PubMed | National Nuclear Energy Agency of Indonesia and International Islamic University Malaysia
Type: Journal Article | Journal: Tropical life sciences research | Year: 2014
Three Malaysian ginger cultivars (Bukit Tinggi, Tanjung Sepat and Sabah) were collected and examined for genetic polymorphisms using microsatellite DNA primers. The single microsatellite oligonucleotide primers (CATA)5, (GATA)5 and (GAC)6 were used in polymerase chain reactions (PCRs). These PCR reactions produced 7 polymorphic bands with an average of 2.334 polymorphic bands per primer, leading to an average polymorphism rate of 17.9%. Cluster analysis revealed 87.50% similarity between Bukit Tinggi and Tanjung Sepat, 64.27% similarity between Bukit Tinggi and Sabah and 56.25% similarity between Tanjung Sepat and Sabah. DNA sequencing of the polymorphic PCR products of Tanjung Sepat ginger revealed the characteristic features of a putative new gene: a core promoter sequence, an enhancer and a transcription start site. Cluster analysis using the unweighted pair group method with arithmetic average (UPGMA) was used to construct a phylogenetic tree, which indicated that Bukit Tinggi ginger is genetically more closely related to Tanjung Sepat ginger than to Sabah ginger. Based on the results of this study, we concluded that there is genotypic variation among ginger cultivars, and the microsatellite DNA primers described here are useful for detecting polymorphic DNA in Malaysian ginger cultivars. Additionally, these microsatellite DNA primers may be used as molecular markers for discriminating among select Malaysian ginger cultivars.
Dharaiya N.,Veer Narmad South Gujarat University |
Patriati A.,National Nuclear Energy Agency of Indonesia |
Kuperkar K.,Veer Narmad South Gujarat University |
Putra E.G.R.,National Nuclear Energy Agency of Indonesia |
Bahadur P.,Veer Narmad South Gujarat University
Colloids and Surfaces A: Physicochemical and Engineering Aspects | Year: 2012
Aqueous micellar solutions of cationic gemini surfactants belonging to 12- s-12 series (where s= 4, 5, 6) in presence of p-toluidine (PTD) exhibit a noticeable micellar growth/transition from viscometric and scattering studies. The dynamic light scattering (DLS) and small angle neutron scattering (SANS) showed pronounced micelle growth around pH 5-6 for gemini with varying spacer. The possible reason is attributed in terms of adsorption, surface charge density, chemical environment and orientation of PTD molecules in the micelle. The probable location of PTD in micelle is successfully correlated by the significant positive crosspeaks obtained from two-dimensional nuclear Overhauser effect spectroscopy (2D-NOESY). © 2011 Elsevier B.V.
Tandian N.P.,Bandung Institute of Technology |
Alkharboushi A.A.K.,Al Zawiya University |
Kamajaya K.,National Nuclear Energy Agency of Indonesia
IOP Conference Series: Materials Science and Engineering | Year: 2015
Natural convection heat transfer in vertical triangular sub-channel has important role in cooling mechanism of the APWR and the PHWR nuclear reactors. Unfortunately, natural convection correlation equations for such geometry are scarcely available. Recent studies showed that ZrO2-water nanofluid has a good prospect to be used in the nuclear reactor technology due to its low neutron absorption cross section. Although several papers have reported transport properties of ZrO2-water nanofluids, practically there is no correlation equation for predicting natural convection heat transfer in a vertical triangular sub-channel in ZrO2-water nanofluid. Therefore, a study for finding such heat transfer correlation equation has been done by utilizing Computational Fluid Dynamics software and reported in this paper. In the study, natural convection heat transfer in a vertical triangular sub-channel has been simulated at several values of heat transfer flux within 9.1 to 30.9 kW/m2 range and ZrO2concentrations of 0 (pure water), 0.27, and 3 volume-% of ZrO2. The study shows that the ZrO2 concentration has no significant influence to the natural convection heat transfer at those concentration levels. The obtained theoretical heat transfer correlation equations were verified through experiment, and they showed very similar results. The correlation equations are reported in this paper.
Susmikanti M.,Energy Informatics |
Dewayatna W.,National Nuclear Energy Agency of Indonesia
AIP Conference Proceedings | Year: 2013
One of the research activities to support the commercial radioisotope production program is a safety research target irradiation FPM (Fission Product Molybdenum). FPM targets form a tube made of stainless steel in which the nuclear degrees of superimposed high-enriched uranium. FPM irradiation tube is intended to obtain fission. The fission material widely used in the form of kits in the world of nuclear medicine. Irradiation FPM tube reactor core would interfere with performance. One of the disorders comes from changes in flux or reactivity. It is necessary to study a method for calculating safety terrace ongoing configuration changes during the life of the reactor, making the code faster became an absolute necessity. Neutron safety margin for the research reactor can be reused without modification to the calculation of the reactivity of the reactor, so that is an advantage of using perturbation method. The criticality and flux in multigroup diffusion model was calculate at various irradiation positions in some uranium content. This model has a complex computation. Several parallel algorithms with iterative method have been developed for the sparse and big matrix solution. The Black-Red Gauss Seidel Iteration and the power iteration parallel method can be used to solve multigroup diffusion equation system and calculated the criticality and reactivity coeficient. This research was developed code for reactivity calculation which used one of safety analysis with parallel processing. It can be done more quickly and efficiently by utilizing the parallel processing in the multicore computer. This code was applied for the safety limits calculation of irradiated targets FPM with increment Uranium. © 2013 AIP Publishing LLC.
