Flux measurements in the Oregon State TRIGA reactor

Graduate Thesis Or Dissertation

Public Deposited

Citeable URL: https://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/j67316421

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Attribute Name	Values
Creator	Upham, Gary Lamont
Abstract	Neutron flux and gamma-ray dose have been measured in the experimental facilities of the Oregon State TRIGA reactor. Thermal neutron flux measurements utilized foil activation techniques. The gamma-ray dose was measured with a thermoluminescent dosimetry system. The thermoluminescent material used was LiF. Fast neutron spectrum measurements were performed. The fast flux measurements utilized threshold detectors. The activation data from the various threshold detectors was analyzed using the Effective Threshold Method. Fast flux measurements were made only in the in-core and near-core experimental facilities (where a fission spectrum was assumed to exist).
Resource Type	Masters Thesis
Date Available	2014-04-09T21:48:55+00:00
Date Issued	1967-12-11
Degree Level	Master's
Degree Name	Master of Science (M.S.)
Degree Field	Mechanical and Industrial Engineering
Degree Grantor	Oregon State University
Commencement Year	1968
Advisor	Ringle, John C.
Academic Affiliation	Mechanical and Industrial Engineering
Non-Academic Affiliation	Oregon State University. Graduate School
Subject	Swimming pool reactors Matrices
Rights Statement	Copyright Not Evaluated
Publisher	Oregon State University
Peer Reviewed	No
Language	English [eng]
Digitization Specifications	File scanned at 300 ppi using Capture Perfect 3.0 on a Canon DR-9050C in PDF format. CVista PdfCompressor 5.0 was used for pdf compression and textual OCR.
Replaces	http://hdl.handle.net/1957/47213

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