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Atom Indonesia Journal

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Published by Badan Tenaga Nuklir Nasional

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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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Fungal Population and Aflatoxin Contamination on Stored Gamma-Irradiated Nutmeg (Myristica fragrans) Kernels K. Nurtjahja; O.S. Dharmaputra; W.P. Rahayu; R. Syarief
Atom Indonesia Vol 44, No 2 (2018): August 2018
Publisher : PPIKSN-BATAN

A study on the effectivenessof gamma irradiation at doses of 5 and 10 kGy on fungal population, Aspergillus flavus strains, and aflatoxin B1 contamination on stored nutmeg kernels was conducted. The kernels were collected from seeds in a period of one week from the ground at North Sulawesi Province, Indonesia.Dried shelled kernels with ±10 %moisture content, packed in polyethylene bags at 2.1 kg/bag, were irradiated at 5 and 10 kGy and stored at ambient temperature (28°C) for 2 and 4 months. Kernel moisture content, fungal population, and aflatoxin B1 were determined before and after irradiation, and after 2 and 4 months of storage. Results showed that fungal population was reduced with the increasing irradiation dose. Five species of fungi were isolated, i.e., Aspergillus flavus, A. niger, Cladosporium cladosporioides, Eurotium chevalieri, and Penicillium citrinum. A total of twelve A. flavus strains were isolated, five strains from unirradiated kernels and five and two strains from irradiated kernels at doses 5 and 10 kGy, respectively. Among these strains, 58 % were capable of producing L sclerotia and 25 % were identified as toxigenic. Kernel moisture during storage was 7.3 % and no aflatoxin B1 was detected before and after irradiation, and after2 and 4 months of storage duration.

The Effect of Urea Molasses Multi-Nutrient and Medicated Block for Beef Cattle, Beef and Dairy Cow Suharyono Suharyono; H. Sutanto; Y. Purwanti; Martanti Martanti; A. Agus; U Ristianto
Atom Indonesia Vol 40, No 2 (2014): August 2014
Publisher : PPIKSN-BATAN

Urea molasses multi-nutrient block (UMMB) is a feed supplement and one of the best formulas constructed by the National Nuclear Energy Agency (BATAN). This supplement contains soya bean meal (SBM) and has been developed using different protein sources, such as Enterolobium cyclocarpum (Ec), soya bean waste sauce (SBWs), wheat pollard (WP) and WP bypass protein (WPBp). It has also been developed using medicated block (MB). The objective is to introduce the P-32 tracer for obtaining a new feed supplement, to apply UMMB-SBM on beef cattle for fattening, and to test UMMB-MB on cows in the field. Parameters measured include microbial protein synthesis (MPS) in rumen liquid, daily live weight gain (DLWG), milk production and total count of worm in feces. Statistical analysis used were Latin squares, Student’s t-test, and completely randomized design. The UMMB-SBM was better than UMMB-Ec, UMMB-SBWs, and UMMB-WP, because it was able to increase MPS by up to 205.67%, superior to the other feed supplements (51.01%, 34.04%, and 73.94% respectively). On the other hand, with UMMB-WPBp supplementation, MPS was enhanced by 425.27%. The UMMB-SBM was able to increase DLWG by 0.34, 0.30, 0.38 and 0.36 kg/(animal d) on Bali cattle, Ongole, Simmental, and Frisian Holstein cross breed respectively. The increase of cost benefit ratio was affected by increasing DLWG. These values were 1:1.89; 1: 1.34; 1:1.45 and 1:1.35 respectively. UMMB-MB-C. aeruginosa and albendazole increased milk production by 4.23% and 46.56% respectively. In the first communal group, beef cows that received UMMB-MB albendazole were able to increase feed consumption, including dry matter, organic matter, crude protein, and total digestible nutrient, at P<0.05.The second communal group, feed consumption significantly differed from control at P<0.05 on crude protein, and total digestible nutrient. UMMB-MB tends to be effective only for ten days on the total amount of egg worm in feces.Received: 28 January 2014; Revised: 13 June 2014; Accepted: 23 June 2014

