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Contact Name
Prof. Dr. Muhayatun Santoso
Contact Email
muha014@brin.go.id
Phone
+62 (21) 7560009
Journal Mail Official
atomindonesia@brin.go.id
Editorial Address
Directorate of Repository, Multimedia and Scientific Publishing National Research and Innovation Agency, Kawasan Sains dan Teknologi - BRIN, KST B.J. Habibie, Gedung 120 TMC, Jl. Raya Puspiptek Serpong,Tangerang Selatan 15314, Indonesia
Location
Kota bogor,
Jawa barat
INDONESIA
Atom Indonesia
ISSN : 01261568     EISSN : 23565322     DOI : -
Core Subject : Science,
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.
Articles 79 Documents
PHITS-Based Simulation of Dose Distributions and Secondary Particle Fluence from Light and Heavy Ions at Therapeutic Energies in a Water Phantom Dalumpines, C. G. M.; Peñonal, G. F. I.; Aringa, H. P.; Convicto, V. C.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1643

Abstract

Comprehensive dosimetric evaluation of light and heavy ions such as protons, alpha particles, carbon, and oxygen ions is essential for advancements in radiation therapy and space applications. This study employed the Particle and Heavy Ion Transport code System (PHITS) to simulate dose distributions and secondary particle fluence in a water phantom across a range of therapeutic ion energies. A 30 × 30 × 30 cm³ water phantom with 2.0 × 108 primary particles at a Source to Surface Distance (SSD) of 100 cm were irradiated using mono energetic axial source. This simulation study also evaluated particle fluence of secondary particles such as electrons, positrons, and neutrons. Results showed that positron fluence concentrates around the water phantom, dispersing more at higher energy, while neutron flux focuses along the source path. The PHITS generated Percent Depth Dose (PDD) curves illustrate varied dose deposition patterns for each ion at different energies. For the highest energy considered, the simulated Bragg peak positions deviated by not more than 4.55 % from the experimental data, with simulation uncertainties kept below 0.1 %, ensuring accurate dose analysis. Helium ions (alpha particles) exhibited favorable treatment characteristics such as lower entrance dose, minimal lateral scattering, and reduced fragmentation consistent with the experimental findings. Additionally, the spatial distributions of electrons, positrons, and neutrons show elevated concentrations near the water phantom, indicating potential benefits for enhancing treatment precision.
Comparison of Lung Cancer Lesion Detection Capability on Standard Dose and Low Dose Computed Tomography Capabilities: An In-House Phantom Study Hutami, A. K.; Raharja, H. D. R.; Lubis, L. E.; Soejoko, D. S.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1587

Abstract

The use of Low-Dose Computed Tomography (LDCT) protocols has garnered significant attention, particularly in detecting cancerous lesions in high-risk populations. However, the drawback of low-dose CT protocols results in image noise. Solutions introduced, such as the use of reconstruction techniques, tend to be time-inefficient, complex, and costly. This paper aims to explain the design and construction of an approach for evaluating the quality of lung cancer lesion imaging that is adequate and easily implementable. In this study, a custom-designed in-house phantom is required to simulate lung cancer lesions. The in-house phantom was constructed from organ or tissue-equivalent materials and equipped with various Hounsfield Unit values and lesion diameter sizes, which were determined based on data from 73 patients, consisting of both males and females, using contrast. Scans were performed on the phantom using standard-dose and low-dose protocol parameters. The results demonstrated that the low-dose protocol was able to detect small lesions at lower radiation levels. The contrast difference is quite good with a Signal Difference to Noise Ratio (SDNR) value ≥ 5. The image was optimum with a relatively high Figure of Merit (FOM). Additionally, Noise Power Spectrum (NPS) measurements provided accurate results within a specific range of spatial frequencies.
Preface Atom Indonesia Vol 51 No 3 indonesia, atom
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1875

Abstract

Characterization and Sorption Study of Cesium-137 by Bentonite from Santrijaya, Indonesia as an Engineering Barrier Material for Radioactive Waste Disposal Facilities Sriwahyuni, H.; Krisnandi, Y. K.; Basuki, T.; Setiawan, B.; Budianti, A.; Anggraini, Z.; Nurliati, G.; Pamungkas, N. S.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1628

Abstract

Engineered barrier materials, such as bentonite, play a critical role for the safety of radioactive waste disposal systems by limiting radionuclide migration. This study aims to evaluate the mineralogical, chemical, and morphological characteristics of natural bentonite from Santrijaya, Tasikmalaya, Indonesia, and to investigate its Cs-137 sorption behavior, focusing on its potential as a candidate for engineered barrier materials. X-Ray Diffraction (XRD) and X-Ray Fluorescence (XRF) analyses showed that the bentonite predominantly consists of montmorillonite, with silica contributing about 80 percent of its composition. The material shows a specific surface area of 121.89 m²/g and a cation exchange capacity of 43.23 meq/100g, supporting its suitability for radionuclide sorption. The sorption capacity at equilibrium (q_e) achieved at 536.67 mg-Cesium/g-bentonite after 10 days of contact time, with adsorption kinetics that follows the Pseudo-Second Order (PSO) model and the distribution coefficient (K_d) value of 5211 mL/g. The study shows the competitive effects of K+ and Na+ ions, with K+ ions showing a stronger competitiveness for Cs-137 binding sites than that of Na+, which could influence radionuclide retention. These findings highlight the high sorption efficiency and stability of Santrijaya bentonite, showing its potential as a barrier material for radioactive waste containment systems and suggest the necessity of considering competing ion interactions in the design of barrier materials.
Acknowledgement Atom Indonesia Vol 51 No 3 indonesia, atom
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1876

