Atom Indonesia (E-Journal)
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Radiation Dose and Image Quality of Bladder Cancer Patients Analysis on Abdominal CT-Scan Examinations
No full textThe bladder is a subperitoneal, hollow muscular organ that acts as areservoir for urine and located in the lower abdomen. Bladder cancer is one of health issues that can affect many people each year. Bladder cancer ranks as the 10th most common cancer worldwide. Early management includes cancer screening using abdominal CT-Scan. The objective of this study was to analyze the radiation dose received by patients and the image quality of patients underwent abdominal CT scans based on the Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values obtained. Data analysis management, specifically using quantitative analysis techniques, involved observing 20 bladder cancer patients with a total of 2,653 images. The IndoseCT software was used for analyzing the radiation dose to patients, while the IndoQCT software was used for analyzing image quality in CT-Abdomen examinations based on Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values. The results showed that the radiation dose received by patients during CT-Abdomen examinations was higher than the dose output by the device. The maximum dose output by the device (CTDIvol) was 50.10 mGy, and the minimum was 6.70 mGy, while the maximum dose received by patients (SSDE) was 53.34 mGy, and the minimum was 9.34 mGy. The image quality results for CT-Abdomen examinations based on SNR and CNR values indicated that the image quality obtained was adequate for diagnostic purposes
Heavy Metal Waste Using Ch/AgNPs Synthesized by Gamma Radiolysis: Preliminary Study
No full textEnvironmental issues had always been a problem for all countries in the world. Within a certain threshold, heavy metal waste in water and air must be considered. Various methods and instruments could be used for analysis of heavy metal waste levels. However, quick and accurate method needs to be upgraded in order to improve the efficiency of analysis. Ag nanoparticle is an alternative that could be used to detect the presence of heavy metal waste. Ag nanoparticles can be synthesized through reduction reaction with reductant agents from chemicals, biological compounds, and gamma irradiation. This research used qualilative analysis, utilizing chitosan stabilizer for Ag nanoparticles with gamma irradiation reductant in various doses, such as 7.5, 15, and 20 kGy. The results showed that AgNPs/chitosan was formed in the peak absorption range of 390-500 nm with optimum gamma irradiation dose of 15 kGy. In addition, AgNPs/chitosan has good sensitivity to detect Cr and Hg metals and was not sensitive to Cu and Pb metals
Atmospheric Plasma-Assisted Preparation of Graphene Oxide from Biomass: Characterization and Elemental Analysis
No full textGraphene oxide (GO) was successfully synthesized using the atmospheric plasma process with biomass precursors, including coconut fronds, palm fronds, and rambutan stems, within a five-minute processing time. Plasma technology converts near-waste materials into valuable resources with potential for various applications. Graphene oxide, in particular, exhibits high mechanical strength, excellent electrical conductivity, good biocompatibility, and a large surface area, making it a highly versatile material. Raman spectroscopy was used to analyze the formation of synthesized graphene. The presence of organic and inorganic elements in graphene oxide was characterized using a scanning electron microscope equipped with energy-dispersive X-ray spectroscopy (SEM-EDS) and neutron activation analysis (NAA). SEM-EDS analysis revealed that the C:O ratio in plasma-derived graphene oxide exceeded 80 % in each sample. NAA identified 22 inorganic elements, which are naturally present in biomass. Understanding the elemental composition of plasma-synthesized graphene oxide is essential for evaluating its potential applications and identifying necessary purification steps. The oxygen content in the synthesized material, which primarily originates from the inherent properties of biomass, can be regulated by optimizing plasma parameters. Using biomass precursors makes plasma-synthesized graphene oxide an economically viable option for large-scale production
A Multicenter Study of IMRT Dosimetry Audit Testing Using C-shape Phantom
No full textIntensity Modulation Radiation Therapy (IMRT) is a complex radiotherapy technique, so independent verification or dosimetry audits must be performed to ensure that accurate dosing is delivered to patients. This study conducted a multicenter audit using a dosimetry audit method developed from the IAEA dosimetry audit for IMRT/VMAT. The phantom in this study is made of acrylic material with two insert structures: planning target volume (PTV) and organ at risk (OAR). Phantom was scanned with a CT simulator at each hospital, and dose distribution was simulated with a PTV prescription dose of 4 Gy/2 fraction (D95 % = 95 %, D2 % < 107 %, and Dmax < 110 %) and a maximum OAR dose of 2.8 Gy. Dose evaluation in this study used TLD-rod for point dose and Gafchromic Film EBT3 for 2D dose distribution. Gamma evaluation was performed for film dose distribution with 3 %/3 mm and 3 %/2 mm criteria. The IMRT dosimetry audit using a C-shape phantom was tested in seven linacs (dynamic and static MLC) from six centers in Jakarta. The TLD results for PTV and OAR point dose show that all 14 IMRT plans meet deviation tolerance within ± 5 %. The film EBT3 evaluation identified that almost all plans pass the minimum 95 % gamma passing rate for 3 %/3 mm criteria and the minimum of 90 % for 3 %/2 mm. Three plans from three centers were also compared to the Gayatri (2022) study data from the same centers. Both results showed that all plans pass the action level ≥ 90 % for both 3 %/2 mm and 3 %/3 mm. Our audit dosimetry study approach employs a small and compact C-shaped phantom and dosimetry, facilitating easier distribution for remote audits. This study could serve as a starting point for remote audits leading to broader multicenter research in Indonesia
