研究目的
To determine the photon shielding features of 16XO–3Al2O3–6CuO–20Na2O–55P2O5 glass systems (where X=Sr, Ca, Mg and Ba mol%) by carrying out XCOM software for a wide range of photon energies between 0.015–10 MeV and compare the radiation shielding capability of the glasses under investigation in terms of mean free path with those of different concretes reported in the literature.
研究成果
The μ/ρ of 16XO–3Al2O3–6CuO–20Na2O–55P2O5 (where X=Sr, Ca, Mg and Ba mol%) glasses have been investigated using XCOM software and MCNPX code. The obtained μ/ρ results are in good agreement with each other. The data showed that the μ/ρ and Zeff of BaO-doped phosphate glass are higher than those of the other alkaline earth elements–doped glasses. The values of MFP of the glasses studied here are lower than RS253, RS253-G18 glasses, ordinary and hematite–serpentine concretes. Therefore, these glasses are better shielding materials than other available commercial glasses and concrete samples.
研究不足
The study focuses on the gamma ray shielding properties of specific glass compositions and compares them with commercial glasses and concrete samples. The limitations include the specific energy range (0.015-10 MeV) and the types of glass compositions studied.
1：Experimental Design and Method Selection:
The radiation shielding characteristics of various alkaline earth elements based phosphate glasses have been calculated using XCOM program and MCNPX code. The formula of the investigated alkaline earth elements based phosphate glasses is 16XO–3Al2O3–6CuO–20Na2O–55P2O5, where X represents the used alkaline earth elements (X = Ba, Sr, Mg, and Ca mol %). The densities of the glass samples were taken from Ref.[20].
2：0]. Sample Selection and Data Sources:
2. Sample Selection and Data Sources: The density and the weight fraction of elements in glass samples are listed in Table
3：List of Experimental Equipment and Materials:
Monte Carlo N-Particle Transport Code System-extended (MCNPX) was performed for the determination of μ/ρ for the selected glasses employing the Lambert-Beer law.
4：Experimental Procedures and Operational Workflow:
F4 tally detection field was placed on the same line with a distance 70 cm from point isotropic radiation source. The F4 tally was used to count the gamma rays inter the detector per MeV.cm
5：s-The studied glass material was located between the point isotropic radiation source and the F4 tally mesh (detection field) at a distance 50 cm from the source. Data Analysis Methods:
Each average photon flux has been recorded from MCNPX output file and has been ploted to obtain the linear attenuation coefficients considering the Beer-Lambert law. Finally, each obtained linear atteuation coefficients has been divided to glass density to obtain mass attenuation coefficients in different photon energies.
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