Piping Flexibility Analysis of the Primary Cooling System of TRIGA 2000 Bandung Reactor due to Earthquake H.P. Rahardjo
Atom Indonesia Vol 37, No 2 (2011): August 2011
Publisher : PPIKSN-BATAN

Earthquakes in a nuclear installation can overload a piping system which is not flexible enough. These loads can be forces, moments and stresses working on the pipes or equipments. If the load is too large and exceed the allowable limits, the piping and equipment can be damaged and lead to overall system operation failure. The load received by piping systems can be reduced by making adequate piping flexibility, so all the loads can be transmitted homogenously throughout the pipe without load concentration at certain point. In this research the analysis of piping stress has been conducted to determine the size of loads that occured in the piping of primary cooling system of TRIGA 2000 Reactor, Bandung if an earthquake happened in the reactor site. The analysis was performed using Caesar II software-based finite element method. The ASME code B31.1 arranging the design of piping systems for power generating system (Power Piping Code) was used as reference analysis method. Modeling of piping systems was based on the cooling piping that has already been installed and the existing data reported in Safety Analysis Reports (SARs) of TRIGA 2000 reactor, Bandung. The quake considered in this analysis is the earthquake that occurred due to the Lembang fault, since it has the Peak Ground Acceleration (PGA) in the Bandung TRIGA 2000 reactor site. The analysis results showed that in the static condition for sustain and expansion loads, the stress fraction in all piping lines does not exceed the allowable limit. However, during operation moment, in dynamic condition, the primary cooling system is less flexible at sustain load, ekspansi load, and combination load and the stress fraction have reached 95,5%. Therefore a pipeline modification (rerouting) is needed to make pipe stress does not exceed the allowable stress. The pipeline modification was carried out by applied a gap of 3 mm in the X direction of the support at node 25 and eliminate the support at the node 30, also a gap of 3 mm was applied in X and Z directions of the support at the node 155. The axial force (FY) that occurred in the pump outlet nozzle (dia. 4 in.) of PriPump line have also exceeded the allowable limit that lead to the pump nozzle failure during an earthquake of Lembang fault. The modifications is necessary to be applied on the cooling system for PriPump line so the nozzle would not receive the force that exceed the allowable limits. The modification can be done by removing the support at node 105 and node 135 so the primary cooling system piping of Bandung TRIGA 2000 reactor would be safe to operate during an earthquake originated from Lembang fault. Received: 20 November 2010; Revised: 18 July 2011; Accepted: 20 July 2011

Acknowledgement Atom Indonesia Vol 44 No 3 ack ack
Atom Indonesia Vol 44, No 3 (2018): December 2018
Publisher : PPIKSN-BATAN

Pseudospin Symmetry of the Position-Dependent Mass Dirac Equation for the Hulthén Potential and Yukawa Tensor Interaction A.N. Ikot; C.N. Isonguyo; J.D. Olisa; H.P. Obong
Atom Indonesia Vol 40, No 3 (2014): December 2014
Publisher : PPIKSN-BATAN

This paper presents approximate analytical solutions of the Dirac equation for the Hulthén potential with position-dependent mass within the framework of pseudospin symmetry limit using the Nikiforov-Uvarov method. The results showed the relativistic energy spectrum and the corresponding un-normalized wave function expressed in terms of the Jacobi polynomials.Received: 30 September 2014; Revised: 29 December 2014: 31 December 2014

Formulation of Oil-in-Water Cream from Mangosteen (Garcinia mangostana L.) Pericarp Extract Preserved by Gamma Irradiation E. Isabella; T. Pohan
Atom Indonesia Vol 39, No 3 (2013): December 2013
Publisher : PPIKSN-BATAN

