SU-E-I-100: Feasibility Study of Gamma-Ray Medical Radiography

2012 ◽  
Vol 39 (6Part5) ◽  
pp. 3648-3648
Author(s):  
A Alyassin ◽  
H Maqsoud ◽  
A Mashat ◽  
A Al-Mohr ◽  
S Abdulwajid
2013 ◽  
Vol 72 ◽  
pp. 16-29 ◽  
Author(s):  
Abdalmajeid M. Alyassin ◽  
Hamza A. Maqsoud ◽  
Ahmad M. Mashat ◽  
Al-Sayed Al-Mohr ◽  
Subhan Abdulwajid

2013 ◽  
Vol 470 ◽  
pp. 012001 ◽  
Author(s):  
A Miceli ◽  
G Festa ◽  
R Senesi ◽  
G Gorini ◽  
C Andreani

2020 ◽  
Vol 225 ◽  
pp. 09001
Author(s):  
Adrien Sari ◽  
Sara Garti ◽  
Frédéric Lainé ◽  
Frédérick Carrel ◽  
Jonathan Dumazert ◽  
...  

In the frame of a partnership between CEA and VINCI, various measurement techniques are applied to soil analysis and tested in different laboratories located at CEA Saclay (France). This paper deals with two nuclear measurement techniques assessed in this project. More specifically, this paper presents the feasibility study carried out for two non-destructive active methods: photon activation and neutron activation. First, some atomic nuclides are activated either by photons or neutrons. Secondly, gamma-rays of specific energies are emitted by activated nuclides and gamma-ray spectrometry enables to identify these activated nuclides. Calibration of the full measurement system with reference samples would enable to quantify the mass of activated nuclides. Irradiations performed for photon activation measurements were conducted using a linear electron accelerator (linac) as the latter enables to generate high-energy photons by Bremsstrahlung thanks to its conversion target. Furthermore, irradiations performed for neutron activation measurements were also conducted with a linac. Indeed, photons may be converted to neutrons by photonuclear reactions using a secondary target. In the frame of this project, experiments were carried out at the SAPHIR platform (CEA Saclay) with a Linatron-M9 VARIAN linac. The electron energy was either 6 or 9 MeV. For neutron activation measurements, a secondary target made of heavy water has been used as neutron source and a polyethylene cell enabled to thermalize neutrons and increase the number of reactions of interest. In this paper, we present the different experimental setups and the measurement protocols established for this feasibility study. We show experimental results obtained with raw material samples coming from three construction sites.


2020 ◽  
Vol 135 (9) ◽  
Author(s):  
Gabriele Zorloni ◽  
Paolo Tancioni ◽  
Marco Caresana

Abstract Orphan radioactive sources inadvertently melted in steel plants are a health and economical hazard. Thus, regulation authorities impose strict control measurements to be performed at these plants. However, a recent series of incidents related to the melting of $${}^{241}\hbox {Am}$$ 241 Am sources demonstrated the inadequacy of even state of the art systems in revealing this low-energy gamma ray emitter up to activities of the order of hundreds GBq. However, $${}^{241}\hbox {Am}$$ 241 Am sources are characterized by a weak neutron emission which can be detected by proper monitor systems. This work provides a feasibility study of a shielding-independent neutron-sensitive portal monitor system to be installed in steel plants. Measurements were performed both with a certified $${}^{241}\hbox {Am}$$ 241 Am shielded source and at the weighing area of a steel plant, to assess both the detector performance and the practical feasibility of the system implementation in work-place fields. A risk evaluation analysis demonstrated that with the current control systems $${}^{241}\hbox {Am}$$ 241 Am sources up to 185 GBq could pass undetected with a potential exposure for workers equal to 1.7 mSv, consistent with recent accidents reports. The proposed technique could reveal $${}^{241}\hbox {Am}$$ 241 Am activities down to 2 GBq, decreasing the worker exposure down to 24 $$\upmu \hbox {Sv}$$ μ Sv , without interfering with the standard plant operations.


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