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Calculation of neutron fluxes and radiation doses for neutron irradiator 226Ra-Be using the MCNP5 code
Source
Issue
Vol. 10, Issue 1 (30 Apr. 2017), pp.1-10, 10 p.
Publisher
Yarmouk University Deanship of Research and Graduate Studies
Publication Date
2017-04-30
Country of Publication
Jordan
No. of Pages
10
Main Subjects
Abstract EN
The irradiator 226Ra-Be unit available at the Physics Department of the Sciences Faculty, Damascus University, was simulated by using the MCNP code.
Calculations of neutron fluxes and radiation doses were carried out.
Simulation results showed that neutron fluxes, in the energy ranges: thermal (10-9-10-6 MeV), fast (0.11-12.0 MeV) and medium (10-5-10-1 MeV), had approximately the same magnitudes in some channels (See text for the definition of these channels), where the flux percent was about (thermal 70.0%, fast 18.0 % and medium 12.0%).
On the other hand, the flux percent in one particular channel was about (thermal 40.0%, fast 39.0% and medium 21.0%) and in another one (thermal %60.0, fast %26.0 and medium %14.0) with the presence of a plate of Cadmium whose thickness is 2 mm.
Absorbed radiation doses, in two channels, were calculated by using MCNP5 code and then compared with those measured experimentally by using thermoluminescent dosimeters (TLD).
A satisfactory agreement between calculated and measured results was found.
The relative differences were about 3.8% and 7.2% in these two channels, respectively.
American Psychological Association (APA)
Taani, A.& Nahili, M.& Bitar, A.. 2017. Calculation of neutron fluxes and radiation doses for neutron irradiator 226Ra-Be using the MCNP5 code. Jordan Journal of Physics،Vol. 10, no. 1, pp.1-10.
https://search.emarefa.net/detail/BIM-845477
Modern Language Association (MLA)
Taani, A.…[et al.]. Calculation of neutron fluxes and radiation doses for neutron irradiator 226Ra-Be using the MCNP5 code. Jordan Journal of Physics Vol. 10, no. 1 (Apr. 2017), pp.1-10.
https://search.emarefa.net/detail/BIM-845477
American Medical Association (AMA)
Taani, A.& Nahili, M.& Bitar, A.. Calculation of neutron fluxes and radiation doses for neutron irradiator 226Ra-Be using the MCNP5 code. Jordan Journal of Physics. 2017. Vol. 10, no. 1, pp.1-10.
https://search.emarefa.net/detail/BIM-845477
Data Type
Journal Articles
Language
English
Record ID
BIM-845477