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Atom Indonesia Journal

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Published by Badan Tenaga Nuklir Nasional

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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.

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Articles 452 Documents

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Analysis of 99Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP A. Isnaeni; M.S. Aljohani; T.G. Aboalfaraj; S.I. Bhuiyan
Atom Indonesia Vol 40, No 1 (2014): April 2014
Publisher : PPIKSN-BATAN

99mTc is a very useful radioisotope in medical diagnostic procedure. 99mTc is produced from 99Mo decay. Currently, most of 99Mo is produced by irradiating 235U in the nuclear reactor. 99Mo mostly results from the fission reaction of 235U targets with a fission yield about 6.1%. A small additional amount is created from 98Mo neutron activation. Actually 99Mo is also created in the reactor fuel, but usually we do not extract it. The fuel will become spent fuel which is a highly radioactive waste. 99Mo production system in the aqueous homogeneous reactor offers a better method, because all of the 99Mo can be extracted from the fuel solution. Fresh reactor fuel solution consists of uranyl nitrate dissolved in water. There is no separation of target and fuel in an aqueous homogeneous reactor where target and fuel become one liquid solution, and there is no spent fuel generated from this reactor. Simulation of the extraction process is performed while reactor in operation (without reactor shutdown). With an extraction flow rate of 3.6 L/h, after 43 hours of reactor operation the production of 99Mo is relatively constant at about 98.6 curie/hour./hour.Received: 11 January 2014; Revised: 18 February 2014; Accepted: 28 February 2014

Analytical Methods INAA and PIXE Applied to Characterization of Airborne Particulate Matter in Bandung, Indonesia D.D. Lestiani; M. Santoso
Atom Indonesia Vol 37, No 2 (2011): August 2011
Publisher : PPIKSN-BATAN

Urbanization and industrial growth have deteriorated air quality and are major cause to air pollution. Air pollution through fine and ultra-fine particles is a serious threat to human health. The source of air pollution must be known quantitatively by elemental characterization, in order to design the appropriate air quality management. The suitable methods for analysis the airborne particulate matter such as nuclear analytical techniques are hardly needed to solve the air pollution problem. The objectives of this study are to apply the nuclear analytical techniques to airborne particulate samples collected in Bandung, to assess the accuracy and to ensure the reliable of analytical results through the comparison of instrumental neutron activation analysis (INAA) and particles induced X-ray emission (PIXE). Particle samples in the PM2.5 and PM2.5-10 ranges have been collected in Bandung twice a week for 24 hours using a Gent stacked filter unit. The result showed that generally there was a systematic difference between INAA and PIXE results, which the values obtained by PIXE were lower than values determined by INAA. INAA is generally more sensitive and reliable than PIXE for Na, Al, Cl, V, Mn, Fe, Br and I, therefore INAA data are preffered, while PIXE usually gives better precision than INAA for Mg, K, Ca, Ti and Zn. Nevertheless, both techniques provide reliable results and complement to each other. INAA is still a prospective method, while PIXE with the special capabilities is a promising tool that could contribute and complement the lack of NAA in determination of lead, sulphur and silicon. The combination of INAA and PIXE can advantageously be used in air pollution studies to extend the number of important elements measured as key elements in source apportionment. Received: 20 November 2010; Revised: 09 August 2011; Accepted: 15 August 2011

Pharmacokinetics Interaction of Non-Steroid Anti Inflammatory Drugs to 99mTc-MDP Radiopharmaceuticals for Bone Imaging and Its Biodistribution I. Mahendra; I. Daruwati; I. Halimah; S.R. Pajrin
Atom Indonesia Vol 44, No 3 (2018): December 2018
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2018.741

