Characterization of Neutron Field in a Spherical Irradiation Facility

Tohamy, M.

doi:10.11648/j.ajmp.20150405.13

Cited by 4 publications

(2 citation statements)

References 7 publications

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“…During irradiation, the source was taken out of the housing to a distance of 50cm and fixed on a wooden table with dimensions of 50cm wide and 120cm length. The experimental arrangement of the irradiating system including the neutron irradiator, neutron house as well as the neutron source handling system is presented in figure 1 [20].…”

Section: Materials and Methods: 21 Description Of 241 Am-be Irradiamentioning

confidence: 99%

Characterization of 241am-Be Neutron Source Using Threshold Foil Activation Technique

Kotb

Tohamy

Solieman

et al. 2019

Al-Azhar Bulletin of Science

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The aim of the study is to characterize 241 Am-Be isotopic neutron source with 5 Ci activity and nominal neutron yield 1.1×10 7 n/s. The emitted neutrons were measured employing threshold multi-foil activation technique using the following reactionsAl(n,α). The threshold reactions were selected based on their half-lives, adequate threshold energy and crosssection. The reaction rate of each sample foil is measured by detecting the gamma ray spectra produced as a result of reaction products decay. A hyper pure germanium detector (HPGe) is used for gamma-ray spectrum measurements. The obtained spectra were analyzed using Genie2000 software and the associated system absolute efficiency was calculated using Efftran software. Obtained reaction rates were compared with available published data.

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Section: Materials and Methods: 21 Description Of 241 Am-be Irradiamentioning

confidence: 99%

Characterization of 241am-Be Neutron Source Using Threshold Foil Activation Technique

Kotb

Tohamy

Solieman

et al. 2019

Al-Azhar Bulletin of Science

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“…In the present work, the neutron irradiation facility designed and constructed previously in the shape of a dual hemisphere container was used [11]. One important feature of this irradiator is that it achieves neutron field symmetry with respect to the position of the neutron source and sample positions near the center of the sphere.…”

Section: Irradiation Setupmentioning

confidence: 99%

Multiscale time-bin analysis of delayed gamma-ray spectra of fission products

Elmaghraby¹,

Tohamy²,

Comsan³

2021

Phys. Scr.

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The present work provides an analysis scheme of delayed gamma-ray spectra based on multiscale time-bin measurements in order to draw conclusions on the association of observed gamma-lines to certain nuclides, especially following the fission process to serve nuclear safeguards and security. The provided time-bin analysis scheme focuses on estimating post-irradiation decays of fission products with interfering gamma-ray lines having energies within the resolution of the used gamma detector. Being a source of deviation, instead of the fixed values of cooling time before each measurement, pinning down the accurate time for each time-bin that should be assigned to each radionuclide in each measurement had been determined independently. This scheme had enabled multiscale of the time-bin analysis ranging from a minute to hours. Experimental measurements were carried out on a natural uranium dioxide sample irradiated in a mixed field of water moderated neutrons. A stable neutron flux from a 5 Ci Am-Be source was used. Results showed great potential for the use of identification and assessment of the contents. The multiscale time-bin analysis scheme was able to resolve the 74 keV gamma-band to obtain the cross-section for 238U(n,γ)239U reaction, the 884.09 keV gamma-line of 134I/ 134Te, the 306.8 keV gamma-line from 101Tc/101Mo, and the 658 keV gamma-line of 97Nb/97Zr. Time-bin analysis showed that 134I, 101Tc, and 97Nb are not, by themselves, primary fission products, but rather they are the daughters of their high-yield parent fission products (134Te, 101Mo, and 97Zr). In the article, the mathematics of the proposed multiscale time-bin analysis is thoroughly outlined.

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