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Prof. Dr. Muhayatun Santoso
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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 79 Documents
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Customization of Source Term into JRODOS Compatible XML File Format Using Visual Basic for Nuclear Accident Analysis Hassan, S. M. T.; Khaer, M. A.; Hoq, M. A.; Chowdhury, M. T.; Rahman, M. M.
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.2025.1432

Abstract

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.
Thermal Properties of Alpha Decay in Magnetic Field Medium Nwabuzor, P. O.; Ngiangia, A. T.; George, F. J.
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.2025.1316

Abstract

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.
Fluka Monte Carlo for Validating Low-Energy Neutron Capture Therapy Tissue with Boron and Gadolinium Bakolia, T. E.; Didi, A.; Sebihi, R.; Adambounou, K.; Hazou, E.
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.2024.1380

Abstract

Research Gap: Neutron Capture Therapy (NCT) represents a cutting-edge neutron-therapy technique for tumor treatment, but there is a gap in understanding the optimization of neutron dose deposition in tumor cells, particularly in tissues enriched with boron and gadolinium. Research Objective: This study aims to evaluate the dose deposited by thermal neutrons in adipose tissues enriched with boron and gadolinium, utilizing the Monte Carlo Fluka code. Research Methodology: The research employs Fluka, an open source Monte Carlo simulations to assess thermal neutron dose deposition in tissues. The focus is on boron and gadolinium-enriched tissues to understand their impact on neutron dose optimization. Results: Findings affirm the advantages of boron and gadolinium in enhancing neutron dose deposition within tissues. Fluka simulations demonstrate the strategic utilization of neutron properties, showcasing the potential for improved tumor management. The study highlights gadolinium's attractiveness, suggesting its promising application in clinical settings.
Characterizing Photon Beam Properties of a TrueBeam STx Linear Accelerator: An Evaluation of Geant4/GATE Monte Carlo Simulation Tool Performance Lam, P. H.; Dung, P. T.; Trung, P. Q.
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.2024.1451

Abstract

Purpose: This study aims to investigate the characteristics of photon beams from TrueBeam STx, comparing flattening filter (FF) and flattening filter free (FFF) configurations between measurements and Monte Carlo simulation. Instruments and methods: The Geant4/GATE simulation toolkit was utilized to simulate percentage depth dose (PDD), off-axis distance profiles (profiles), dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry. Subsequently, these simulated results were compared with experimental measurements and evaluated using the gamma index method. Results: There was a good agreement between simulation and experimental measurement results in modeling the PDD and profile of photon beams. All gamma passing rate indices exceeded 97 %, 94 %, and 90 % with criteria of 3 % and 3 mm, 2 % and 2 mm, and 1 % and 1 mm, respectively. The calculated results of beam characteristics (dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry) were highly compatible with experimental measurements, with discrepancies less than 3 %, except for the surface dose of the 6MV FF photon beam, which had an error of 3.83 %. Conclusion: The Geant4/GATE simulation toolkit provided accurate results for simulating and investigating photon beam characteristics, aligning closely with experimental measurements.
Atmospheric Nitrogen Plasma-Induced for Embedding NH2@Cubic-Bicontinuous Mesoporous Silica as Uranium (VI) Adsorbent Candidate in Seawater Pamungkas, N. S.; Wongsawaeng, D.; Swantomo, D.; Kamonsuangkasem, K.; Chio-Srichan, S.
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.2024.1301

Abstract

This work aims to achieve interesting progress in uranium extraction by introducing a promising strategy that utilizes atmospheric nitrogen plasma-induced amine modification of CBC (Cubic Bi-continuous) material, providing a compelling pathway to enhance CBC's adsorption properties specifically for uranium harvesting. CBCs mesoporous silica samples were prepared by mixing the Pluronic F-127 as a template and TEOS (Tetraethyl Orthosilicate) as silica sources in the sol-gel process under acidic conditions. The obtained CBCs were treated using nitrogen plasma at room temperature (RT) under atmospheric pressure in a customized-borosilicate plasma reactor. Subsequently, the treated CBSs were grafted with amine groups. The final samples were characterized using SAXS (Small Angle Synchrotron X-ray Scattering) to determine the phase and structure, SEM-EDS (Scanning Electron Microscopy-Energy Dispersive Spectroscopy) analysis to quantify the presence of silica, oxygen, and embedded nitrogen, and Specific Surface Area (SSA) Analyzer using Brunauer-Emmett-Teller (BET) method to determine the specific surface area and pore size distribution. The SAXS profiles indicate that the obtained samples can be classified as CBCs Im3m mesoporous silica. The presence of silica, oxygen, and nitrogen was verified through SEM-EDS analysis, with approximate compositions of 36-37 %, 51-62 %, and 0.7-1.0 %, respectively. The use of SSA analysis further supported the findings, confirming the typical adsorption isotherm IV model. The specific surface areas were measured to be 371 m2/g for pure CBC, 573 m2/g for P1-CBC, and 607 m2/g for P2-CBC. The pore size distribution analysis revealed mesoporous characteristics within the material, with pore sizes ranging from 4 to 6.5 nm. On a batch laboratory scale, the material achieved the highest adsorption capacity of 15.68 mg-U(VI)/g-NH2@P1-CBC from natural seawater after 1 hour of contact time.
Acknowledgement 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.2025.1660

