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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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Assessment of the Level of Radioactivity in the Soil in Urban Areas and Building Materials of Arlit City (Agadez-NIGER) Sidibé, M. O.; Manga, A. O.; Soumana, S.; Adukpo, O. K.
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.2024.1374

Abstract

Niger's uranium deposits are located in the north, bordering the southern Sahara. Mining activities led to the creation of the town of Arlit in 1969. Uranium mining and uranate production generate large volumes of radioactive solid and liquid tailings, as well as radioactive gases. Through dispersion and transport, these radioactive discharges become a source of contamination to the environment and food chain. The aim of our work is to assess the additional ambient exposure to radioactivity of surrounding populations as a result of mining activities. We assessed the risk of exposure to radionuclides from the uranium-238 decay chain through soil and certain building materials. The methodology used is based on collection of soil, sand, gravel and mud samples, which are analyzed using gamma spectrometry technique. Nine (9) public sites and five (5) building materials quarries were sampled for the work. The radiological parameters calculated are radium equivalent activity (Raeq), absorbed dose rate (D), internal and external risk indices (Hin and Hex) and gamma index (Iγ). For the whole study area, the calculated Raeq values range from 78.67 Bq/kg to 199.32 Bq/kg. These values are below the guideline value of 370 Bq/kg. In terms of air dose rate, however, the average value found was 0.32 mSv/year for the nine public sites considered. This exceeds the threshold value of 0.29 mSv/year corresponding to the selected exposure scenarios. In addition, in the mud (Quarry 5) and the second gravel quarry (Quarry 4), Iγ values greater than unity were found. A comparison is made with the results of similar studies around the world. Interpretation of the data obtained concludes that there is a risk of radiological overexposure at six (6) sites and two (2) quarries. This work is independent research which sheds new light on the issue of uranium mining activities impact on the environment in Arlit.
Neutronic Design Modification of Passive Compact-Molten Salt Reactor Dwijayanto, R. A. P.; Harto, A. W.
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.2024.1308

Abstract

Passive compact molten salt reactor (PCMSR) is a design concept of a molten salt reactor (MSR) currently under development in Universitas Gadjah Mada, Indonesia. It is designed as a thermal breeder reactor using thorium fuel cycle. However, our previous study shows that the original PCMSR design was incorrectly modelled, primarily overestimating its thorium breeding capability. To improve PCMSR neutronic design, we modified the core configuration by the addition of radial fuel channel layers previously nonexistent in original PCMSR core design in various configurations. Neutronic parameters of modified PCMSR geometries in the beginning of life (BOL) were simulated using MCNP6.2 radiation transport code with ENDF/B-VII.0 library. All variations of fuel layer addition show improvement in both temperature coefficient of reactivity (TCR) and breeding ratio (BR), with TCR values became more negative and BR values are larger than unity, ensuring proper breeding capability. Configuration Inner Core-Outer Blanket (IC-OB) achieves the largest BR and lowest doubling time (DT), whilst its TCR is an improvement from the original design. Therefore, IC-OB fuel layer configuration can be applied to redesign the original PCMSR and used in various design optimization scenarios.
Preface Atom Indonesia Vol 50 No 2 prfc50no2, prfc50no2
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.2024.1512

Abstract

Preliminary Study of Micronucleus Frequencies and Responses in Thyroid Cancer Patients After Treatment with 131I Therapy Basri, I. K. H.; Lusiyanti, Y.; Ramadhani, D.; Tetriana, D.; Dewi, A. R.; Purnami, S.; Suvivan, V. A.; Gani, M. R. A.; Kisnanto, T.
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.2024.1409

Abstract

Radioiodine has become the most widely used to treat an overactive thyroid (hyperthyroidism) and thyroid cancer worldwide. The present research aimed to study the association between micronuclei (MN) frequencies, and follow-up responses after treating thyroid cancer patients with iodium-131(131I). The detection of the MNs assay was carried out by Giemsa staining from lymphocytes obtained from twenty-four thyroid cancer patients one week after receiving 131I treatment at Dharmais Cancer Center Hospital, Jakarta, Indonesia. Follow-up for clinical and laboratory responses grouped into good (stable) and bad (progressive, refractory, and dropout patients) responses, was observed one and six months after treatment. All patients received radioiodine with an activity dose of 30 - 200 μCi. The mean MN frequency in the good response group was 14.22, and that of bad response patients was 17.22. There was no statistically significant difference in MN frequency (p>0.05) between the two groups of patients after six months of treatment.
Preliminary Neutronic Studies on RSG-GAS Fuel Element with 4.8 grU/cc and Burnable Poison Wire for Reactivity Reduction Luthfi, W.; Setiadipura, T.; Su’ud, Z.
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.2025.1503

Abstract

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.
Radiological Risk to Inhalation of Thoron Gas from Medical Materials Samples Derived from Medical Plants in Iraq Abojassim, A. A.; Lawi, D. J.; Hassan, A. B.
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.2024.1329