The aim of this researchwas to formulate mangosteen (Garcinia mangostana L.) pericarp extract into oil-in-water (O/W) cream which stable and durable. In order to improve the shelf life durability of the formula, the irradiation of formula using gamma rays from cobalt-60 was done. The concentrations of extract were varied to 1, 2 and 3% and were irradiated by gamma rays with doses of 5, 7.5 and 10 kGy. Physicochemical and microbiological properties of these formulas were carried outfor 90 days stored at 30 ± 2°C and 40 ± 2°C. It was found that both of physicochemical and microbiological properties of the formulas were changed by extract concentrations and after irradiation. The irradiated formulas with dose up to 7.5 kGy, which were stored at 30 ± 2°C and 40 ± 2°C, presented acceptable physicochemical and microbiological stability for at least 90 days. Analysis by TLC (Thin Layer Chromatography)-densitometry to study decomposition of G. mangostana pericarp extract cream formulas was carried out 24 h after preparation and 90 day after storage. The result of TLC-densitometry analysis showed that G. mangostana pericarp extract in the cream formulas did not develope significant decomposition after 90 days of storage. Decontamination dose for all formulas was found to be about 7.5 kGy. At this condition, the bacteria and mold-yeast have been killed, without reducing the antioxidant activity.Received: 24 November 2013; Revised: 20 December 2013; Accepted: 26 December 2013

Expression of γ-H2AX, 53BP1 and Micronuclei as Genome Damage Biomarker of Population in Keang and Salumati Village, Mamuju West Sulawesi Province A.D. Pratiwi; I.K.H. Basri; S. Purnami; M. Syaifudin; D. Tetriana; D. Yusuf; T. Rahardjo; S. Nurhayati; N. Rahajeng; Y.U. Anggraito; I. Kashiwakura
Atom Indonesia Vol 45, No 2 (2019): August 2019
Publisher : PPIKSN-BATAN

The residents living in high background radiation area have risk to be exposed by ionizing radiation that also potentially cause their DNA damage. The aim of this study was to determine the expression of γ-H2AX, 53BP1 foci and micronuclei in the residentswho live in high background radiation area of Salumati village, Mamuju, West Sulawesi, Indonesia. Twenty one blood samples which consist of 11 from the study area and 10 from control were assessed for their expression of γ-H2AX and 53BPI foci by using specific antibodies and observed under fluorescence microscope whereas micronuclei was detected after being cultured and giemsa stainedaccording to standard procedures. Results showed that both γ-H2AX and 53BP1foci from high background area was lower than that of control area (0.37±0.24vs 0.19±0.11 (p=0.03) for γ-H2AX and 0.61±0.30vs 0.31±0.12 for 53BP1 (p=0.01)). The mean of micronuclei frequency in exposed area was 0.02 (0,01-0,03) while in control area was 0.02 (0.003-0.02). There was statistical significant in corellation between both γ-H2AX, 53BP1 foci with micronuclei index in exposed area (p=0.02, p=0,04 respectively).In conclusion,there was a positive correlation between γ-H2AX and 53BP1 foci to micronuclei and this might be a clue of the occurrence of genome repairing mechanism caused by natural radiation at low dose chronical exposure in thestudied area.

Optimization of Residual Stress of High Temperature Treatment Using Genetic Algorithm and Neural Network M. Susmikanti; A. Hafid; J.B. Sulistyo
Atom Indonesia Vol 41, No 3 (2015): December 2015
Publisher : PPIKSN-BATAN