99mTc-MDP has been developed as a radiopharmaceutical for bone imaging in nuclear medicine. A drug therapy can alter the pharmacokinetic profiles and biodistribution patterns of radiopharmaceuticals. To achieve an optimum diagnostic outcome, this research focused on pharmacokinetics interaction between two kinds of nonsteroidal anti-inflammatory drugs (NSAID) drugs, meloxicam and sodium diclofenac with 99mTc-MDP using mice(Mus musculus). Therewerefive groups of animal modeland each group consists of three mice except for group II and III which consists of six mice. The groups were classified asuntreated mice (I), mice treated withmeloxicam for 3 days (II), treated with sodium diclofenac for 3 days (III), treated with meloxicam once or at onset (IV), and mice with sodium diclofenac once or at onset (V). Pharmacokinetics interaction and biodistribution test were conducted by injecting 100 µCi/100 µL 99mTc-MDP intravenously. Blood samples were withdrawn from each mouse which were then weighted and counted using single channel analyzer. The %ID/g of 99mTc-MDP in blood of untreated mice (I), mice treated with meloxicam (II) and sodium diclofenac (III) 5 minutes post injection were 3.71, 8.96 and 9.15 % respectively, then decrease to 0.12, 0.01, and 0.01 %, respectively, 24 hours post injection. The results of T-test showed there were no significant differences in distribution of 99mTc-MDP in untreated mice (I) and in treated mice either with meloxicam (II) or sodium diclofenac (III). However, there was significant difference in elimination of 99mTc-MDP in untreated mice (I) and in treated mice either with meloxicam (II) or sodium diclofenac (III). The bone uptakes of 99mTc-MDP were 9.03 ± 0.41, 3.52 + 0.52, 3.62 + 0.45, 8.44 + 1.39, and 8.09 ± 0.86 % in group I, II, III, IV, and V, respectively. T-test showed there were significant differences in bone uptake of 99mTc-MDP in mice with previously treated with meloxicam and sodium diclofenac for 3 days. From these result, it can be concluded that anadministration of meloxicam and sodium diclofenac could accelerate elimination half-life that cause low uptake of 99mTc-MDP radiopharmaceuticalon the bone as the primary target. Therefore, it is necessary to follow up using image study to determine the significance of the effects on image quality.

Development of TRIGA Fuel Fabrication by Powder Technique H. Suwarno
Atom Indonesia Vol 40, No 3 (2014): December 2014
Publisher : PPIKSN-BATAN

The prospect of operation of the Indonesian TRIGA reactors may be jeopardizes in the future due to the lack of fuel and control rods. Both fuel and control rods may not longer be imported and should be developed domestically. The most specific technology to fabricate TRIGA fuel rod is the production of UZrH1.6 pellet. The steps include converting the massive U metal into powder in by hydriding-dehydriding technique and mixing the U and Zr powders. A research has been planned to conducted by the National Nuclear Energy Agency (BATAN) in Indonesia. Fixed amount of U-Zr mixed powders at the ratio of U/Zr = 10 wt% was pressed into a pellet with a diameter of 1.41 in and a thickness of 1 or 1.5 in, sintered at a temperature of 1200oC, followed by hydriding at 800oC to obtained UZrH1.6. The pellets, cladding, and other components were then fabricated into a fuel rod. A detailed discussion of the TRIGA fuel fabrication is presented in the paper. Received: 22 October 2014; Revised: 29 December 2014; Accepted: 31 December 2014

Simulation of Ion Source’s Control System on Cyclotron Using Programmable System on Chip (PSoC) R.S. Darmawan; S. Santosa; Silakhuddin Silakhuddin
Atom Indonesia Vol 37, No 3 (2011): December 2011
Publisher : PPIKSN-BATAN

Cyclotron is an ion accelerator machine with spiral beam path. Ion source system is one of the main systems which its function is to produce ions that will be accelerated. In order to obtain maximum ion current, the ion source must be equipped with a control system that control mechanical system that will adjust the position of the ion source. The mechanical system able to make adjustment in three different axis, that is x, y and z axis. The mechanical system consists of a stepper motor and a set of gears. The control system using Programmable System on Chip (PSoC) utilizes its user module from the Random Sequence group, that is 8-bit Pseudo Random Sequence Generator (PRS8).For x and y axis, if the stepper motor rotate one rotation that means the support will be pushed or pulled 2.5 mm. While for z axis if the stepper motor rotate one rotation that means the support will be pushed or pulled 0.83 mm. The largest deviation of the stepper motor is 2° with error percentage is 1.09%. The mean value of step of the stepper motor is 2.03 step per second.Received: 20 November 2010; Revised: 07 October 2011; Accepted: 11 October 2011

