Radioactive Sources Research Articles

Using a Monte Carlo simulation to analyze the ideal activity for a phosphorus-32 polymeric brachytherapy source for paraspinal tumors

A promising radioactive source for use in intracavitary brachytherapy is phosphorus-32. This source has been prominent as a minimally invasive treatment for craniopharyngiomas and in the treatment of metastatic bone diseases in general and has been developed at Nuclear and Energy Research Institute (IPEN). In this work, a Monte Carlo simulation was used to evaluate the ideal activity this source must have to deliver a 1 Gy/min dose rate. TOPAS was used to model the simulation, and its geometry was simulated with the source centered in the origin point, inserted into an isotropic volume of water of 17.42 cm3. The source has the decay properties of phosphorus-32. The total dose was calculated using volumetric scorers. The results were promising, showing that the initial activity must be 86.14 mCi or 2871 MBq to obtain the 1 Gy/min dose rate. With the initial activity measured in this work, it is possible to minimize the patient’s exposure to radiation, while ensuring the quality of the treatment.

Antimicrobial Sensitivity of Pseudomonas aeruginosa to Aztreonam, Amoxicillin, Erythromycin, Carbenicillin, Norfloxacin, Chloramphenicol, Gentamycin and Azithromycin after Exposure to Radiation Emitted from Radioactive Sources, Lasers and Exposure to Magn

Objective: The aim of this study to assess the sensitivity of P. aeruginosa for ATM, AML, E, CAR, NOR, CL, CN and AZM after exposure to radiation emitted from radioactive sources, Lasers and exposure to magnetized water. Study design: Cross-sectional in descriptive study design with case–control in analytical study design Backgrounds: P. aeruginosa gram negative bacteria occasion distinct kinds of contagion including epidermis, optics, ears, respiratory tract, urinary tract, intestines derived sepsis, soft tissues, skeleton and joint contagion. Radiation including ionizing and non-ionization depending on the energy of the radiated particles emitted Alpha, Beta and Gamma rays from different radioactive sources. Methodology: Study populations and bacterial deposition and identification of P. aeruginosa. Exposure P. aeruginosa to radiation at different times and doses. Antimicrobial susceptibility test for ATM, AML, E, CAR, NOR, CL, CN and AZM after exposure to radiation emitted from radioactive sources, Lasers and magnetized water. Results: After exposing P. aeruginosa to the Na23, CO60, Cs137 and Sr90 radioactive source without or without aluminum for (1,2,3) hr., the bacteria were examined for antibiotics and the results are high sensitivity to NOR, ATM, CAR. As well as, exposure to Nd: YAG laser in (10, 20) min. with exposure to magnetized water which show high sensitive to NOR and ATM antibiotics. Conclusions: The radioactive sources, Nd: YAG laser and magnetic water have a strong effect on bacteria and their sensitivity to antibiotics, so that their sensitivity rate increased very significantly compared to before exposure. The most effective antibiotics in killing bacteria after exposure are Aztreonam, Norfloxacin, Carbenicillin and Gentamycin (ATM, NOR, CAR and CN).

Multichannel SiPM test readout system for gamma ray measurements with monolithic inorganic CeBr3

Abstract Energy resolution and the detection efficiency for gamma quanta are fundamental properties in the construction of detectors for ionizing radiation. In this study, a SiPM-based photodetector coupled to a monolithic inorganic CeBr3 crystal is exposed to gamma rays in order to study the performance of the CeBr3 crystal. Measurements are made using three different radioactive sources - 137Cs, 22Na and 60Co. For each source, the measurements are made using a few different values for the Bias voltage of the SiPM. Furthermore, two CeBr3 crystals with different thicknesses are used in order to study how detector efficiency is affected by crystal dimensions. A preliminary analysis of the data is presented.

Annual Effective Dose due to Ingestion and Inhalation of 222Rn in Drinking Water of Daupe Village in Tafa Local Government Area of Niger State, Nigeria

Radon is one of the sources of nuclear contamination in water and the largest contributor of the total radiation received by the general public from natural radioactive sources. In this research, the concentrations of 222 Rn were investigated from six (6) wells (WW) and four (4) borehole (BW) water samples collected within Daupe village, Tafa Local Government area using Liquid Scintillation Counter (LSC).

