Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source

Didi, Abdessamad; Dadouch, Ahmed; Jaï, Otman; Tajmouati, Jaouad; Bekkouri, Hassane El

doi:10.1016/j.net.2017.02.002

Cited by 24 publications

(3 citation statements)

References 8 publications

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“…The 239 PuBe source has varying isotopic compositions depending on the source origin (Bagi et al, 2013). The total Pu content and its isotopes can be determined from the combination of alpha activities of Pu isotopes and its isotopic composition, which can be measured using various methods (Bagi et al, 2016;Abdessamad et al, 2017). However, the neutron source strength of 239 PuBe tends to vary with time due to the buildup of 241 Am from the decay of 241 Pu impurities in the source (Vega-Carrillo et al, 2012).…”

Section: Introductionmentioning

confidence: 99%

Radiological Characterization of the Philippine Research Reactor-1 Legacy Neutron Sources via Monte Carlo Simulation

Palangao,

Asuncion-Astronomo,

Tare

et al. 2022

MJST

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Three legacy neutron sources (LNS), one 239PuBe and two 252Cf, are currently stored in the Philippine Research Reactor-1 (PRR-1) facility. These LNS have been kept in the storage tank for the irradiated fuel in the PRR-1 facility for three decades. However, there is limited information available on these sources. Thus, in this paper, the dose rates associated with the irradiated fuel and the three LNS were calculated using Monte Carlo simulations. The dose distribution for the three LNS in a 200-L concrete-filled stainless steel container was also calculated. Results showed that the storage tank has provided adequate shielding against neutrons from the three LNS and the neutron doses are negligible compared with the gamma dose from the irradiated fuel. Simulation results demonstrated that the container has given sufficient radiation shielding for handling LNS. The results of this study will serve as a basis for developing procedures for safe handling, storage, transfer, disposal and use of LNS upon commissioning of the PRR-1 Subcritical Assembly for Training, Education, and Research (SATER). Moreover, this offers a reference for updating and improving the radiation protection measures in the PRR-1 facility.

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Section: Introductionmentioning

confidence: 99%

Radiological Characterization of the Philippine Research Reactor-1 Legacy Neutron Sources via Monte Carlo Simulation

Palangao,

Asuncion-Astronomo,

Tare

et al. 2022

MJST

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“…Despite the widespread use of radioisotopes in the world, the production of these is available only in developed countries. Although, the production of radioisotopes includes a nuclear reactor [1][2][3][4][5], a source of alpha-beryllium [6][7][8] and an accelerator [9]. In these recent years, global demand for molybdenum radioisotopes has increased significantly, with 90% of these was producted by five old reactors located in Canada, Belgium, the Netherlands, South Africa and France.…”

Section: Introductionmentioning

confidence: 99%

System and process of thermal neutron flux producing by means of an accelerator base electron of 18 MeV

Didi

Dadouch

Bekkour

et al. 2018

Eurasian j. phys. funct. mater.

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Neutrons are produced in accelerators by irradiating heavy targets with an electron or proton beam. Produced neutrons are of high energy. The purpose of our work is optimization the neutron flux by MCNP-6 code for production the thermal neutron flux using a moderator and for convertation the fast neutron flux into a thermal neutron flux. In this article, we are interested in a thermal neutron flux due it is useful for method of neutron activation analysis. In conventional sources, the moderator is usually a large volume of water or paraffin around the source. Initially, fast neutrons have energy above 1 MeV, and then slow down to energies below 1 eV.

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“…In the contest to best production of the radiation by Linac, many studies are done to improve its use. For increasing the radiotherapy efficiency, some works are carried out on the isotopes production for brachytherapy [3]. Others however are carried out on the beam filtration system quality for external photon radiotherapy [4,5] and the removing flattening filter from Linac head configuration to improve its technology [6,7].…”

Section: Introductionmentioning

confidence: 99%

New approach to evaluate the exit dose quality for high radioprotection and radiotherapy efficiency

Bencheikh¹,

Maghnouj²,

Tajmouati³

et al. 2018

Nucl. Phys. At. Energy

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For safety and radioprotection reasons in radiotherapy treatment, the exit dose is evaluated with irradiation field size and photon beam energy. The objective of this study is to introduce an empirical law for predicting the delivered dose at the other side of patient while radiotherapy treatment of cancer. In this study, the exit dose is the delivered dose out of the phantom on beam central axis. The measurements of percentage depth dose were done as a function of irradiation field size with an uncertainty of 2 % as recommended by IAEA protocols for two photon beam energies 6 and 18 MV. For high radioprotection quality inside radiotherapy department, an empirical law is elaborated with a reliability of 97 %. Thereafter, it consists a basic law that should be used theoretically to know the delivered dose variation with field size at the exit dose point for knowing the behavior of dose outside of radiotherapy treatment region. The medical physicists and physicians should take this law in radiotherapy treatment of the cancer.

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Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source

Cited by 24 publications

References 8 publications

Radiological Characterization of the Philippine Research Reactor-1 Legacy Neutron Sources via Monte Carlo Simulation

Radiological Characterization of the Philippine Research Reactor-1 Legacy Neutron Sources via Monte Carlo Simulation

System and process of thermal neutron flux producing by means of an accelerator base electron of 18 MeV

New approach to evaluate the exit dose quality for high radioprotection and radiotherapy efficiency

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