Acknowledgement Atom Indonesia Vol 45 No 1 ack ack
Atom Indonesia Vol 45, No 1 (2019): April 2019
Publisher : PPIKSN-BATAN

The Effect of Pretreatment by using Electron Beam Irradiation on Oil Palm Empty Fruit Bunch A. Kristiani; N. Effendi; D. Styarini; F. Aulia; Y. Sudiyani
Atom Indonesia Vol 42, No 1 (2016): April 2016
Publisher : PPIKSN-BATAN

Oil palm empty fruit bunch (OPEFB) is a potential type of lignocellulosic biomass for second-generation bioethanol production. The pretreatment process is an important process in the series of processes to produce bioethanol. This research aims to study the effects of pretreatment process by using electron beam irradiation to OPEFB’s characterization as raw materials for the hydrolysis reaction to produce monomer sugars which will be fermented into ethanol. The untreated and treated OPEFB are characterized in terms of their physical and chemical properties. Analysis results of the compositional analysis by using NREL/TP-510-42618 method show that after pretreatment by using electron beam irradiation, OPEFB's total lignin content is changed little while its cellulose and hemicellulose contents tend to decrease with increasing irradiation dose. X-ray diffraction (XRD) analysis shows that there is a decrease of crystallinity compared to untreated OPEFB, except for 200-kGy irradiated OPEFB. The highest decrease of crystallinity was shown by 300-kGy irradiated OPEFB. Further, crystallite sizes of treated OPEFBs are not significantly different from the untreated, except for the 200-kGy irradiated OPEFB. Irradiation pretreatment also increases specific surface area, pore volume, and pore size. The IR spectra analysis show the absorption of cellulose, hemicellulose, and lignin.Received: 07 January 2015; Revised:15 May 2015; Accepted: 17 May 2015

Neutron-Gamma Pulse Shape Discrimination with a NE-213 Liquid Scintillator by Using Digital Signal Processing Combined with Similarity Method Mardiyanto Mardiyanto
Atom Indonesia Vol 34, No 2 (2008): July 2008
Publisher : PPIKSN-BATAN

Neutron-Gamma Pulse Shape Discrimination with a NE-213 Liquid Scintillator by Using Digital Signal Processing Combined with Similarity Method. Measurement of mixed neutron-gamma radiation is difficult because a neuclear detector is usually sensitive to both radiations. A new attempt of neutron-gamma pulse shape discrimination for a NE-213 liquid scintillator is presented by using digital signal processing combined with an off-line similarity method. The output pulse shapes are digitized with a high speed digital oscilloscope. The n-γ discrimination is done by calculating the index of each pulse shape, which is determined by the similarity method, and then fusing it with its corresponding pulse height. Preliminary results demonstrate good separation of neutron and gamma-ray signals from a NE-213 scintillator with a simple digital system. The results were better than those with a conventional rise time method. Figure of Merit is used to determine the quality of discrimination. The figure of merit of the discrimination using digital signal processing combined with of line similarity method are 1.9; 1.7; 1.1; 1.1; and 0.8 ; on the other hand by using conventional method the rise time are 0.9; 0.9; 0.9; 0.7; and 0.4 for the equivalent electron energy of 800 ; 278 ; 139 ; 69 ; and 30 keV.

