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INDONESIA
Atom Indonesia Journal
Published by Badan Tenaga Nuklir Nasional
ISSN : -     EISSN : -     DOI : -
Core Subject : Science,
Materials Science & Nanotechnology
Exist for publishing the results of research and development in nuclear science and technology Starting for 2010 Atom Indonesia published three times a year in April, August, and December The scope of this journal covers experimental and analytical research in all areas of nuclear science and technology. including nuclear physics, reactor physics, radioactive waste treatment, fuel element development, radioisotopes and radio pharmaceutical engineering, nuclear and radiation safety, neutron scattering, material science and technology, as well as utilization of isotopes and radiation in agriculture, industry, health and environment.
Arjuna Subject : -
Articles 13 Documents
 1   2 
Search results for , issue "Vol 47, No 1 (2021): April 2021" : 13 Documents clear
Proposed Managements of 137Cs Contaminated Soil: Case Study in South Tangerang City B. Setiawan; D. Iskandar; G. Nurliati; H. Sriwahyuni; M Mirawaty; P. A. Artiani; K. Heriyanto; N. E. Ekaningrum; Y. Purwanto; S Sumarbagiono
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1055

Abstract

Recently, BAPETEN found contamination of 137Cs while testing environmental radiation monitoring equipment in an area in South Tangerang City. The area, therefore, needs to be cleaned up by performing decontamination followed by the activity of treating the contaminated soil. The decontamination works were carried out by excavating the contaminated soil on the surface to a depth of more than 1.5 m, and then the soils were put into the 100L drum. Decontamination work resulted in a significant reduction dose exposure in the area to 0.3-0.75 mSv/h. The drums containing contaminated soil were then sent to the interim storage facility in BATAN Serpong facility for further treatment. To resolve the 137Cs contaminant, some alternatives in the decontamination and management of the contaminated soils were studied. Some techniques and strategies for decontamination and managing 137Cs are presented in this paper. Management that involves wet and dry methods will be proposed in this paper. By comparing and evaluating various alternative management methods, an appropriate method for treating the contaminated soil in South Tangerang City can be obtained. The objective of the study was to find a suitable management method for the contaminated soil based on the proposed alternative management methods.In the present case, the compaction method seems promising for use soon.
Investigation on the Background Radiation of Abakaliki Rice Mill in Ebonyi State, Nigeria A. Nwachukwu; F. C. Ikeagwuani; A. O. Adeboje
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1040

Abstract

This study investigated the background ionizing radiation of Abakaliki rice mills. The requirement to monitor this site is because the prevalent activities in the site suggest that it is a source of ionizing radiation. The activities include fuel stations and excavation sites. Other sources are various chemicals and agrochemicals (like Phosphate, Uranium, Thorium, and Radium) used during the planting of the different rice species. There is, therefore, an urgent need to investigate the radiation level of Abakaliki rice mills in Ebonyi state, Nigeria to ascertain if it has passed the safety standards. The investigation was carried out using the Radalert 100 radiation monitor and a geographical positioning system (Garmin GPSMAP 765). The studied site was split into different points with each representing a mill that houses different grinding plants. This study included all the sections of the mill. The mean background radiation exposure rate ranges from 0.014mRhr-1to 0.0204mRhr-1. The obtained values are higher than the world standard limit of 0.013mRhr-1 recommended by ICRP except point 7 which corresponds to the top of the rice husk dumpsite. The calculated absorbed dose rates for the various sections of the mill ranged from 99.18 nGh-1 to 177.48 nGyh-1. These values of absorbed dose rates were observed to be far higher than the world permissible value of 89 nGyh-1. The annual effective dose equivalent (AEDE) for the exposure values ranged from 0.122 mSvy-1 to 0.218 mSvy-1 which are far lower than the ICRP permissible limits of 1.00 mSvlyr for the public and therefore implies absence of any immediate radiological risk. The excess lifetime cancer risk for the mill users were all above the 0.29 × 10-3 world recommended value. This suggests a possibility of the rice mill workers developing radiation-related illnesses over time.
Cover Atom Indonesia Vol 47 No 1 cover47 cover47
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1142

Abstract

Safety Investigation of Hazardous Materials Released from the Combined High Temperature Gas Cooled Reactor – Hydrogen Production Plant Using ALOHA Software D. Priambodo; S Sunarko; W. W. Purwanto
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.939

Abstract

Safety Investigation of Hazardous Materials Released from The Combined High Temperature Gas Cooled Reactor (HTGR) – Hydrogen Production Plant Using ALOHA software has been carried out. Currently, most of studies for HTGR-hydrogen plant are focused only on the impact of hydrogen presence to the HTGR plant safety. Therefore, the objective of this study was to investigate the effect of the presence of natural gas and synthetic gas from Steam Methane Reforming hydrogen plant on the combine HTGR-Hydrogen production system using ALOHA software. Three selected hazardous materials: CH4, CO and H2 were analyzed. The selected potential hazards of the hazardous materials after leaking from the pipe were downwind suffocation/toxication, flammable area and blast area from vapor cloud explosion. Two types of parameter, i.e., meteorological dispersion (including wind speed, temperature, humidity, nuclear building air changes for day and night) and source release parameters (including pipeline length, and distance from the reactor building to the hydrogen plant), were selected for this study. The effects of the parameters on the hazard distance were then analyzed. The study shows that hydrogen detector needs to be installed at the plant to ensure safety of field operator. Furthermore, CO adsorber and H2 recombiner should be installed at the Reactor HVAC system for CO poisoning and H2 fire protection. Provision of a separation distance of more than 250 meters or construction of a blast barrier between the reactor building and the hydrogen plant is also recommended to protect the reactor from H2 explosion hazard.
Radon Concentrations in Canned Liquid Juice A. A. Abojassim
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2020.1030