Experimental investigation of radiation shielding competence of B2O3-Na2O-Al2O3-BaO-CaO glass system

Aiming to extend the scope of utilizing glass in radiation shielding, this work investigates the radiation interaction response of a borate-based glass system. Four borate-glass samples of different substituting concentrations of calcium oxide (70-x\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$70-x$$\\end{document})B2O3:10\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$10$$\\end{document} Na2O :5\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$:5$$\\end{document} Al2O3:15\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$:15$$\\end{document} BaO:x\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$x$$\\end{document} CaO were prepared. To assess the shielding performance of the prepared glass samples, a high-purity germanium detector and different radioactive sources (different energies) were used. Via the narrow beam method, the linear attenuation coefficients (LACs) were experimentally measured. So, the transmission factor (TF), the half-value layer (HVL), the tenth value layer (TVL), the mean free path (MFP), and the radiation protection efficiency (RPE) were calculated for all prepared samples. It was observed that the increase of the concentration of calcium oxide in the proposed borate-based glass samples leads to improve their performance in shielding against radiation. At low energy, the RPE of the samples is almost 100%. However, it was observed that as energy of the radiation source increases, the shielding performance of the samples will decrease. High energy dependence was found when calculating TF, HVL, TVL, and MFP. They were increased with the increase of the energy of the incident photons. At 0.662 MeV, the TF values are equal to 79.26, 79.00, 79.72, and 78.43% for BNABC-1, BNABC-2, BNABC-3, and BNABC-4 in the same oder, respectively. The application of the proposed composition of borate-based glass as a transparent shield against low-energy ionizing radiation was highlighted.

Determination of the type of radioactive nuclei and gamma spectrometry analysis for radioactive sources

Determining the type of radioactive nuclei is the second activity after the inventory of radioactive waste in Kosovo, their location and the number of radioactive sources. Before starting any type of radioactive waste action, it is necessary to determine the content of their activity, the type of radioisotope, physical and chemical form and the risks associated with their management. The realization of this is achieved as a combination of quality assurance processes, the inventory of the radioisotope and its activity that is present in the waste, the composition of the waste material and direct measurements. This serious activity was carried out entirely in the field and was undertaken due to the lack of source certification or any other indication of their classification and activity. The process of determining the type of radioactive nuclei helps to realize a more effective characterization of them as well as to determine the path of waste management. The probability that a gamma radiation detector interacts with it to produce a pulse represents the effectiveness of the detector.

Discussion about a new possible experiment for detection of resonance Mössbauer electron neutrinos

Up to date, resonant neutrino emission and absorption, although predicted more than half a century ago, has not been measured. We propose a new neutrino resonance experiment exploiting the isotope 55Fe. Experimental features such as the use of sources, detectors and experimental conditions are discussed in detail. For the resonant neutrino absorption cross-section in the range of 10−38 to 10−37 cm2, resonant Mössbauer neutrinos can be detected using high-activity commercially available radioactive sources in conjunction with a multi-detector system. Although the experiment has the same serious difficulties as other neutrino experiments, it offers unique opportunity in an effort to provide the first successful detection of resonant Mössbauer neutrinos. In the case of no signal, the proposed experiment will provide state-of-the art information and unprecedented limits on the cross-section parameters for resonant neutrino absorption.

Novel approach for emergency dosimetry: Investigations of screen protectors for smartphones by EPR spectroscopy

Screen protectors for smartphone are investigated in attempts for emergency dosimetry as for example in case of malicious attacks with radioactive sources or accidental overexposure. Electron Paramagnetic Resonance (EPR) measurements were carried out on six different types of screen protectors (SPs). The inter and intra batch variability of the EPR signals characteristics (sensitivity, stability, signal shape) were studied. Contrary to touch screen (De Angelis et al., 2015; Juniewicz et al., 2020), UVB exposure for SP is not a limiting confounding factor. All samples under irradiation exhibit same EPR signals. The nature of the radio-induced point defects was identified (HC1 and HC2) as well as their evolution according to dose. The linear dose response was studied in the 0–5 Gy dose range with a detection limit estimated of 750 mGy with a field deployable benchtop EPR spectrometer. Large variability of the dose response prevents presently from using universal calibration curve. Therefore, further work is needed to consider possible application for triage in the case of large-scale accidents scenarios.