Investigation of Tissue Components Impacts on Dose Enhancement Factor Using Monte Carlo Code
No full textDespite the progress of science in cancer treatments and radiotherapy improvements, there are still several side effects that occur during tumors treatment, particularly on healthy tissues surrounded tumors. Newer treatment methods are being explored lately, one of which is the use of nanoparticles, wherein the tumor is injected with gold nanoparticles. Its aim is to enhance tumor sensitivity to radiation and reduce radiation damage to healthy tissues. Tissue type may play an effective role in enhancing the dose being received under the use of nanoparticles. This study aims to find the effect of different tissue components on dose enhancement factor through MCNP6 and GATE simulations, as well as to accurately compare the simulation results of these two code packages for dose enhancement factors. A 125I brachytherapy source was simulated in phantoms for five tissues or materials (adipose tissue, breast tissue, soft tissue, water, and brain tissue). MCNP6 simulation code was validated by comparing its results with a previous study by Cho et al. Gold nanoparticles were injected as a mixture at a concentration of 7 mg/g into tissues inside a tumor. MCNP6 and GATE simulation results were compared. It was estimated from MCNP simulations that the highest radiation dose enhancement of 2.34 occurs in adipose tissue while lowest dose enhancement of 1.69 is in brain. In comparison, from GATE results, the estimates were that the highest value of dose enhancement factor also occurred in adipose tissue at 2.01, and the lowest value in brain at 1.48. The comparison between two codes suggest that they are compatible with the percentage difference in all tissues being less than 15 %. This study confirms that both MCNP6 and GATE codes could calculate DEF for different tissues under irradiation from a low-energy source
Radiological and Toxicity Hazards Estimate of Drinking Water in Al-Diwaniyah, Iraq
No full textIn this work, analyses of 222Rn concentration and effective 226Ra content in all available types of drinking water in Al-Diwaniyah city, Iraq, were achieved by using CR-39 detectors technique. The annual effective dose from 222Rn and 226Ra distribution by three age groups were calculated. Radiological and chemical hazards were also calculated in drinking water samples. Drinking water samples were taken from tap water, water treatment plants, reverse osmosis water, and bottled drinking water in Al-Diwaniyah city. Effective 226Ra content level in some tap water samples were bigger than recommended value WHO for drinking water (1 Bq/L), but far below maximum acceptable limit of 370 Bq/L according to IAEA. All other values of 222Rn concentration and effective 226Ra content, annual effective dose, cancer morbidity and mortality hazards, and the lifetime average daily dose caused by consumption 226Ra in drinking water were less than recommended limits. Therefore, 222Rn concentration and effective 226Ra content in drinking water obtained in this work cannot give rise to radiological and chemical threats to population. However, for greater safety, we advise not to use tap water directly as drinking water. This work will provide important new data on the possible health effects of drinking water in Al-Diwaniya city
Thermal Properties of Alpha Decay in Magnetic Field Medium
No full textAn analytical study of alpha decay in the presence of an imposed magnetic field and some of its thermodynamic properties was considered. The study used the JWKB method to determine the allowed energy eigenvalues and mean lifetime of the decay process with the understanding that the two expressions will enable us to determine the impact of the imposed magnetic field and the select thermodynamic properties. The study reveals that the solution admits a discrete energy spectrum and the radial wave function decreases exponentially as the imposed magnetic field decreases and is square integrable with zero point energy and the presence of the imposed magnetic field, enhanced the decay rate of the particles as well as partially removed the degeneracy of the process. The four thermodynamic properties considered as shown in the graphs plotted also laid credence by enhancing the entropy and the Helmholtz free energy, while the internal energy and the specific heat at constant volume of the decay process, depreciated as the magnetic field increases as well as attainment of saturation point. Generally, the shape of the wave function plot confirmed the radioactive decay curve
Comparison of the Thermo-Hydraulic Response of MELCOR 1.8.6 and 2.1 for SBO Accident for APR 1400 Reactor
No full textAn analysis of thermohydraulic response during a station blackout (SBO) accident for the APR 1400 nuclear power plant is performed using MELCOR version 1.8.6. MELCOR 1.8.6 results for the SBO scenario are benchmarked with MELCOR 2.1. The simulation of the SBO accident with MELCOR 2.1 was done by the APR 1400 reactor designer company (KEPCO). This research consists of two parts; the first part is related to the results of MELCOR 1.8.6, and the thermo-hydraulic analysis of MELCOR1.8.6 has been done. Analysis of thermohydraulic response is focused on investigating thermohydraulic parameters, such as core pressure, fuel clad temperature, water mass flow rate in the core, time of fuel clad failure, time of lower head failure, and time of containment failure. In the second part, the results of MELCOR version 1.86 have been benchmarked with the results of MELCOR 2.1. The results of the analysis of containment pressure changes in version 1.8.6 showed that the effect of pressure increase in containment is mostly due to the increase in carbon dioxide mass, but in version 2.1, the increase in pressure is more due to water vapor