Abstract

This study was performed at University of  Kufa, Iraq, using canned liquid juice samples found in Iraqi markets due to the absence of environmental contamination from radionuclides emitting 222Rn concentrations using RAD-7 detectors. The annual effective dose (AED) of 222Rn was estimated for children and adults from the ingestion of canned liquid juice samples. The estimated concentrations of 222Rn in unit (mBq/L) ranged from 35.4 to 249.1, with an average of  77.880.24 ± 15.42. It also shows that the AED values for children and adults in (nSv/y) ranged from 19.11 to 134.48 with an average of 43.31 ± 8.32 and from 22.67 to 159.55 with an average of 51.39 ± 9.88, respectively. All estimated results of 222Rn concentrations for juice samples were lower than the natural limits provided by the WHO and the European Union Commission to the public (0.5 and  1 Bq/L, respectively). Therefore, there are no health hazards from drinking juice sold in Iraq markets.
Preface Atom Indonesia Vol 47 No 1 preface471 preface471
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1143

Abstract

Conceptual Design of Experimental Facility for Large-Diameter NTD-Si at the IRT-T Reactor I. I. Lebedev; D. E. Zolotykh; A. G. Naymushin; N. V. Smolnikov; M. N. Anikin; V. V. Varlachev
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1005

Abstract

The IRT-T reactor has been conducting research in the field of irradiation of ingots of single-crystal semiconductor materials since 1987. The article describes the existing silicon doping facility. The results of studies on the possibility of creating an additional irradiation channel for neutron-transmutation doping of silicon are presented. It is shown that the use of a graphite reflector and a thermal neutron filter based on boron makes it possible to achieve non-uniformity of irradiation up to 5 %. The principal possibility of irradiating single-crystal silicon ingots with a diameter of up to 203 mm and a length of up to 500 mm is shown. The questions of optimizing the configuration of the core and the regime of reactors operation for increasing the neutron flux in the irradiation channels are discussed. In addition, applying the facility to produce base materials for neutron dosimeter in neutron capture therapy studies is proposed.
Study of Dried and Calcinated Ceria Stabilized Zirconia Microspheres Morphology by Small-Angle X-Ray Scattering and Optical Microscopy A. Patriati; A. Insani; N. Suparno; E. Hutamaningtyas; S. Soontaranoon; M Mujamilah
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2020.1023

Abstract

The knowledge of how to avoid crack at high temperature is crucial in fuel fabrication for Experimental Power Reactor or Reaktor Daya Eksperimental (RDE). This knowledge should be established and well-mastered by BATAN. RDE uses uranium dioxide as its nuclear fuel. However, uranium utilization for research purposes is heavily restricted. Therefore, the fabrication of ceria-stabilized zirconia (CSZ) microspheres as nuclear fuel surrogate was studied. In this work, the CSZ was prepared by external gelation with two different washing solutions, i.e. isopropyl alcohol (IPA) and propylene glycol methyl ether (PGME). The morphology in nano- and micro-scale of each CSZ microspheres from both variations was evaluated by small-angle x-ray scattering (SAXS) and optical microscopy. The morphology of the CSZ microsphere after drying at 80 °C and calcination at 200 °C were observed to understand the structural change in those steps and to see the potential crack based on its morphology. There are two parameters that can prevent microspheres from cracking at high temperatures for the next process, i.e., porosity and gel texture. It was observed that IPA solution has a benefit as a washing solution as it can trigger more porosities in the microspheres, but less in gel texture.
Acknowledgement Atom Indonesia Vol 47 No 1 ack471 ack471
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1144

Abstract

Synthesis and Characterization of Ordered and Disordered Mesoporous Alumina as High-Performance Molybdenum-99 Adsorbents I. Saptiama; F. Rindiyantono; A. Aries; Y. V. Kaneti; M. Iqbal
Atom Indonesia Vol 47, No 1 (2021): April 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1000

Abstract

Molybdenum-99 (99Mo) is the parent radioisotope of technetium-99m (99mTc),an essential medical radioisotope for diagnostic agents in nuclear medicine.In 99Mo/99mTc generator, a chromatography column system with 99Mo adsorbent as afiller is usually used to produce 99mTc in hospitals. However, it is still challenging to find high-performance adsorbentsfor Mo adsorption.We have synthesized both ordered and disordered mesoporous alumina and compared their performance as 99Mo adsorbents. These materials were prepared via a soft-templated method using a triblock copolymer as the template, followed by air calcination at 400°C.The amount of nitric acid (HNO3) and the drying time were adjusted systematically to synthesize the ordered mesoporous alumina. The obtained ordered and disordered mesoporous alumina were characterized by low-and wide-angle X-ray diffractions (XRD), nitrogen adsorption-desorption, thermogravimetric analysis (TGA), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The 99Mo adsorption capacities of these materials were evaluated by using the batch method. The experimental results show that the ordered mesoporous alumina hasa higher 99Mo adsorption capacity of 72.06 mg(Mo)g-1 than the disordered mesoporous alumina (50.12 mg(Mo)g-1). The results indicate the excellent potential of ordered mesoporous alumina as an adsorbent for the 99Mo/99mTc generator column.

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