APPLICATION OF A PORTABLE AM-241-BE NEUTRON SOURCE FOR THE TRACE ANALYSIS OF URANIUM IN DIFFERENT MATRICES

Authors
OTHMAN I RAJA G ALHUSHARI M IYER RH
Citation
I. Othman et al., APPLICATION OF A PORTABLE AM-241-BE NEUTRON SOURCE FOR THE TRACE ANALYSIS OF URANIUM IN DIFFERENT MATRICES, Nuclear geophysics, 7(3), 1993, pp. 449-454
Citations number
NO
Categorie Soggetti
Geosciences, Interdisciplinary","Metallurgy & Mining","Nuclear Sciences & Tecnology
Journal title
Nuclear geophysics → ACNP
ISSN journal
09698086
Volume
7
Issue
3
Year of publication
1993
Pages
449 - 454
Database
ISI
SICI code
0969-8086(1993)7:3<449:AOAPAN>2.0.ZU;2-7
Abstract
The thermal neutron flux distribution from a 5 Ci, Am-241-Be neutron s ource, thermalized by a cylindrical paraffin moderator of 41 cm diam. and 60 cm height has been measured using the U-235 (n, f) reaction and the fission track detection technique using ''Lexan''. The portable n eutron source has been used to measure uranium at the microgram level. The possibility of using this neutron source for measuring uranium at trace levels in different matrices (environmental and geological) by the fission track detection method is demonstrated.