Atom Indonesia
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.
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<![CDATA[Source Identification Performance of Plastic Scintillator Ranging from 100–1300 keV: Assessment Through Monte Carlo Code and Experimental Validation ]]>
<![CDATA[Putro, G. E.]]>;
<![CDATA[Omar, M. R.]]>;
<![CDATA[Kasmudin, K.]]>;
<![CDATA[Nuri, H. L.]]>;
<![CDATA[Pancoko, M.]]>;
<![CDATA[Jamil, A.]]>;
<![CDATA[Subhiyah, H.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1401
<![CDATA[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.]]>
<![CDATA[Customization of Source Term into JRODOS Compatible XML File Format Using Visual Basic for Nuclear Accident Analysis ]]>
<![CDATA[Hassan, S. M. T.]]>;
<![CDATA[Khaer, M. A.]]>;
<![CDATA[Hoq, M. A.]]>;
<![CDATA[Chowdhury, M. T.]]>;
<![CDATA[Rahman, M. M.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1432
<![CDATA[A Visual Basic code was developed to generate an XML file in the RODOS format from the provided source term data in Microsoft Excel Spreadsheet. This XML file can be directly used in JRODOS (Java-based Real-time On-line Decision Support) platform. A simple source term model was used to check the applicability of the code. Finally, the code was successfully implemented to reproduce the JRODOS-formatted XML file for a detailed Fukushima Dai-ichi nuclear power plant accidental scenario. This code simplifies a vital analysis step, which would otherwise be very cumbersome, especially for a complex source term scenario involving many radionuclides, release intervals, and release heights of a nuclear accident.]]>
<![CDATA[Thermal Properties of Alpha Decay in Magnetic Field Medium ]]>
<![CDATA[Nwabuzor, P. O.]]>;
<![CDATA[Ngiangia, A. T.]]>;
<![CDATA[George, F. J.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1316
<![CDATA[An analytical study of alpha decay in the presence of an imposed magnetic field and some of its thermodynamic properties was considered. The study used the JWKB method to determine the allowed energy eigenvalues and mean lifetime of the decay process with the understanding that the two expressions will enable us to determine the impact of the imposed magnetic field and the select thermodynamic properties. The study reveals that the solution admits a discrete energy spectrum and the radial wave function decreases exponentially as the imposed magnetic field decreases and is square integrable with zero point energy and the presence of the imposed magnetic field, enhanced the decay rate of the particles as well as partially removed the degeneracy of the process. The four thermodynamic properties considered as shown in the graphs plotted also laid credence by enhancing the entropy and the Helmholtz free energy, while the internal energy and the specific heat at constant volume of the decay process, depreciated as the magnetic field increases as well as attainment of saturation point. Generally, the shape of the wave function plot confirmed the radioactive decay curve.]]>
<![CDATA[Radiation Dose and Image Quality of Bladder Cancer Patients Analysis on Abdominal CT-Scan Examinations ]]>
<![CDATA[Anthon, R.]]>;
<![CDATA[Intifadhah, S. H.]]>;
<![CDATA[Putri, E. R.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1526
<![CDATA[The bladder is a subperitoneal, hollow muscular organ that acts as areservoir for urine and located in the lower abdomen. Bladder cancer is one of health issues that can affect many people each year. Bladder cancer ranks as the 10th most common cancer worldwide. Early management includes cancer screening using abdominal CT-Scan. The objective of this study was to analyze the radiation dose received by patients and the image quality of patients underwent abdominal CT scans based on the Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values obtained. Data analysis management, specifically using quantitative analysis techniques, involved observing 20 bladder cancer patients with a total of 2,653 images. The IndoseCT software was used for analyzing the radiation dose to patients, while the IndoQCT software was used for analyzing image quality in CT-Abdomen examinations based on Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values. The results showed that the radiation dose received by patients during CT-Abdomen examinations was higher than the dose output by the device. The maximum dose output by the device (CTDIvol) was 50.10 mGy, and the minimum was 6.70 mGy, while the maximum dose received by patients (SSDE) was 53.34 mGy, and the minimum was 9.34 mGy. The image quality results for CT-Abdomen examinations based on SNR and CNR values indicated that the image quality obtained was adequate for diagnostic purposes.]]>
