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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 92 Documents
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Development of Burnup Fraction Calibration Curve for the Silicide Fuel Equilibrium Core of the RSG-GAS Reactor Pinem, S.; Sulistyo, F. Y.; Liem, P. H.; Hakim, A. A.; Luthfi, W.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1655

Abstract

The reactivity value of the RSG-GAS research reactor fuel with different burnup levels has been measured. The primary objective of this study is to establish the burnup calibration curve using the equilibrium core reactivity method of the RSG-GAS reactor. The reactivity value of each fuel element was measured at the same position within the reactor core to ensure that the measured burnup corresponds to the experimental core. The reactivity value of each fuel element was then extrapolated with the known burnup of the fuel element. The total control rod worth measurement was compared with Monte Carlo Serpent2 code calculations. The experimental fuel reactivity results were compared with the calculation results, showing a maximum discrepancy of -4.88%. Based on the reactivity measurement and calculation results, a fuel burnup calibration curve was successfully developed, which can be used to determine the burnup fraction of the RSG-GAS reactor.
Image Quality Assessment of Hybrid Statistical Iterative Reconstruction (H/SIR) in Comparison to Filtered Back Projection (FBP) Arjah, H.; Osman, N. D.; ALMasri, H.; Anam, C.; Aziz, M. E.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1528

Abstract

Hybrid Statistical Iterative Reconstruction (H/SIR) is a method for Computed Tomography (CT) image reconstruction that provides optimal diagnostic images while reducing radiation doses compared to the standard protocol using Filtered Back Projection (FBP). This work aims to assess the image quality metrics; Signal to Noise Ratio (SNR) and Contrast-to-Noise Ratio (CNR) of Low-Dose Computed Tomography (LDCT) examination with different vendors H/SIR algorithms. Three CT scanners from different manufacturers (Philips, GE, and Siemens) were used in this work. A total of 218 clinical images were analysed. The SNR and CNR of LDCT+H/SIR images were compared with standard protocol combined with FBP. The quantitative assessments were achieved by IndoQCT software. Results showed that H/SIR preserved image quality while radiation dose was minimized.
Probabilistic Model of Liquefaction in Serpong and Its Impact on Nuclear Installation Safety Haifani, A. M.; Prakoso, W.; Setiadipura, T.; Suntoko, H.; Muhammad, A. G.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1676

Abstract

This study delivers the first full probabilistic liquefaction hazard assessment specifically for an Indonesian nuclear power station (NPP) site, filling a major gap in current geotechnical risk evaluation techniques for nuclear infrastructure. We want to assess liquefaction risk under seismic loading in the Serpong region, a potential site for future NPP development, by integrating seismic hazard data and geotechnical site characteristics. The technique includes Probabilistic Seismic Hazard Analysis (PSHA), Ground Motion Prediction Equations (GMPEs), disaggregation curves, and soil characteristics extracted from 18 boreholes, such as SPT-N values, fines content, and groundwater level changes. Liquefaction triggering is assessed using Cyclic Stress Ratio (CSR), Cyclic Resistance Ratio (CRR), and associated factors (MSF, Rd), followed by probabilistic validation. Over a 50-year exposure period, the total liquefaction probability ranges from 0.5676 to 0.594, with the maximum vulnerability seen in water-saturated sandy layers at depths of 1-6 meters. These findings emphasize localized seismic susceptibility and have direct implications for risk-informed NPP foundation design and regulatory safety evaluations. Furthermore, the findings can be integrated into Probabilistic Safety Assessment (PSA) frameworks to help with quantitative risk indicators like Core Damage Frequency (CDF) and Large Early Release Frequency (LERF). This study provides a reproducible methodology for assessing liquefaction at nuclear plants in other seismically active regions.
Comparative Assessment of Radioactive Contamination in APR 1400 Reactor During SBO and TMI Accidents Ghaderinia, F.; Rahgoshay, M.; Jafari, J.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1558