Abstract

The Effect of Zinc Concentration on Bioaccumulation in Milkfish (Chanos chanos) Use of 65Zn as a Radioactive Tracer Wahyono, I. B.; Muslim, M; Suseno, H.; Suryono, C. A.
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.2024.1355

Abstract

Bioaccumulation studies of zinc (Zn) in milkfish (Chanos chanos) have been carried out in the laboratory using a 65Zn radiotracer. The research was conducted to determine the effect of Zn concentration on the ability of Chanos chanos to accumulate and release these contaminants. Zn absorption follows the single-compartment model, and experiments were carried out until stable conditions were achieved. The stages of research were biota collection, acclimatization, bioaccumulation, and elimination. Acclimatization was carried out for biota adaptation in the experimental environment. Bioaccumulation was carried out for 7 days by placing the biota in an aquarium filled with seawater added with 65Zn radiotracer contaminants. The elimination process involves the release of contaminants from the biota by placing them in contaminant-free seawater for 7 days. The results of the bioaccumulation experiment showed that the concentration factor (CF) ranged from 0.67 - 18.18 mLgr-1 at a concentration of ZnCl2 of 1.5 ppm, and the absorption constant (ku) 1.878 - 3.267d-1 and R2 was 0.0276. The release of contaminants in depuration experiments was highest at ZnCl2 2 ppm concentrations. The percentage of retention during depuration was between 14.61 - 79.91 %, the elimination constant (ke) was 8.681, and R2 was 0.7213.
Radiation Dose and Image Quality of Bladder Cancer Patients Analysis on Abdominal CT-Scan Examinations Anthon, R.; Intifadhah, S. H.; Putri, E. R.
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.2025.1526

Abstract

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.
Dose Response of Hp(0.07) on TLD-700 and TLD-900 Based Ring Dosimeters to the Sr-90 Exposure Jumpeno, E. B.; Anggraeni, R.; Putri, M. Muharani; Barokah, S. N.; Adisti, F. N.
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.2024.1425

Abstract

The preparation of radiopharmaceuticals may necessitate close contact with the radioactive source. In this case, high-energy beta-emitting nuclides can cause a high exposure. There are two methods of measuring the dose in the extremities, including using a bracelet and a ring dosimeter. In this study, the response of Hp(0.07) dose in TLD-700 and TLD-900-based ring dosimeters to Sr-90 beta radiation will be compared for parameters of distance, time, and angle of irradiation. The dosimeters were irradiated using Sr-90 at a distance of 5, 7, and 10 cm from the source surface and all of them were subsequently read with TLD Reader. The same type of dosimeters were exposed to Sr-90 for 1 day, 2 days, and 3 days at a distance of 7 cm and read. At a distance of 7 cm, the other dosimeters were irradiated at angles of 30°, 60°, -30°, and -60°, and then read. The study shows that the relationship between the distance of irradiation to Hp(0.07) dose is polynomial with a correlation factor of 1, both for TLD-700 and TLD-900-based ring dosimeters. The dose response at the variation of irradiation time showed linear behavior with correlation coefficients of 0.9942 and 0.9999 for TLD-700 and TLD-900, respectively. The decrease in Hp(0.07) response in TLD-700 reached 14-31 % for the irradiation angle of ±30o and 23-27 % in TLD-900 for the same angle. Meanwhile, the decrease in Hp(0.07) response at the angle of irradiation ±60o reached 48 % for TLD-700 and 66-67 % for TLD-900.
Investigation of Tissue Components Impacts on Dose Enhancement Factor Using Monte Carlo Code AL-suhbani, M. N.; Baghous, N. E. H.; Serag, S.; EL Mahjoub, C.; Ait-Mlouk, L.; Zia, A.; Hamid, B.; Azougagh, M.
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.2024.1305

Abstract

Despite the progress of science in cancer treatments and radiotherapy improvements, there are still several side effects that occur during tumors treatment, particularly on healthy tissues surrounded tumors. Newer treatment methods are being explored lately, one of which is the use of nanoparticles, wherein the tumor is injected with gold nanoparticles. Its aim is to enhance tumor sensitivity to radiation and reduce radiation damage to healthy tissues. Tissue type may play an effective role in enhancing the dose being received under the use of nanoparticles. This study aims to find the effect of different tissue components on dose enhancement factor through MCNP6 and GATE simulations, as well as to accurately compare  the simulation results of these two code packages for dose enhancement factors. A 125I brachytherapy source was simulated in phantoms for five tissues or materials (adipose tissue, breast tissue, soft tissue, water, and brain tissue). MCNP6 simulation code was validated by comparing its results with a previous study by Cho et al. Gold nanoparticles were injected as a mixture at a concentration of 7 mg/g into tissues inside a tumor. MCNP6 and GATE simulation results were compared. It was estimated from MCNP simulations that the highest radiation dose enhancement of 2.34 occurs in adipose tissue while lowest dose enhancement of 1.69 is in brain. In comparison, from GATE results, the estimates were that the highest value of dose enhancement factor also occurred in adipose tissue at 2.01, and the lowest value in brain at 1.48. The comparison between two codes suggest that they are compatible with the percentage difference in all tissues being less than 15 %. This study confirms that both MCNP6 and GATE codes could calculate DEF for different tissues under irradiation from a low-energy source.

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