In a nuclear industry area, high temperature treatment of materials is a factor which requires special attention. Assessment needs to be conducted on the properties of the materials used, including the strength of the materials. The measurement of material properties under thermal processes may reflect residual stresses. The use of Genetic Algorithm (GA) to determine the optimal residual stress is one way to determine the strength of a material. In residual stress modeling with several parameters, it is sometimes difficult to solve for the optimal value through analytical or numerical calculations. Here, GA is an efficient algorithm which can generate the optimal values, both minima and maxima. The purposes of this research are to obtain the optimization of variable in residual stress models using GA and to predict the center of residual stress distribution, using fuzzy neural network (FNN) while the artificial neural network (ANN) used for modeling. In this work a single-material 316/316L stainless steel bar is modeled. The minimal residual stresses of the material at high temperatures were obtained with GA and analytical calculations. At a temperature of 6500C, the GA optimal residual stress estimation converged at –711.3689 MPa at adistance of 0.002934 mm from center point, whereas the analytical calculation result at that temperature and position is -975.556 MPa . At a temperature of 8500C, the GA result was -969.868 MPa at 0.002757 mm from the center point, while with analytical result was -1061.13 MPa. The difference in residual stress between GA and analytical results at a temperatureof6500C is about 27 %, while at 8500C it is 8.67 %. The distribution of residual stress showed a grouping concentrated around a coordinate of (-76; 76) MPa. The residuals stress model is a degree-two polynomial with coefficients of 50.33, -76.54, and -55.2, respectively, with a standard deviation of 7.874.Received: 09 October 2014; Revised: 21 April 2015; Accepted: 16 June 2015

Prospect on Desalination and Other Non-Electric Applications of Nuclear Energy In Indonesia G.R. Sunaryo
Atom Indonesia Vol 33, No 1 (2007): January 2007
Publisher : PPIKSN-BATAN

As the standard of living increases globally, the need for fresh water and industrial products are also increasing; they require energy for production and hence, the demand for energy–both electric and non-electric, is also increasing. This trend also happens in Indonesia as an archipelagic country. In an effort to meet the current and future water and energy demands, Indonesia is now planning to utilize nuclear power for not only electricity but also producing fresh water through desalination process named Nuclear Desalination. Feasibility and option studies have been carried out by Indonesian National Nuclear Energy Agency, locally called Badan Tenaga Nuclear Nasional or ‘BATAN’ since 1995, and also in collaboration with Korean Atomic Energy & Research Institute (KAERI) since 2002. The study concluded that it would be technically feasible to build desalination plants on selected sites pending further economic assessments. BATAN also has a duty to study the future Nuclear Power Plant (NPP) that can be coupled to various industrial processes. From the literature study it seems that HTGR (High Temperature Gas Cooled Reactor) is the promising one because of its huge range steam temperature. Beside that study, BATAN also has (1) developed a small scale Mechanical Vapor Compression system to study and establish vital parameters that will affect system performance, water chemistry, corrosion, scaling, evaporation, condensation, and choice of materials and (2) basic research on hydrogen production through the Iodine Sulfur (IS) process.

A Backward Method to Estimate the Dai-ichi Reactor Core Damage Using Radiation Exposure in the Environment P.M. Udiyani; S. Kuntjoro; S. Widodo
Atom Indonesia Vol 42, No 2 (2016): August 2016
Publisher : PPIKSN-BATAN

The Fukushima accident resulted in the melting of the reactor core due to loss of supply of coolant when the reactor stopped from operating conditions. The earthquake and tsunami caused loss of electricity due to the flooding that occurred in the reactor. The absence of the coolant supply after reactor shutdown resulted in heat accumulation, causing the temperature of the fuel to rise beyond its melting point. In the early stages of the accident, operator could not determine the severity of the accident and the percentage of the reactor core damaged. The available data was based on the radiation exposure in the environment that was reported by the authorities. The aim of this paper is to determine the severity of the conditions in the reactor core based on the radiation doses measured in the environment. The method is performed by backward counting based on the measuring radiation exposure and radionuclides releases source term. The calculation was performed by using the PC-COSYMA code. The results showed that the core damage fraction at Dai-ichi Unit 1 was 70%, and the resulting individual effective dose in the exclusion area is 401 mSv, while the core damage fraction at Unit 2 was 30%, and the resulting individual effective dose was 99.1 mSv, while for Unit 3, the core damage fraction was 25% for an individual effective dose of 92.2 mSv. The differences between the results of the calculation for estimation of core damage proposed in this paper with the previously reported results is probably caused by the applied model for assessment, differences in postulations and assumptions, and the incompleteness of the input data. This difference could be reduced by performing calculations and simulations for more varied assumptions and postulations.Received: 30 October 2015 ; Revised: 29 March 2016; Accepted: 31 March 2016

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