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Atom Indonesia
Published by Badan Riset dan Inovasi Nasional
ISSN : 01261568     EISSN : 23565322     DOI : -
Core Subject : Science,
Energy Physics
Atom Indonesia is dedicated to publishing and disseminating the results of research and development in nuclear science and technology. The scope of this journal covers experimental and analytical research in nuclear science and technology. The topics include nuclear physics, reactor physics, radioactive waste, fuel element, radioisotopes, radiopharmacy, radiation, and neutron scattering, as well as their utilization in agriculture, industry, health, environment, energy, material science and technology, and related fields.
Arjuna Subject : Fisika dan Astronomi - Fisika Nuklir dan Molekuler, dan Ooptik
Articles 69 Documents
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Estimation of Organ Dose, Effective Dose, and Cancer Risk in Abdominal CT Scan Patients Putri, S. S.; Intifadhah, S. H.; Putri, E. R.
Atom Indonesia Vol 50, No 3 (2024): DECEMBER 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1502

Abstract

Computed 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.
Monte Carlo Methods to Simulate the Propagation of the Created Atomic/ Nuclear Particles from Underground Piezoelectric Rocks through the Fractures Before the Earthquakes Bahari, A.; Mohammadi, S.; Shakib, N. S.; Benam, M. R.; Sajjadi, Z.
Atom Indonesia VOL 50, NO 1 (2024): APRIL 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1311

Abstract

Until 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.
The Impact of Different Light-Reflecting Materials Compositions of (LaBr3:Ce) Scintillation Detector on Spent Nuclear Fuel Gamma Spectrum El-Tayebany, R. A.
Atom Indonesia Vol 50, No 3 (2024): DECEMBER 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1421

Abstract

The 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.
Evaluation of Tumor Control Probability and Normal Tissue Complication Probability of Breast Cancer Treatment Plan in Post Mastectomy Radiation Therapy Herwiningsih, S.; Yuana, F.; Latifah, R.; Hidayat, A.; Rahmahtullah, D. P.; Alviani, I.; Hentihu, F. K.
Atom Indonesia Vol 50, No 2 (2024): AUGUST 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1423

Abstract

Radiotherapy has been widely used to treat cancer, including breast cancer treatment, which can be given after patients undergo mastectomy procedures. This study aims to evaluate tumor control probability (TCP) and normal tissue complication probability (NTCP) of three-dimensional conformal radiation therapy (3DCRT) and intensity modulated radiation therapy (IMRT) treatment planning in post-mastectomy breast cancer radiation therapy. Twenty clinical breast cancer treatment plans delivered using 3DCRT were evaluated retrospectively. The IMRT plans were created for the same patients. The dose-volume histograms of each plan were extracted from the Treatment Planning System (TPS) computer which were then used to compute the TCP and NTCP for each plan. The TCP was calculated using the Poisson model and the NTCP was calculated using the Lyman-Kutcher-Burman (LKB) model. The NTCP was calculated for normal lung tissue, heart, esophagus, and spinal cord. The results show that the TCP of the 3DCRT and IMRT plans are not significantly different, with a value of above 99 %. The NTCP of the left lung is lower in the IMRT plans while the NTCP of the esophagus is lower in the 3DCRT plans. The NTCP for the heart, spinal cord, and right normal lung are zero in all plans.
Cover Atom Indonesia Vol 51 No 1 indonesia, atom
Atom Indonesia Vol 51, No 1 (2025): APRIL 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1659

Abstract

The Effect of I-131 Treatment on Complete Blood Count Sahutoglu, G.; Cetin, S. K.; Atilgan, H. I.
Atom Indonesia VOL 50, NO 1 (2024): APRIL 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1381

Abstract

Radioactive iodine-131 (RAI) treatment may cause suppression in the bone marrow. In this study, hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts will be compared before total thyroidectomy and 6 months after RAI treatment. 97 patients (76 females, 21 males) with a diagnosis of    well-differentiated thyroid cancer who had undergone total thyroidectomy and received 50-200 mCi RAI treatment were included in the study. Hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts of the patients in the last month before the treatment and in the sixth month after the treatment were compared retrospectively. When the whole patients were analyzed, hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts in pretreatment were statistically lower than after-treatment values. While hemoglobin levels of female patients were similar before and after treatment, lymphocyte, thrombocyte, and leukocyte counts were statistically lower before treatment. Hemoglobin levels, leukocyte,and thrombocyte counts were similar before and after treatment, while lymphocytes decreased significantly after RAI treatment. Thyroid cancer patients who received 50-200 mCi RAI treatment after total thyroidectomy, have bone marrow suppression but are still in normal mean value ranges. This mild bone marrow suppression is more prominent in female patients than in male patients.
Source Identification Performance of Plastic Scintillator Ranging from 100–1300 keV: Assessment Through Monte Carlo Code and Experimental Validation Putro, G. E.; Omar, M. R.; Kasmudin, K.; Nuri, H. L.; Pancoko, M.; Jamil, A.; Subhiyah, H.
Atom Indonesia Vol 51, No 1 (2025): APRIL 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1401