Runaway electron dynamics in ITER disruptions with shattered pellet injections

This study systematically explores the parameter space of disruption mitigation through shattered pellet injection in ITER with a focus on runaway electron (RE) dynamics, using the disruption modeling tool Dream. The physics fidelity is considerably increased compared to previous studies, by e.g. using realistic magnetic geometry, resistive wall configuration, thermal quench onset criteria, as well as including additional effects, such as ion transport and enhanced RE transport during the thermal quench. The work aims to provide a fairly comprehensive coverage of experimentally feasible scenarios, considering plasmas representative of both non-activated and high-performance DT operation, different thermal quench onset criteria and transport levels, a wide range of hydrogen and neon quantities injected in one or two stages, and pellets with various characteristic shard sizes. Using a staggered injection scheme, with a pure hydrogen injection preceding a mixed hydrogen-neon injection, we find injection parameters leading to acceptable RE currents in all investigated discharges without activated runaway sources. Dividing the injection into two stages is found to significantly enhance the assimilation and minimize RE generation due to the hot-tail mechanism. However, while a staggered injection outperforms a single stage injection also in cases with radioactive RE sources, no cases with acceptable RE currents are found for a DT-plasma with a 15MA plasma current.

Determination of Natural Radioactivity Levels and Radiation Hazards from the Soil of Tin Mining in Kyerwa District, Tanzania

Gamma spectrometry was used to determine the activity concentrations of the natural radionuclides 226Ra, 232Th, and 40K in soil samples from the Tin mining in Kyerwa District, Tanzania. The study findings revealed that the mean activity concentrations of 226Ra, 232Th, and 40K were 90.68, 65.45, and 630.95 Bq/kg, respectively. These values were all greater than the average global activity concentrations for 226Ra, 232Th, and 40K which are 32 Bq/kg, 45 Bq/kg, and 420 Bq/kg, respectively. Assessments of the radiological risks associated with these naturally occurring radionuclides were done. In this case, the radium equivalent activity (Raeq), external hazard index (Hex), internal hazard index (Hin), and radioactivity level index (Iγ) were calculated. The results show that the mean values of Raeq, Hex, Hin, and Iγ were 230.6 Bq/kg, 0.628, 0.861, and 0.831, respectively. These results were below the global criteria levels for Raeq, Hex, Hin, and Iγ, which are 370 Bq/kg, 1, 1, and 2, respectively. Estimates for the absorbed dose rate in the air (DR), the annual effective dose equivalent (AEDE), and the annual gonadal equivalent dose (AGED) were also made. The findings revealed that the corresponding mean values for DR, AEDE, and AGED were 106.8 nGy/h, 1.07 mSv/y, and 744.4 μSvy-1. The mean values exceeded the global average value of 57 nGy/h for DR, 0.07 mSv/y for AEDE, and 2984 Sv/y for AGED. Therefore, Tin mining activities in the Kyerwa District could endanger the mining community from natural radioactive sources. In this study, therefore, we recommend performing a periodic inspection of the mining areas, monitoring the mining workers, and determining the level of activity and concentrations of different radionuclides in the mining area.