Abstract

The Effect of Loop Inclination on Natural Circulation Mass Flow Rate and Heat Removal Inside Rectangular Passive Cooling Loop Budiyanto, N. R.; Deendarlianto, D; Yuliaji, D.; Oktaviandi, R.; Raharjo, E. P. A.; Mariyadi, S. A.; Pamungkas, A. E.; Setiawan, P. H.; Budiman, A. A.; Juarsa, M.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1467

Abstract

The use of passive cooling systems as a reactor safety measure has become a key approach to preventing future incidents similar to the Fukushima Daiichi NPP accident. These systems operate based on natural circulation, a process driven by temperature differences and elevation between the heat source and heat sink. Key design factors, such as the inclination angle of the rectangular loop, significantly influence this circulation. This study aims to investigate the effects of different inclination angles of the rectangular loop and variations in the initial water temperature in the Water Heating Tank (WHT) on the flow rate and heat removal capability. The research was conducted experimentally using a natural circulation rectangular loop facility, FASSIP-04 Ver.0, which has an inner diameter of 26.64 mm, a rectangular loop height of 2280 mm, and a width of 780 mm. The experimental variations were achieved by adjusting the water temperature inside the WHT to 50°C, 70°C, and 90°C. Meanwhile, the inclination angle of the loop was set to 30°, 60°, and 90° mass flow rate and heat removal capability was influenced by both the loop inclination angle and the water temperature in the WHT. The highest values were observed at a 90° inclination angle and a set temperature of 90°C, with a mass flow rate of 0.0241 kg/s, and heat removal rates of qH = 0.791 kW, qC = 0.489 kW. The resulting buoyancy force was stronger under these conditions, leading to greater heat removal through natural circulation compared to free convection, thereby increasing both mass flow rate and heat removal efficiency.
Evaluation of Neutron Flux in Boron Neutron Capture Therapy for a 10-Year-Old Child with Head and Neck Rhabdomyosarcoma Using Monte Carlo Simulation Salim, F. M.; Hidayanto, E.; Setiabudi, W.; Arianto, F.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1708

Abstract

Head and neck rhabdomyosarcoma is among the most frequently encountered malignancies in children under the age of 10, necessitating effective treatment modalities with minimal toxicity. Boron Neutron Capture Therapy (BNCT) is recognized as a promising therapeutic alternative in radiotherapy owing to its ability to selectively target malignant cells. The aim of this study was to evaluate the neutron beam quality of a BNCT collimator in a simulation model for the treatment of head and neck rhabdomyosarcoma in a 10-year-old pediatric phantom, using the MCNP 6.2 Monte Carlo method. The simulation included tumor modeling incorporating Gross Tumor Volume (GTV), Clinical Target Volume (CTV), and Planning Target Volume (PTV) to assess neutron flux distribution. The results showed a thermal neutron flux of 5.22 × 10⁹ n cm⁻² s⁻¹, an epithermal neutron flux of 1.22 × 10¹⁰ n cm⁻² s⁻¹, and a fast neutron flux of 5.91 × 10⁷ n cm⁻² s⁻¹. Further analysis indicated that the produced epithermal flux exceeded the minimum standard recommended by the IAEA, and the highest flux was concentrated in the GTV region, suggesting effective tumor targeting. However, the thermal-to-epithermal neutron flux ratio (0.43) remained above the threshold value recommended by the IAEA (≤ 0.05). In conclusion, while the collimator design was capable of delivering a high-quality epithermal neutron beam that selectively targeted the tumor, further optimization of the filter components remains necessary to reduce unwanted thermal flux and enhance therapeutic safety and efficacy.
Cover Atom Indonesia Vol 51 No 3 indonesia, atom
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1874

Abstract

Measurement of Percentage Depth Dose using Fabricated Water Phantom Tank for 6 MV Photon Beam Alssnusi, A. M.; Abdulla, Y. A.; Hussein, N. A.; El-Tashani, F. H. A.
Atom Indonesia Vol 51, No 3 (2025): DECEMBER 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1524

Abstract

Radiotherapy phantoms are utilized to estimate radiation dose delivered to patients, and to improve the accuracy and measurement of radiation dosimetry. The aim of this research is to measure the percentage depth dose (PDD) using a locally designed and fabricated water phantom tank as a cost-effective alternative to the commercially available water phantom used for calibrating therapeutic radiation doses from a linear accelerator. Acrylic material was used to construct the 30 × 40 × 30 cm3 water tank, and tests were conducted on the fabricated phantom using the Elekta linear accelerator at the National Cancer Center Benghazi (NCCB). An IBA FC65-P ionization chamber was used to measure the dose at depths ranging from 0 to 16 cm in 1 cm intervals for 6 MV photon energy at 10 x 10 cm2 field size, and 100 cm source surface distance (SSD). The results indicated that the dose values obtained from the locally fabricated water phantom closely matched those from the commercially installed water phantom and were consistent with values reported in the literature.