<![CDATA[Heavy Metal Waste Using Ch/AgNPs Synthesized by Gamma Radiolysis: Preliminary Study ]]>
<![CDATA[Ariyanti, D.]]>;
<![CDATA[Basuki, K. T.]]>;
<![CDATA[Megasari, K.]]>;
<![CDATA[Ismail, I]]>;
<![CDATA[Abimanyu, A.]]>;
<![CDATA[Hamadi, H.]]>;
<![CDATA[Rozana, K.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1181
<![CDATA[Environmental issues had always been a problem for all countries in the world. Within a certain threshold, heavy metal waste in water and air must be considered. Various methods and instruments could be used for analysis of heavy metal waste levels. However, quick and accurate method needs to be upgraded in order to improve the efficiency of analysis. Ag nanoparticle is an alternative that could be used to detect the presence of heavy metal waste. Ag nanoparticles can be synthesized through reduction reaction with reductant agents from chemicals, biological compounds, and gamma irradiation. This research used qualilative analysis, utilizing chitosan stabilizer for Ag nanoparticles with gamma irradiation reductant in various doses, such as 7.5, 15, and 20 kGy. The results showed that AgNPs/chitosan was formed in the peak absorption range of 390-500 nm with optimum gamma irradiation dose of 15 kGy. In addition, AgNPs/chitosan has good sensitivity to detect Cr and Hg metals and was not sensitive to Cu and Pb metals.]]>
<![CDATA[Radial Sensitivity of the Nuclear Shell Structure at N=92 ]]>
<![CDATA[Swain, R. R.]]>;
<![CDATA[Anupam, A.]]>;
<![CDATA[Mohanty, P.]]>;
<![CDATA[Jena, K. K.]]>;
<![CDATA[Agarwalla, S. K.]]>;
<![CDATA[Sahu, B. B.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1491
<![CDATA[The nuclear ground-state properties of Sm isotopes are calculated and analyzed using an improved mass formula. The asymmetric energy term is consistently observed, separated into a volume and surface component. While distinctive signatures for certain isotopes remain elusive, the results show reasonable agreement with experimental data and well-established theoretical models such as the Relativistic-Continuum-Hartree-Bogoliubov (RCHB) and the Finite Range Droplet Model (FRDM). By utilizing a root-mean-square (rms) charge radius formula that incorporates both shell and deformation effects, the study provides new insights into the anomalous shifts observed in magic isotopes (N=82, N=126), as well as in N=92, 136, and 144 within the isotopic series of the "Sm" element.]]>
<![CDATA[Preliminary Neutronic Studies on RSG-GAS Fuel Element with 4.8 grU/cc and Burnable Poison Wire for Reactivity Reduction ]]>
<![CDATA[Luthfi, W.]]>;
<![CDATA[Setiadipura, T.]]>;
<![CDATA[Su’ud, Z.]]>
<![CDATA[ Atom Indonesia Vol 51, No 1 (2025): APRIL 2025 ]]>
Publisher : <![CDATA[National Research and Innovation Agency ]]>
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DOI: 10.55981/aij.2025.1503
<![CDATA[High-density fuel can increase the operating cycle of a nuclear reactor. The G.A. Siwabessy Multipurpose Reactor (RSG-GAS) is a research reactor owned by Indonesia that currently uses 19.75 % enriched uranium silicide fuel (U3Si2-Al) with a uranium density of 2.965 grU/cc. Previous studies have shown that high-density fuel, 4.8 grU/cc, can be used in the RSG-GAS core to extend the operating cycle. Previous studies related to high-density fuel conversion scenarios included a temporary conversion process to a density of 3.55 grU/cc before being increased to 4.8 grU/cc. However, the previous conversion process requires the addition of control rods to suppress the excess reactivity of the RSG-GAS. The current study focuses on determining the configuration of burnable poison wire for the standard fuel element of RSG-GAS (FE) made of cadmium and hafnium to suppress the reactivity (k-inf) of the 4.8 grU/cc fuel element so it could have an initial reactivity closer to the 2.965 grU/cc fuel. 5 pairs of 0.4 mm diameter Cd-wire coated with 0.1 mm AlMg2 cladding can suppress the reactivity of the fuel assembly, while 7 pairs of 0.8 mm diameter Hf-wire without cladding could suppress reactivity longer. The temperature coefficient of reactivity for the moderator temperature (MTC) and fuel temperature (FTC) also becomes more negative in high-density FE RSG-GAS while the amount of Pu-239 produced increases in high-density fuel element.]]>
