Atom Indonesia (E-Journal)
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Estimation of Organ Dose, Effective Dose, and Cancer Risk in Abdominal CT Scan Patients
No full textComputed tomography scan (CT scan) is a modality that is used to diagnose diseases inside the human body. In the scanning process, the patient will receive radiation from the CT scanner, so that it is necessary to calculate the amount of radiation dose. The purpose of this study was to determine the organ dose, effective dose, and cancer risk received by abdominal examination patients. Data taken from the results of abdominal examination patients at Radiology Installation of A.W. Sjahranie Regional Hospital Samarinda using 16-slice CT scan modality GE BRIVO type D3161T. The data collected included 150 patients, both female and male, with ages ranging from 15 to 79 years. Dosimetry parameters taken from CT scan results are the exposure factor (kV, mAs), scan length, computed tomography dosimetry indeks volume (CTDIvol), and dose length product (DLP) of the patient. CTDIvol and DLP of the patient are used to calculate the organ dose, effective dose, and cancer risk values of abdominal CT scan patients. Then the effective dose value received by the abdominal CT scan examination patient is compared with the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) standard based on the CTDIvol and DLP values of the patient, and also compared with the International Commission Radiological Protection (ICRP) standard. Based on the results of organ dose estimation calculations, the average value of the stomach is 0.82 mSv, the gonads are 0.54 mSv, and the bladder is 0.28 mSv. Meanwhile, the average value of effective dose received by abdominal examination patients is 5.28 mSv with an average cancer risk of 0.029 %. Based on the CTDIvol and DLP values of the patients, the 3rd quartile values of the patients were 8.25 mGy and 413.84 mGy.cm. This value is still below the value recommended by BAPETEN when viewed from the 2021 Diagnostic Reference Level (DRL) guidelines. The effective dose received by one patient exceeded the standard set by the ICRP. Meanwhile, the cancer risk received by patients is still in a low percentage
The Effect of Zinc Concentration on Bioaccumulation in Milkfish (Chanos chanos) Use of 65Zn as a Radioactive Tracer
No full textBioaccumulation studies of zinc (Zn) in milkfish (Chanos chanos) have been carried out in the laboratory using a 65Zn radiotracer. The research was conducted to determine the effect of Zn concentration on the ability of Chanos chanos to accumulate and release these contaminants. Zn absorption follows the single-compartment model, and experiments were carried out until stable conditions were achieved. The stages of research were biota collection, acclimatization, bioaccumulation, and elimination. Acclimatization was carried out for biota adaptation in the experimental environment. Bioaccumulation was carried out for 7 days by placing the biota in an aquarium filled with seawater added with 65Zn radiotracer contaminants. The elimination process involves the release of contaminants from the biota by placing them in contaminant-free seawater for 7 days. The results of the bioaccumulation experiment showed that the concentration factor (CF) ranged from 0.67 - 18.18 mLgr-1 at a concentration of ZnCl2 of 1.5 ppm, and the absorption constant (ku) 1.878 - 3.267d-1 and R2 was 0.0276. The release of contaminants in depuration experiments was highest at ZnCl2 2 ppm concentrations. The percentage of retention during depuration was between 14.61 - 79.91 %, the elimination constant (ke) was 8.681, and R2 was 0.7213
Monte Carlo Methods to Simulate the Propagation of the Created Atomic/ Nuclear Particles from Underground Piezoelectric Rocks through the Fractures Before the Earthquakes
No full textUntil now, many studies have been performed on particle radiations before or during earthquakes (EQs). Neutron, gamma, electron, proton, and ultra-low frequency (ULF) photons are among the particles, detected during EQs. In our previous study, with the help of piezoelectricity relationships and the elastic energy formula, the Monte Carlo N‐Particle eXtended (MCNPX) simulation code was applied to find the amount of created atomic/nuclear particles, the dominant interactions; and the energy of the particles for various sizes of quartz and granite blocks. In this study, using the MCNPX simulation code, we have estimated the flux of the particles (created from under-stressed