Antiproliferative Activity of Extracts and Fractions from Irradiated Curcuma zanthorrhiza Rhizomes Against Mouse Leukemia and Human Cancer Cell Lines E.K. Winarno; H. Winarno; S Susanto
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.957

Curcuma zanthorrhiza Roxb. is a medicinal plant that is used as a raw material in the herbal medicine and pharmaceutical industries. The main content of C. zanthorrhiza is curcuminoid, which is used as an antioxidant and an anticancer agent. The aim of this research was to study the effect of gamma radiation used for preserving simplicia or herbal drugs through the examination of their cytotoxicity against mouse leukemia L1210 cells and antiproliferative activity against human cancer cell lines HUT78, A549, HeLa, and THP1. The samples of curcuma rhizome were irradiated by gamma ray emitted by Cobalt-60 as a source at doses of 0 (control), 5, 7.5, 10, and 15 kGy. After irradiation, the samples were macerated using n-hexane, ethyl acetate, and ethanol, respectively. Preliminary cytotoxicity test toward extract from control sample against mouse leukemia L1210 cells revealed that the ethyl acetate extract was the most active extract inhibiting the growth of cells with an IC50 value of 16.6 µg/mL, followed by ethanol extract (18.8 µg/mL) and n-hexane extract (42.7 μg/mL). Fractionation using a chromatography column of the ethyl acetate extract resulted in seven fractions denoted as F1-F7. The cytotoxicity test of the seven fractions against mouse leukemia L1210 cells showed that fraction 3 (F3) was the most active fraction with an IC50 value of 10.0 μg/mL, followed by F7 (11.2 μg/mL), F6 (11.8 μg/mL), F5 (12.0 μg/mL), F1 (13.2 μg/mL), F4 (14.5 μg/mL), and F2 (27.8 μg/mL), respectively. Based on these results, all irradiated samples were then extracted, fractionated, and tested for cytotoxicity in a similar manner. The result showed that irradiation of samples under doses up to 10 kGy can be used to preserve Curcuma zanthorrhiza simplicia without damaging its efficacy. To ensure that the irradiation dose of 10 kGy did not reduce anticancer activity, the F3 from the irradiated sample at a dose of 10 kGy was also examined of its in-vitro antiproliferative activity using HUT78, A549, HeLa, and THP1 human cancer cell lines. The results showed that irradiation of the sample at a dose of 10 kGy reduced the antiproliferative activity of F3 against HUT78 (32 %), A549 (48 %), HeLa (42 %), and THP1 (31 %). However, its reduction did not eliminate its antiproliferative activities. These results indicated that the preservation of simplicia using radiation can be done at a maximum radiation dose of 10 kGy by modifying the concentration of simplicia in the fabrication process of herbal medicine formulation.

Study of Sulphate Origin in Shallow Groundwater in the Vicinity of Bantar Gebang-Bekasi Landfill Using Sulphur-34 and Oxygen-18 E.R. Pujiindiyati; Syafalni Syafalni
Atom Indonesia Vol 33, No 2 (2007): July 2007
Publisher : PPIKSN-BATAN

Bantar Gebang-Bekasi landfill-West Java has caused a social impact due to the possibility of groundwater contamination. An investigation to trace sulphate origin in shallow groundwater in surrounding of Bantar Gebang -Bekasi landfill had been done. The methods were related to Rafter for extraction of CO2 and Robinson-Kusakabe for extraction of SO2 gas. Both gases were injected to mass spectrometer for measuring of δ 18O (SO42-) and δ 34S (SO42-). The results showed that a mixing of sulphate from leachate water to shallow groundwater had occurred. The more enriched value of δ 34S (SO42-) as much as 8.87 o/oo in leachate water compared to shallow groundwater having that value of 3.92o/oo to 6.66 o/oo might be caused by rapidly growth of sulphate reducing bacteria. The source of oxygen in sulphide oxidation dominantly came from atmosphere whereas percentage of H2O supplying oxygen was 0-25% for groundwater and 40% for leachate water. The extend of this value in leachate water might be caused by higher degree of bacteria, higher content of heavy metals and lower content of dissolved atmospheric oxygen.

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