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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 4 Documents
 1 
Search results for , issue "Article In Press" : 4 Documents clear
Application of Sub-Miniature Fission Chamber Neutron Detector for Neutron Flux Measurement at the RSG-GAS Reactor: Foil Activation Benchmarking Gusman, R.; Agung, A.; Subekti, R. M.; Iswahyudi, F. N.; Susanti, F.; Pinem, S.
Atom Indonesia Article In Press
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2026.1768

Abstract

Accurate neutron flux measurement is essential for reactor characterization and utilization. At the RSG-GAS reactor, previous flux measurements relied on the foil activation method. While this method provides high accuracy, it lacks real-time capability due to its requirement for irradiation, post-irradiation cooling, and subsequent gamma spectroscopy for activity assessment. Direct online measurements of thermal neutron flux in the RSG-GAS reactor irradiation positions were performed using a Sub-Miniature Fission Chamber (SMFC) detector, where the flux was determined from the detector's output current proportional to fission events. This approach offers a viable alternative to the conventional foil activation technique by eliminating its time-consuming process and multiple uncertainty sources. After applying a correction factor obtained from gold foil activation reference measurements and the combined measurement uncertainty was quantified as ± 4.0%, results showed an axial flux distribution peaking at 200 mm height from the bottom of the core with maximum values of 4.997 x 1012 ± 0.199 x 1012 n/cm².s at central iradiation position (CIP E7), 6.212 x 1012 ± 0.248 x 1012 n/cm².s at iradiation position (IP B6), and 2.096 x 1012 ± 0.083x1012 n/cm².s at reflector element with plug (BS+ A2) under 200 kW operation. Radial mapping at 600 mm height from the bottom of the core revealed a maximum flux of 1.230 x 1012 ± 0.049 x 1012 n/cm².s at IP (G7). These results demonstrate that the Sub-Miniature Fission Chamber (SMFC) enables real-time neutron flux monitoring and provides a viable alternative to the conventional foil activation technique.
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 Article In Press
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 in Comparison to Filtered Back Projection (FBP) Arjah, Hamza; Osman, Noor Diyana; ALMasri, Hussein; Anam, Choirul; Aziz, Mohd Ezane
Atom Indonesia Article In Press
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 brain CT (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 is 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 show that H/SIR preserves image quality while radiation dose is 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 Article In Press
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.

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