Diagnostic and therapeutic radioisotopes in nuclear medicine: Determination of gamma-ray transmission factors and safety competencies of high-dense and transparent glassy shields

Abstract

We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete. Gamma-ray transmission factors of newly designed glass shields are determined using a variety of diagnostic, therapeutic, and research radioisotopes, including 67Ga, 57Co, 111In, 201Tl, 99mTc, 51Cr, 131I, 58Co, 137Cs, 133Ba, and 60Co. A general-purpose Monte Carlo code MCNPX (version 2.7.0) is used to determine the attenuation parameters of different material thicknesses. Next, the findings are compared using a standard concrete shielding material. The results indicate that adding more CdO to the glass composition improves the overall gamma-ray attenuation properties. As a result, among the heavy and transparent glasses developed, the C40 sample containing 40% CdO exhibited the best gamma-ray absorption properties against all radioisotopes. Furthermore, the gamma-ray absorption characteristics of this created high-density glass were shown to be better to those of a standard and heavy concrete sample. It can be concluded that the newly developed CdO-rich and transparent glass sample may be used in medical radiation fields where the radioisotopes examined are used in daily clinical and research applications.

Advances in the novel and green-assisted techniques for extraction of bioactive compounds from millets: A comprehensive review

“…Electron beam irradiation utilizes a stream of high-energy electrons to irradiate the sample. Similarly, gamma rays emitted by radioisotopes like 60 Co or 137 Cs also possess strong penetration capabilities [ 211 ]. The radiation after penetrating materials can effectively disrupt the cellular structures, promote the decomposition of chemical bonds, and result in the release of targeted compounds.…”

Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study

“…Simulation studies were carried out using Lenovo-P620 ® workstation and the number of tracks was defined as 10 8 (NPS) in each simulation phase. Other technical details about the design and critical information about the input code can be obtained from our previous studies [ 33 , 34 ] .

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A closer look at the efficiency calibration of LaBr3(Ce) and NaI(Tl) scintillation detectors using MCNPX for various types of nuclear investigations

“…Monte Carlo simulations have been used efficiently in radiation protection [ 13 , 14 , 15 , 16 ], materials research [ 17 , 18 , 19 , 20 ], detector design [ 21 , 22 , 23 ], and medical applications [ 24 ]. In this work, two different 2 × 2 inch NaI(Tl) and LaBr3(Ce) scintillation detectors were modeled in terms of their full energy peak efficiency measurements and comparisons.…”