Abstract

Current plastic detectors need improvement in efficiency and accuracy, to enhance reliability. Simulation offers a cost-effective approach to accelerate detector development, yet its effectiveness relies on the reliability of the simulations used. Therefore, validating these simulations is crucial to ensure they accurately reflect actual scenarios and yield reliable results. This study employs the Monte Carlo approach to estimate the performance and efficiency of a plastic detector exposed to radiation sources within the 100–1300 keV energy range. The plastic detector (50 mm x 3 mm) was simulated using MCNP with Gaussian Energy Broadening (GEB) correction applied to capture detector response. Simulated data were then compared against experimental measurements to validate the model. This work aims to confirm that simulation results align with empirical data, ensuring theoretical models accurately represent physical phenomena. The study highlights both the limitations and strengths of simulation codes, leading to more efficient research through validated models. Notably, an 8.04 % deviation was observed at 662 keV for 137Cs, demonstrating a strong correlation between simulated and experimental results and confirming the model’s accuracy and reliability.
Ground-Based Gamma-Ray Spectrometer Application on Drone-Borne: Suitability and Height Attenuation Syaeful, H.; Muhammad, A. G.; Rachael, Y.; Pratiwi, F.; Rosianna, I.; Ngadenin, N; Indrastomo, F. D.; Ciputra, R. C.; Sukadana, I. G.; Adimedha, T. B.; Karunianto, A. J.
Atom Indonesia Vol 50, No 3 (2024): DECEMBER 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1468

Abstract

Rapid development in the use of unmanned aerial vehicles (UAVs) in many applications, such as topographic mapping, agricultural management, marine monitoring, and others, has also brought the radiometric mapping application to this drone-borne application. Before the application, several corrections are performed to the data, including stripping corrections obtained from calibration results and height attenuation corrections. This study aims to determine the effectiveness and the height attenuation of the ground-based spectrometer attached to the drone. The method is carried out to determine the optimal altitude and conduct direct testing in the field of a small detector of 0.1 l of RS-125 gamma-ray spectrometer using drone-borne radiometric applications. In ideal conditions without obstacles in the flying path, 15 m is considered the ideal height, proportional to the detector size. Based on the results of field measurements at a drone height of 24 m, the comparison of drone and ground data is acceptable for dose rate, thorium, and potassium concentration with Pearson correlation of 0.67, 0.49, and 0.45, respectively. The drone measurement result is less acceptable for uranium data, with a Pearson correlation of 0.05 to the ground measurement. In conclusion, the RS-125 gamma-ray spectrometer is generally suitable for drone-borne radiometric applications.
Non-Dimensional Number Analysis on Natural Circulation Flow Changes Inside Straight-Pipe Heat Exchanger of Water Cooling Tank in FASSIP-02 Test Loop Arista, E. P.; Deendarlianto, D; Al-amin, A. S.; Setiawan, P. H.; Gunawan, H. A.; Juarsa, M.
Atom Indonesia Vol 50, No 2 (2024): AUGUST 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1387

Abstract

The FASSIP-02 test loop is a large-scale experimental facility that investigates natural circulation flow rate phenomena to improve passive safety systems of nuclear reactors. Heat transfer in the piping system will result in pattern and magnitude of the natural circulation flow being formed, so it is essential to investigate the heat dissipation capabilities, which will later be applied in nuclear passive cooling systems. The heat transfer behavior of passive cooling systems in large-scale facilities can be quantified with non-dimensional numbers. This research analyzes heat transfer in a straight heat exchanger by comparing non-dimensional numbers based on the Dittus-Boetler and McAdams correlation with the correlation generated from experimental data. The analysis results show that the predicted McAdams correlation with the experimental correlation is higher than 83 %. Meanwhile, Dittus Boetler's correlation prediction with the experimental correlation is smaller than 71 %. The dominance of momentum diffusivity in the cooling process shows the characteristics of thermal behavior with the Prandtl number. In addition, all-natural circulation flow variations occur in a turbulent flow regime that increases with increasing water temperature in the heating tank.
Radon Concentration in Biological Samples of Smokers and Non-smokers Using Lexan Detector Alkufi, A. A.; Abojassim, A. A.; Oleiwi, M. H.
Atom Indonesia Vol 50, No 2 (2024): AUGUST 2024
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2024.1402

Abstract

This study was conducted in the Najaf Governorate, Iraq, to analyze radon concentration in biological samples from smokers and non-smokers. The samples, including blood serum, urine, hair, and nails, were used as biomarkers to determine the presence or absence of radon (222Rn). Using a natural exposure method, the nuclear track detector (Lexan, Belgium) was utilized to measure these radon concentrations in the samples. Seventy-five samples of blood serum, urine, hair, and nails were collected for smokers of healthy people and fifty samples for non-smokers of healthy people in five age groups. This study was based on age and smoking to compare the results and determine their effects on radon concentrations. The results show that the average values of radon concentrations (in Bq/m3) in blood serum, urine, hair, and nails for smokers were 54.7 ± 22.1, 62.9 ± 23.1, 34.7 ± 11.2, and 41.7 ± 15.2, respectively. Meanwhile, the average values of radon concentrations (in Bq/m3) in blood serum, urine, hair, and nails for non-smokers were 24.2 ± 6.0, 30.0 ± 6.3, 18.7 ± 5.2, and 21.6 ± 6.9 respectively. The results and comparisons indicate that radon concentrations depend on the variables on which this study was based (age and smoking). Smokers and non-smokers had different levels of radon in all biological samples. The P-value was

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