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Characterization of the neutron flux gradients in typical irradiation channels of a TRIGA Mark II reactor

Characterization of the neutron flux gradients in typical irradiation channels of a TRIGA Mark II... The neutron distribution in a defined volume (gradient) for different matrices (air, water, cellulose, biological material and silicon dioxide) in two typical irradiation channels (pneumatic tube (PT) and IC40-channel in the carousel facility) in the TRIGA Mark II reactor at the Jožef Stefan Institute (IJS) was studied. Our experiment was based on inserting Fe wires (flux monitors) into the chosen matrices. The wires were cut into small pieces after irradiation and the induced activities of 59 Fe measured. The results showed that for the studied geometry the average spatial thermal neutron flux inhomogeneities (for five studied matrices) are about 2.3% in the PT-channel and about 2.9% in the IC40-channel. http://www.deepdyve.com/assets/images/DeepDyve-Logo-lg.png Journal of Radioanalytical and Nuclear Chemistry Springer Journals

Characterization of the neutron flux gradients in typical irradiation channels of a TRIGA Mark II reactor

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References (1)

Publisher
Springer Journals
Copyright
Copyright © 2003 by Kluwer Academic Publishers/Akadémiai Kiadó
Subject
Chemistry; Inorganic Chemistry; Physical Chemistry; Diagnostic Radiology; Nuclear Physics, Heavy Ions, Hadrons
ISSN
0236-5731
eISSN
1588-2780
DOI
10.1023/A:1025484313986
Publisher site
See Article on Publisher Site

Abstract

The neutron distribution in a defined volume (gradient) for different matrices (air, water, cellulose, biological material and silicon dioxide) in two typical irradiation channels (pneumatic tube (PT) and IC40-channel in the carousel facility) in the TRIGA Mark II reactor at the Jožef Stefan Institute (IJS) was studied. Our experiment was based on inserting Fe wires (flux monitors) into the chosen matrices. The wires were cut into small pieces after irradiation and the induced activities of 59 Fe measured. The results showed that for the studied geometry the average spatial thermal neutron flux inhomogeneities (for five studied matrices) are about 2.3% in the PT-channel and about 2.9% in the IC40-channel.

Journal

Journal of Radioanalytical and Nuclear ChemistrySpringer Journals

Published: Sep 1, 2003

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