Abstract

Pollution by thoron is one of the factors that is harmful to human health. Medical materials, especially those derived from plants, have natural ingredients which are a major source of natural radioactivity, thoron being one of them. Therefore, the presence of harmful radioactivity in these materials is a matter of concern. This study determined the concentrations of thoron (220Rn or radon-220) from 70 samples of medical materials derived from medical plants using a CR-39 detector. Samples are drugs (solid), skin creams, herbs, toothpaste, drugs (liquid), and cosmetic products found in Iraqi pharmacies. Also, radiological risks such as Annual Effective Dose (AED), Excessive Lifetime Cancer Risk (ELCR), and Lung Cancer Case (LCC) due to inhalation of thoron from medical materials samples in pharmacies were calculated. The results show that the results of the thoron  concentrations in the samples of medical materials ranged from 1.02 Bq/m3 to 74.53 Bq/m3, with an average value of 18.21 ± 2.00 Bq/m3. The range values of AED, ELCR (×10-3) and LCC (×10-6) were 0.01-0.588 mSv/y, 0.04-2.36, and 0.18-10.58, respectively. It was als found that the thoron concentrations in samples of the present study vary from a minimum of 12.82 Bq/m3 in cosmetic products samples to a maximum of 30.29 Bq/m3 in herbs samples. Nonetheless, all thoron and radiological risk values were lower than the acceptable world limit (thoron = 200-300 Bq/m3  by ICRP and AED = 1.1-4.4 mSv/y by UNSCEAR).
Preface Atom Indonesia Vol 50 No 3 Indonesia, Atom
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.2024.1574

Abstract

The Modelling and Analysis of iPWR-Type SMR Core Dynamics: Control Rods, Reactivity Feedback, and Thermal-Hydraulic Effects Septawijaya, G.; Sukarman, S.; Bakhri, S.; Subekti, M.
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.2024.1414

Abstract

Development plans for Nuclear Power Plants (NPPs) in Indonesia have been widely discussed. One of the planned NPP types is the Small Modular Reactor (SMR). Human resource readiness is an essential aspect to be considered before constructing an NPP. Simulators capable of illustrating core dynamics can be used to educate the public about the processes within a nuclear reactor. Core modeling is a key component in developing an NPP simulator. The neutronic behavior of the reactor core is modeled using point kinetics equations, while the thermal-hydraulic aspect uses Mann’s model. The results indicate that the modeled core can operate up to 160 MWt and other operating parameters at maximum power align well with the SMR reactor design certification data.
Bibliometric Analysis of the Literature on Carbon Ion Therapy Using VOSviewer Software and Dimensions Database El Bekkouri, H.; Al Ibrahmi, E.; El-Asery, M.; Bardane, A.; Didi, A.; El Mahjoub, C.; Sadoune, Z.
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.2024.1392

Abstract

This study aims to carry out a bibliometric assessment of the worldwide research literature and historical research results on carbon ion therapy for cancer treatment. To carry out this work, we used the VOSviewer software and the Dimensions database. The VOSviewer software tool examined 2,500 publications exported from the Dimensions database. The results show a notable upward trajectory in academic research on carbon ion therapy since 1994, with 2020 showing the highest volume of publications. “Biomedical and Clinical Sciences”, “Physical Sciences”, “Oncology and Carcinogenesis”, and “Medical and Biological Physics” are the most important research categories. “Physics in Medicine and Biology” and “Medical Physics” are the leading journals for research publications on carbon ion therapy. Scrutiny based on term occurrences demonstrates the shift in research interest towards carbon ion radiation therapy. The analysis of bibliographic couplings concerning different countries revealed that Japan is the most dynamic and prolific country based on the number of publications (659) and citations (13734), followed by Germany with 590 publications and 19679 citations. These analytical studies provide a thorough overview of academic publications dedicated to using carbon ions for tumor treatment. This data is anticipated to be highly valuable for researchers seeking to pinpoint the most recent developments and emerging trends in this field of research.
Atmospheric Plasma-Assisted Preparation of Graphene Oxide from Biomass: Characterization and Elemental Analysis Handayani, A. H.; Amalia, F.; Noviantana, E. V.; Mulyaningsih, T. R.; Waris, A.; Dimyati, A.
Atom Indonesia Vol 51, No 2 (2025): AUGUST 2025
Publisher : National Research and Innovation Agency

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/aij.2025.1472

Abstract

Graphene oxide (GO) was successfully synthesized using the atmospheric plasma process with biomass precursors, including coconut fronds, palm fronds, and rambutan stems, within a five-minute processing time. Plasma technology converts near-waste materials into valuable resources with potential for various applications. Graphene oxide, in particular, exhibits high mechanical strength, excellent electrical conductivity, good biocompatibility, and a large surface area, making it a highly versatile material. Raman spectroscopy was used to analyze the formation of synthesized graphene. The presence of organic and inorganic elements in graphene oxide was characterized using a scanning electron microscope equipped with energy-dispersive X-ray spectroscopy (SEM-EDS) and neutron activation analysis (NAA). SEM-EDS analysis revealed that the C:O ratio in plasma-derived graphene oxide exceeded 80 % in each sample. NAA identified 22 inorganic elements, which are naturally present in biomass. Understanding the elemental composition of plasma-synthesized graphene oxide is essential for evaluating its potential applications and identifying necessary purification steps. The oxygen content in the synthesized material, which primarily originates from the inherent properties of biomass, can be regulated by optimizing plasma parameters. Using biomass precursors makes plasma-synthesized graphene oxide an economically viable option for large-scale production.

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