Radiation shielding properties of shotcrete containing different aggregates

In this study, the physical and mechanical properties of wet mix shotcrete produced using crushed stone aggregate (CS), ferrochrome slag aggregate (FS), and barite (B) aggregate have been investigated. Furthermore, the radiation shielding properties have been determined experimentally, theoretically, and through simulation. A control sample was produced using 50 % CS and 50 % FS. Subsequently, shotcrete groups were produced by substituting B aggregate at replacement rates of 25 %, 50 %, 75 %, and 100 % instead of FS. The mechanical properties such as density, ultrasonic pulse velocity (UPV), compressive strength, flexural strength, and splitting tensile strength of the produced spray concrete groups were investigated. Additionally, experimental radiation shielding measurements were conducted using a high-purity germanium (HPGe) detector system with emissions from four different radioactive sources (133Ba, 137Cs, 60Co, and 22Na) spanning nine different gamma energies ranging from 276.5 to 1332.5 keV. As a result of the experimental measurements, the linear attenuation coefficients (μ) of the shotcrete samples were obtained. A proportional increase in μ was determined with increasing barite content. Using the experimental mass attenuation coefficient (μ/ρ) results, half-value layer (HVL) and tenth-value layer (TVL) thicknesses, as well as mean free path (MFP) values, were calculated. An increasing B aggregate ratio did not have a significant effect on the μ/ρ value, while an increase was observed in the HVL, TVL, and MFP values. Moreover, the WinXCOM interface was employed for theoretical calculations, and the FLUKA Monte Carlo code was utilized for simulation calculations. The obtained data were compared with experimental results, revealing a good agreement between them. Based on the obtained data, it was concluded that increasing the B aggregate ratio resulted in improvement in mechanical properties compared to the control sample, and additionally, it was determined that B aggregate-added shotcrete is an effective gamma radiation shielding material.

Reconstruction method for gamma-ray coded-aperture imaging based on mask and anti-mask functions

Gamma-ray coded-aperture imaging technology plays an important role in nuclear security, decommissioning of nuclear facilities, and nuclear medicine diagnosis. However, under near-field imaging condition, artifacts in the reconstructed image can interfere with identifying the shape and position of the radioactive source. In this paper, a gamma-ray coded-aperture imaging method based on mask and anti-mask functions was proposed to suppress imaging artifacts and speed up the acquisition of low-noise reconstructed images. Through simulation, the effects of the number of iterations and the thickness of the coded-aperture collimator on the imaging quality were studied, and the range of the optimal correction factor in the method was determined. Imaging experiments were conducted using a compact coded-aperture gamma camera based on CdZnTe detector to verify the applicability of the optimal correction factor range. The limitations of the proposed method were analyzed through complex-shaped source imaging simulations and multi-source imaging experiments. This method has an insufficient suppression effect on random artifacts and requires further improvement in imaging irregular radioactive sources. However, it has good imaging performance for single-point source and multi-point sources, effectively reducing regular cross-shaped and stripe-like artifacts. In the non-uniform radioactive background, it can eliminate a part of artifacts, significantly improving imaging quality. Therefore, this method has potential applications in complex radioactive environments.

Heterojunction betavoltaic Si14C-Si energy converter

A potential opportunity to improve the integrated betavoltaic batteries and low-power cells performance is the radionuclide-activation method, which is an integrated combination of an injection source and an energy converter in the one material. Energy converters that contain an activated SiC thin film as the Si14C-Si barrier heterojunctions energy converter in betavoltaic cell are considered. The Si14C-Si heterojunction is positioned as by 14C beta source doped direct energy converting material two-in-one, for the device structure with an emitter of Si14C with optimized thickness is 0.4μm and the doping concentrations of N-SiC/p-Si are 15.7÷15.9×1017/16.2×1017÷∼1019cm−3. To ensure efficient operation of a betavoltaic element, the mathematical model determines: the short circuit current density is up to 900 nA cm−2, the open circuit voltage is up to 1.21 V, the fill factor is 0.9, the maximum output power density is up to 300 nW cm−2, the conversion efficiency is up to 16% and up to 0.5 V voltage per load in the experiment. The calculation and experimental verification results indicate that the Si14C-Si structure improved output performance of the nuclear cell by reducing the radioactive source self-absorption energy losses and due to better energy deposition distributions of inner injector. The results are valuable for optimizing the integrated betavoltaic elements production.

Rapid nuclide identification algorithm based on self-attention mechanism neural network