Abstract

An alternative approach to estimate the tissue phantom ratio (TPR) at depths of 20 cm and 10 cm (TPR₂₀,₁₀) under non-reference conditions is required to address situations where a 10 × 10 cm² field size is not achievable on a specific linear accelerator (LINAC) during a beam quality test. This study aims to estimate the TPR20,10 under non-reference conditions using a geometric sequence approach, and to compare it with the TPR₂₀,₁₀ under non-reference conditions estimated using the Sauer method, the Palmas method, a linear fit approach, as well as with the TPR₂₀,₁₀ under reference conditions calculated using the TRS-398 protocol. The first step in this study was measuring the percentage depth dose (PDD), D20cm, and D10cm with field size variations from 4 × 4 cm² to 10 × 10 cm² for both 6 MV and 10 MV X-ray beams. The PDD were used to estimate the TPR₂₀,₁₀ using a geometric sequence approach, the Sauer method, the Palmans method, and a linear fit approach, and to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The D20 cm and D10 cm were also used to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach were 0.683 ± 0.004 and 0.742 ± 0.005, respectively. The level of precision that could be reached by the geometric sequence approach is potentially equivalent to the TRS-398 protocol, the Sauer method, the Palmans method, and the linear fit approach. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence method did not show a significant difference compared with the TPR₂₀,₁₀ calculated using the TRS-398 protocol. However, the TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach showed a significant difference compared with those TPR₂₀,₁₀ estimated using the Sauer method and the Palmans method.
Evaluation of ALON for Proton Shielding of Low Earth Orbit (LEO) Satellite Solar Arrays Firat, C.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1724

Abstract

This study evaluates the proton radiation shielding efficacy of various materials, with a focus on ALON, for satellite solar arrays in LEO across the 0.1-200 MeV energy range using SRIM/TRIM simulations. Key metrics, ion penetration, vacancies per ion, range, displacements per atom, non-ionizing energy loss, Bragg curves, and transmission, were analyzed for aluminum, SiO2, polyimide, ALON, and Ta2O5/Al2O3 at thicknesses from 0.01 mm to 4 mm. ALON demonstrates moderate stopping power and damage resistance, with penetration exceeding 20 µm and 100 µm at 0.5 MeV and 5 MeV, respectively, and 2000 µm and 4000 µm providing protection up to 50 MeV and 100 MeV, while maintaining high optical clarity (>80%) for photovoltaic (PV) applications. Thinner layers mitigate high-energy proton damage but are vulnerable to low-energy (
Estimating TPR₂₀,₁₀ Under Non-Reference Conditions Using a Geometric Sequence Approach Rizaldi, F. A.; Herwiningsih, S.; Widodo, C. S.; Hentihu, F. K.; Anto, A. K.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1564

Abstract

An alternative approach to estimate the Tissue Phantom Ratio (TPR) at depths of 20 cm and 10 cm (TPR₂₀,₁₀) under non-reference conditions is required to address situations where a 10 × 10 cm² field size is not achievable on a specific Linear Accelerator (LINAC) during a beam quality test. This study aims to estimate the TPR20,10 under non-reference conditions using a geometric sequence approach, and to compare it with the TPR₂₀,₁₀ under non-reference conditions estimated using the Sauer method, the Palmas method, a linear fit approach, as well as with the TPR₂₀,₁₀ under reference conditions calculated using the TRS-398 protocol. The first step in this study was measuring the percentage depth dose (PDD), D20cm, and D10cm with field size variations from 4 × 4 cm² to 10 × 10 cm² for both 6 MV and 10 MV X-ray beams. The PDD were used to estimate the TPR₂₀,₁₀ using a geometric sequence approach, the Sauer method, the Palmans method, and a linear fit approach, and to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The D20cm and D10cm were also used to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach were 0.683 ± 0.004 and 0.742 ± 0.005, respectively. The level of precision that could be reached by the geometric sequence approach is potentially equivalent to the TRS-398 protocol, the Sauer method, the Palmans method, and the linear fit approach. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence method did not show a significant difference compared with the TPR₂₀,₁₀ calculated using the TRS-398 protocol. However, the TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach showed a significant difference compared with those TPR₂₀,₁₀ estimated using the Sauer method and the Palmans method.
Monte Carlo Simulation of Pediatric Chest Radiography: Validation of the Irradose Through Comparison with MCNP Qassimi, O.; Kabach, O.; Messous, M. Y.; Tahiri, N.; Arianto, F.; El Bounagui, O.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1763