granitic rocks) at different distances from the EQ hypocenter inside the fractures, filled with air, water, and CO2. It was found that inside a water-filled fracture, the particles do not show the flux far from the EQ hypocenter. However, inside the gases like air and CO2 with the normal condition density, different types of particles can have a flux far from the source (more than a kilometer) and they might reach themselves to the surface in the case that the EQ hypocenter is very shallow (0-5 km). However, for deep EQs, it seems that the most detected nuclear particles on the surface should pass via the vacuum-filled fractures and reach the surface. Moreover, it was concluded that the higher the density of the fracture’s filling fluid, the less distance that the particles can have a flux
Preliminary Study of Micronucleus Frequencies and Responses in Thyroid Cancer Patients After Treatment with 131I Therapy
No full textRadioiodine has become the most widely used to treat an overactive thyroid (hyperthyroidism) and thyroid cancer worldwide. The present research aimed to study the association between micronuclei (MN) frequencies, and follow-up responses after treating thyroid cancer patients with iodium-131(131I). The detection of the MNs assay was carried out by Giemsa staining from lymphocytes obtained from twenty-four thyroid cancer patients one week after receiving 131I treatment at Dharmais Cancer Center Hospital, Jakarta, Indonesia. Follow-up for clinical and laboratory responses grouped into good (stable) and bad (progressive, refractory, and dropout patients) responses, was observed one and six months after treatment. All patients received radioiodine with an activity dose of 30 - 200 μCi. The mean MN frequency in the good response group was 14.22, and that of bad response patients was 17.22. There was no statistically significant difference in MN frequency (p>0.05) between the two groups of patients after six months of treatment
The Impact of Different Light-Reflecting Materials Compositions of (LaBr3:Ce) Scintillation Detector on Spent Nuclear Fuel Gamma Spectrum
No full textThe Scintillation detectors are extensively employed in nuclear safeguards, nuclear security fields, radioactive material testing, and physics research. Light-reflecting materials of (LaBr3:Ce) scintillation detectors positively affect their ability to capture light. Our goal is to investigate the characteristics of various reflectors by MCNPX code. In this paper, high-activity fission products from the spent fuel, identified as the utilized radionuclides 152Eu, 154Eu, 134Cs, 137Cs, and 243Cm, have been used in the simulation. Also, short-lived fission products, and short-lived actinides (239U and 239Np), which have decay heat in the timeframe of severe accident analysis, have been included. The findings of this investigation are consistent with the discovery that LaBr3:Ce delivers superior resolution. Additionally, some closely spaced peaks in the spectra of numerous radioisotopes could be resolved by the LaBr3:Ce detector. With different energy lines, the spectral responses of the scintillators' various reflectors were evaluated
Characterizing Photon Beam Properties of a TrueBeam STx Linear Accelerator: An Evaluation of Geant4/GATE Monte Carlo Simulation Tool Performance
No full textPurpose: This study aims to investigate the characteristics of photon beams from TrueBeam STx, comparing flattening filter (FF) and flattening filter free (FFF) configurations between measurements and Monte Carlo simulation. Instruments and methods: The Geant4/GATE simulation toolkit was utilized to simulate percentage depth dose (PDD), off-axis distance profiles (profiles), dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry. Subsequently, these simulated results were compared with experimental measurements and evaluated using the gamma index method. Results: There was a good agreement between simulation and experimental measurement results in modeling the PDD and profile of photon beams. All gamma passing rate indices exceeded 97 %, 94 %, and 90 % with criteria of 3 % and 3 mm, 2 % and 2 mm, and 1 % and 1 mm, respectively. The calculated results of beam characteristics (dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry) were highly compatible with experimental measurements, with discrepancies less than 3 %, except for the surface dose of the 6MV FF photon beam, which had an error of 3.83 %. Conclusion: The Geant4/GATE simulation toolkit provided accurate results for simulating and investigating photon beam characteristics, aligning closely with experimental measurements