Nuclide identification technology plays a critical role in various fields such as nuclear energy, medicine, environmental monitoring, and defense. However, traditional nuclide identification algorithms face challenges, such as high computational complexity and long response time, when handling large-scale data. The adaptability and universality of these algorithms for different domains and tasks are also confronted with certain challenges. In recent years, numerous nuclide identification methods based on convolutional neural networks have been proposed, to some extent, addressing the issues present in traditional nuclide identification algorithms. Yet, in the context of unmanned nuclear emergencies, nuclear counterterrorism, and post-nuclear contamination processing, there is a widespread need for rapid nuclide identification methods suitable for deployment on edge computing devices. Therefore, this paper combines the advantages of self-attention mechanisms and convolutional neural networks to design a novel network architecture which can meet the aforementioned application requirements. We simulated and measured energy spectrum data for radioactive sources, including 241Am, 57Co, 60Co, 99mTc, 131I, 133Ba, 137Cs, 226Ra, 232Th, and 40K, as the training dataset. In experiments with a training set containing only individual radioactive source energy spectra, the model achieves 99.49% accuracy, with an average inference time of 0.14 ms per sample. It has 0.27 million parameters and 1.55 billion FLOPs. When the training set includes both individual and mixed radioactive source energy spectra, the model achieves 99.84% accuracy, with an average inference time of 0.25 ms per sample. It has 0.83 million parameters and 1.58 billion FLOPs.

Methodology for integrating MCNP6 Monte Carlo simulation into PLUNC for prostate brachytherapy planning

Brachytherapy is a well-established therapeutic technique for treating tumours involving the placement of radioactive encapsulated sources close to or in direct contact with a tumour. Considering this type of treatments, the purpose of this work is to incorporate Monte Carlo (MC) simulation into brachytherapy treatment planning. This approach allows for precise estimation of dose distribution in target organs as well as in Organs At Risk (OAR), due to the accuracy of the MC methods in describing dose deposition.To carry out this work, the medical image visualization and dose analysis tools provided by the open-source planner PlanUNC (PLUNC) were utilized. Additionally, a set of programs was developed which automatize the main steps of a treatment planning segmentation, from DICOM images, exporting geometries determining materials and seeds positions, creating an input file for the simulation code (MCNP6.2) and, finally, reading and visualization of the simulation results in the format of the used planning software. With this methodology, results of 3D dose distribution, isodoses curves, Dose-Volume Histograms (DVH), and absorbed dose in OAR were obtained. Thus, the integration of the MC simulation into PLUNC for brachytherapy treatments, has demonstrate its utility for this purpose, showing adaptability to different anatomical geometries and extensibility to various types of treatments.

The relationship between ceramic additives among structural, morphological, shielding, and stopping power features of BN/ZnFe metal matrix materials

Ionizing radiation has many negative effects on human health. These include eye and skin disorders and DNA damage inside cells. To eliminate or reduce these destructive effects of radiation, economical, low-corrosion, effective shielding materials with high absorption properties are needed. In this study, zinc-iron-based metal matrix composite materials with various proportions of boron nitride were produced on steel substrates. The structural and surface properties of the materials were examined with XRD and SEM images, respectively. These structures were irradiated with radioactive Am-241, Sr-90, Na-22, and Co-60 sources for their radiation shielding properties. Then, the absorption ratios in the samples were investigated according to the reinforced ceramic amounts in their content. In addition to the experiment, the stopping power and range values of the samples were calculated to check the reliability of the results. ZnFe alloys and composites are based on the dominant peaks of the heta (ƞ) phase of zinc. The amount of boron nitride added to the electrolyte significantly affected the crystal structure, while the incorporation of boron nitride into the zinc-iron matrix impressed the average grain size of the coating. The microstrain and dislocation densities of the film first decreased to 15 g/L and then increased depending on the ion diameter. The BN doping made the porous surface smooth, crack-free, and compact. It was found that the absorption rates for radiation increased as the amount of boron nitride in the samples increased. According to the rising amount of boron nitride, the absorption percentages are between 1.88 and 6.19% for alpha particles, 0.78–3.06% for electrons, 0.77–6.56% for positrons, and 0.61–6.34% for gamma photons. When the stopping power and range values were averaged, the amount of boron nitride increased directly and inversely with the stopping power and range values, respectively.