Abstract

Radiological examinations are essential for medical diagnostics, but accurate estimation of dose deposition is crucial for patient safety, particularly in pediatric patients. This study employs Monte Carlo simulations with the MCNP code and a newly developed custom program, Irradose, to analyze photon dose deposition in a cylindrical phantom representing the thorax of a 10-year-old child. Two tissue-equivalent compositions were modeled: water and a more realistic HCNO-based soft tissue mixture. Depth-dose distributions obtained with Irradose were compared to MCNP results. Both codes predicted a maximum dose at 2 cm depth, followed by exponential fall-off, with deviations remaining below 5% across the depth range. These results validate Irradose as a reliable and computationally efficient tool for pediatric chest dosimetry in phantom studies. While limited to simplified geometries, this work demonstrates the potential of Irradose for use in preliminary dose assessments and as a complement to established Monte Carlo codes.
The Role of Neutron Absorbers in Soliton Wave Creation Using Heavy Water as a Diffusive Medium Shakeri, A.; Abbasi, K.; Hosseinimotlagh, S. N.; Zarei, M. A.; Rezaei, V. R.; Bayat, J.; Pour, A. G.; Vanaie, H. R.; Rasati, E.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1465

Abstract

One of the simplest nuclear fission reactor designs is the soliton reactor. In these reactors, neutrons reduce the toxicity of fissile materials in a manner that allows new vital areas appear successively. Therefore, the spatial dependence of the neutron flux, specific power density, and associated particle density exhibit wave phenomena of solitons and emerge from the solution of nonlinear partial differential equations, preserving their shape during propagation. The velocity of the burnup Soliton Wave (SW) is related to the density of the initial Nuclear Fuel (NF) in each Neutron Absorber (NA) in the medium. These nonlinear waves can be described by equations describing the atomic flux and density in terms of time and space in the medium. The soliton wave can also be observed in advanced nuclear power systems. Burnup SWs in a propagation medium can be analyzed using the spatial coordinates and position of the NA in a propagation region. The aim of this work is to investigate the burnup SW characteristics by selecting various isotopic neutron absorbers in the slab reactor core. Our computational findings show that the SW burning rate is affected by increasing the diffusion coefficient. However, both the diffusion length and the Length of Transient (LOT) increase with increasing the diffusion coefficient. Interestingly, the ratio of LOT to diffusion length remains constant. Furthermore, while increasing the diffusion coefficient leads to a higher Transient of Time (TOT), the ratio between TOT and characteristic time remains constant.
Acknowledgement Atom Indonesia Vol 52 No 1 Indonesia, Atom
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1957

Abstract

Isolation and Selection of Radiation Resistant Fungi from Mamuju High Natural Radiation Soil for Uranium and Thorium Bioremediation Robifahmi, N.; Laksmana, R. I.; Pratama, A. A.; Kusuma, A. T.; Tjiptosumirat, T.; Tuasikal, B. J.; Nugraha, E. D.; Rijal, M. S.; Febrian, V. A.; Yusup, M.; Futy, W.; Mujiyanto, A.; Sugoro, I.
Atom Indonesia Vol 52, No 1 (2026): APRIL 2026
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1590

Abstract

Microorganisms from high natural radiation environments hold potential as bioremediation agents for radioactive waste. In this study, isolation and selection of fungi from Mamuju high natural radiation soil was done for radioactive bioremediation. The methods included fungal isolation from soil samples, radiosensitivity tests, sensitivity tests to uranium and thorium, and absorption tests under gamma radiation (100 Gy hour-1). Results revealed three fungal isolates with high growth ratios and resistance to gamma radiation: Talaromyces flavus (A3), Gongronella butleri (A4), and Aspergillus sp. (F1). Isolates A3 and A4 survived up to 2 kGy, while F1 endured up to 8 kGy. At 24 hours, A3 absorbed uranium at 96% with a biomass of 0.73 g and thorium at 84% with 0.98 g biomass. A4 achieved the highest uranium absorption of 97% (biomass 4.11 g) and thorium absorption of 100% (biomass 0.74 g). F1 demonstrated 96% uranium absorption (biomass 1.29 g) and 87% thorium absorption (biomass 2.17 g). These isolates exhibited significant potential for bioremediation of uranium and thorium-contaminated environments, showing unique adaptations to high radiation conditions and effective radioactive metal uptake.

Page 9 of 10 | Total Record : 92

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