Neutron Flux Measurements of the Triga Mark F Reactor PDF Download
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Author: JOHN H. MCNEILLY
Publisher:
ISBN:
Category :
Languages : en
Pages : 1
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Book Description
The neutron environment of the Triga Mark F Reactor was determined by using the neutron threshold detector system. A total of 107 measurements was made resulting in 562 separate neutron flux determinations. This analysis contains the results of the measurements and a description of the experimental procedure.
Author: JOHN H. MCNEILLY
Publisher:
ISBN:
Category :
Languages : en
Pages : 1
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Book Description
The neutron environment of the Triga Mark F Reactor was determined by using the neutron threshold detector system. A total of 107 measurements was made resulting in 562 separate neutron flux determinations. This analysis contains the results of the measurements and a description of the experimental procedure.
Author: K. C. Humpherys
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 22
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Neutron flux and spectra measurements were made in the void tank irradiation chamber of the TRIGA Mark-F reactor in support of radiation effects studies in that facility. Threshold foils were used for the measurements. Measurements were made with three lead-shielding thicknesses; zero, 3, and 4 inches between the reactor core shroud and the points of measurements. (auth).
Author: Gary Don Bouchey
Publisher:
ISBN:
Category :
Languages : en
Pages : 194
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Author: Kenneth Edward Habiger
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 172
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Author: G. Berwanger
Publisher:
ISBN:
Category :
Languages : en
Pages : 16
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Author: Ah Auu Gui
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 23
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Author: Gary Lamont Upham
Publisher:
ISBN:
Category : Matrices
Languages : en
Pages : 210
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Book Description
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).
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 104
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Author: Harold Davis Oak
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 192
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