Design of electronic system for 2D hard X-ray spectrum camera on EAST

This paper presents the construction of a electronic system for two-dimensional hard X-ray spectroscopic imaging using CZT(Cadmium Zinc Telluride, CdZnTe) detector on EAST(Experimental Advanced Superconducting Tokamak), designed to measure the spatiotemporal distribution evolution of fast electrons in the energy range of 20 keV-700 keV. The system primarily consists of a two-dimensional array of CZT detector, an observation window, shielding components, front-end electronics system, and a data acquisition system. The two-dimensional array of detector is installed on the horizontal D window of EAST, with an observation range covering the plasma core region. The system achieves a temporal resolution of 2–16 ms and a spatial resolution of 10 cm. Data processing is carried out using FPGA-based (Field Programmable Gate Array) spectral recognition algorithms. Prior to the experiments on EAST, spectrum calibration is conducted using radioactive sources Eu152, Cs137, and Am251. In the 2023 EAST experiments, the system successfully measured the behavior of fast electrons generated under low hybrid discharge conditions, enabling spectrum measurements at different spatial locations within the plasma. Finally, the experimental results show that the system has a good performance.

Comparing 3D printing techniques (SLA vs. FDM) for their use in radionuclide metrology

This paper presents a comparative analysis, in which we evaluate the parameters of SLA and FDM printing technologies, for the production of radioactive standard sources in the SARPAGAN geometry, frequently encountered in radionuclide metrology. Aspects such as material compatibility, dimensional accuracy, radiation stability and the influence of 3D printing technology on the reliability of the final product will be addressed. Furthermore, the results obtained by gamma-ray spectrometry on a sample of 99mTc, using the standard SARPAGAN geometry, in comparison with the two 3D printed SARPAGAN geometries (SLA and FDM), were analyzed to evaluate how both the material and the technique printing of the geometry influences the results.

Impact of La2O3 incorporation on the structural, physical, mechanical properties and radiation shielding performance of basalt glasses

This study investigates the influence of La2O3 addition on the structural, physical, and radiation shielding properties of basalt-based glasses. Incorporating varying concentrations of La2O3 (0, 10, 20, 30 wt%) into basalt glasses, we aimed to evaluate the potential of La2O3 in enhancing the material's effectiveness against gamma radiation. Utilizing Ba-133 point radioactive source and Ultra Ge detector, we measured the attenuation parameters in different photon energies (81, 160, 223, 276, 302, 356, and 383 keV). The glasses exhibited an amorphous structure, as confirmed by XRD analysis, with density values ranging from 2.72 to 3.305 g/cm³, increasing with La2O3 content. The microstructural analysis indicated that La3+ ions predominantly integrate into the glass matrix, enhancing the structural integrity without forming separate phase regions. Our findings demonstrate a significant improvement in radiation protection parameters, including mass attenuation coefficients and half-value layers, with higher La2O3 concentrations. These outcomes were also supported by the data obtained for Zeff and EBF values of G1-G4 glasses. The mechanical properties of the glasses were also investigated with the Makishima-Mackenzie model and it was observed that the elastic moduli were also affected by the addition of La2O3. The enhancements observed with La2O3 additions suggest promising avenues for developing advanced shielding materials, combining the inherent advantages of basalt glasses with the high atomic weight and electron density of lanthanum compounds.

USE OF CATHODE RAY TUBE (CRT) COMPOSITE WASTE GLASS FOR NUCLEAR SHIELD TILES

This research is aimed at producing radiation shield tiles from cathode ray tube waste glass, borosilicate waste glassand soda lime silicate waste glass. The waste glasses were sourced for and crushed to powder. The powder wassieved through a 0.25 mm sieved with mesh number 60 and analysed using XRF spectrometer to ascertain theirchemical constituents. Twenty-one samples were generated using a 21-point triaxial blend of the three wasteglasses. The various samples were poured into moulds, fired in an electric furnace at 1000oC and soaked for anhour. Radiation shielding test using a radioactive source (cobalt 60) was carried out. The radiation shielding testsshows that sample 1 which comprises of 100% CRT had the highest radiation shielding ability with 0.178 cm-1linear attenuation coefficient and sample 21 which is made up of 100% soda lime silicate glass had the leastradiation shielding ability with 0.109 cm-1 linear attenuation coefficient.According to the 49th NCRP report,conventional tiles HVL for 60-Co gamma is 6.2 cm; whereas HVL for the RST in this work ranges between 3.8-6.3cm which shows that the RST is within the range of offering a good radiation protection. The results obtained in thisstudy showed that the radiation shielding tiles developed can be used as wall tiles in nuclear power facilities andmedical X-ray systems.