactor may be determined by activation of a pure target of known cross section. Gold foils were irradiated in the core of the AGN=201 reactor and from the absolute disintegration rate the thermal flux at the core center was determined to be 5.31 x 10(6) neutrons per square centimeter per second, maximum, at a nominal power level of 100 milliwatts.
The previous determination of the thermal flux by the manufacturer using a comparison method and a polonium-beryllium neutron source gave a value of 4.5 x 10(6) neutrons per square centimeter per second at the same power level.
The writers wish to express their appreciation to Professor William W. Hawes of the U.S. Naval
Postgraduate School for his assistance and encouragement during this investigation.
Type
Thesis
Description
Series/Report No
Department
Physics
Organization
Naval Postgraduate School (U.S.)
Identifiers
NPS Report Number
Sponsors
Funder
Format
Citation
Distribution Statement
Approved for public release; distribution is unlimited.
Rights
This publication is a work of the U.S. Government as defined in Title 17, United States Code, Section 101. Copyright protection is not available for this work in the United States.