Radiation Dose Calculation Analysis During The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results
No full textDisused Sealed Radioactive Sources (DSRS) present significant risks of radiation exposure and environmental contamination during dismantling. Despite their sealed nature, DSRS can emit ionizing radiation, necessitating careful management to mitigate health risks. This article presents the MCNP simulation results of dosimetric operational quantities, namely Hp(3), Hp(10), and H(0.07), for hands and feet. This study focuses on a 60Co source, due to its high radiation energy levels and widespread use in various socioeconomic sectors. The assessment of radiation exposure levels enabled the improvement of occupational radiation protection measures related to critical areas and steps in the dismantling process. According to the obtained results with the 60Co source at its initial activity, and considering the maximum task duration, the dismantling process contributes to approximately 72.35 % of the daily dose limit of 80 µSv for worker category A, for the whole body. Therefore, these findings can contribute to a better understanding of radiation exposure risks and confirm compliance with regulatory requirements
Weighted CTDI Equation for 3D Rotational Angiography: A Monte Carlo Study
No full textThis study aims to verify the weighted Computed Tomography Dose Index (CTDIw) coefficients of 3D rotational angiography (3DRA) procedure using Monte Carlo simulation. The Monte Carlo simulation EGSnrc usercode was employed for 3D dose simulations of the rotational angiography procedure. A virtual phantom resembles the head CTDI phantom was constructed, with a diameter of 16 cm and a density resembling polymethyl methacrylate (1.13 g/cm3). A series of virtual phantoms consisting of 5 images with ionization chamber detectors at the center position, 12 o'clock, 9 o'clock, 6 o'clock, and 3 o'clock were acquired. Simulations were performed with photon sources of 70 and 109 kVp for 200-degree x-ray tube rotation. The field of view was divided into narrow, wide, and full beam with diameters of 1.7 cm; 4.9 cm; and 8.6 cm, respectively. The simulated doses at the ionization chamber were processed into weighting factor for weighted CTDI and compared with direct measurements. The dose ratio between peripheral and center positions for 360° CBCT and 200° 3DRA was 1:1 and 1:3 in this study. The weighting factors for 3DRA were determined as CTDIcenter = ¼ and CTDIperiphery = ¾. The measured average percentage difference of CTDIw between our weighted factor and conventional CTDIw was 1.75 % (-3.99 % to 6.08 %). The x-ray tube position of 3DRA impacted the accuracy of weighting factor of CTDIw, with implications for the proposed weighting factor (Wcenter = ¼ and Wperiphery = ¾) when using a 3DRA machine
Bibliometric Analysis of the Literature on Carbon Ion Therapy Using VOSviewer Software and Dimensions Database
No full textThis study aims to carry out a bibliometric assessment of the worldwide research literature and historical research results on carbon ion therapy for cancer treatment. To carry out this work, we used the VOSviewer software and the Dimensions database. The VOSviewer software tool examined 2,500 publications exported from the Dimensions database. The results show a notable upward trajectory in academic research on carbon ion therapy since 1994, with 2020 showing the highest volume of publications. “Biomedical and Clinical Sciences”, “Physical Sciences”, “Oncology and Carcinogenesis”, and “Medical and Biological Physics” are the most important research categories. “Physics in Medicine and Biology” and “Medical Physics” are the leading journals for research publications on carbon ion therapy. Scrutiny based on term occurrences demonstrates the shift in research interest towards carbon ion radiation therapy. The analysis of bibliographic couplings concerning different countries revealed that Japan is the most dynamic and prolific country based on the number of publications (659) and citations (13734), followed by Germany with 590 publications and 19679 citations. These analytical studies provide a thorough overview of academic publications dedicated to using carbon ions for tumor treatment. This data is anticipated to be highly valuable for researchers seeking to pinpoint the most recent developments and emerging trends in this field of research