Sembiring T.M.,National Nuclear Energy Agency of Indonesia |
Liem P.H.,NAIS Co. Inc.
ARPN Journal of Engineering and Applied Sciences | Year: 2016
An optimum fuel composition is a very important parameter in the operation of a pebble bed high temperature gas-cooled reactor (HTGR). In the present scoping study, the optimum ranges of heavy metal (HM) loading per pebble and the uranium enrichment are investigated. The HM loading range covers 4 to 10 g per pebble, while the uranium enrichment covers 5 to 20 w/o. Two fuel loading schemes typical to pebble-bed HTGRs are also investigated, i.e. the OTTO and multi-pass schemes. All calculations are carried out using BATAN-MPASS, a general in-core fuel management code dedicated for pebble-bed type HTGRs. The reference reactor design case is adopted from the German 200 MWth HTR-Module but with core height of half of the original design. Other design parameters follow the original HTR-Module design. The results of the scoping study show that, for both once-through-then-out (OTTO) and multi-pass fueling schemes, the optimal HM loading per pebble is around 7 g HM/ball. Increasing the uranium enrichment minimizes the fissile loading however higher enrichment than 15 w/o is not effective anymore. The multi-pass fueling scheme shows lower fissile loading requirement and a significantly lower axial power peaking than the OTTO scheme. It can be concluded that the optimum range of HM loading and uranium enrichment are found to be around 7 g per pebble and 15 w/o. In addition the multi-pass fueling scheme shows superior BURNUP and safety characteristics than the OTTO fueling scheme. © 2006-2016 Asian Research Publishing Network (ARPN).
Tjahaja P.I.,National Nuclear Energy Agency of Indonesia |
Sukmabuana P.,National Nuclear Energy Agency of Indonesia |
Roosmini D.,Bandung Institute of Technology
International Journal of Phytoremediation | Year: 2015
Soil contamination with radiocaesium is a significant problem at any countries when a nuclear accident occurred. Recently, phytoextraction technique is developed to remediate the contaminated environment. However, the application is limited by the availability of the contaminant for root uptake. Therefore, a green house trial experiment of soil amendment with ethylene diamine tetraacetic acid (EDTA) has been conducted to examine 134Cs availability for root uptake. Two groups of Indian mustard (Brassica juncea) were cultivated in 134Cs contaminated soil. The soil in the first group was treated with EDTA amendment, while the other was not. Plant growth was observed gravimetrically and the 134Cs concentration in soil as well as plants were determined using gamma spectrometry. The plant uptake capacity was determined as transfer factor (Fv), and the Fv values of 0.22 ± 0.0786 and 0.12 ± 0.039 were obtained for the soil treated with and without EDTA amendment, respectively. The phytoextraction efficiency of the plant cultivated in 134Cs contaminated soil both with and without EDTA amendment was low. The EDTA amendment to the soil seems to enhance the 134Cs availability for root uptake of Indian mustard and can still be considered to assist the field phytoremediation of contaminated soil. © 2015, Copyright © Taylor & Francis Group, LLC.
Susmikanti M.,National Nuclear Energy Agency of Indonesia |
Sulistyo J.B.,National Nuclear Energy Agency of Indonesia
Proceedings - 2014 International Conference on Advanced Informatics: Concept, Theory and Application, ICAICTA 2014 | Year: 2014
It is very important to analyze the characteristics of materials utilized especially in nuclear engineering. Many approximation of strain hardening phenomena or cooling process have been carried out by experiments, but many cases are costly. There are alternative such as modeling and simulation. The purpose of this study is to predict the properties of material due to a particular strain hardening process for molybdenum and austenitic stainless steel. The optimization for some load to get stress and strain was analysed by genetic algorithm. The strain hardening mechanism behavior under stress and strain of material can be modeled using Neural Network with Backpropagation. Levenberg-Marquardt was selected to reach convergence rapidly. The true strain and stress of molybdenum converges to 0.997 and 60489.821 psi. For the austenitic steel are stabilizes to 0.809 and 158255.290 psi. The estimates mean of an exponentially distributed of molybdenum is 4.5667 and austenitic steel is 4.1667. © 2014 IEEE.
Umar E.,National Nuclear Energy Agency of Indonesia |
Fiantini R.,National Nuclear Energy Agency of Indonesia
AIP Conference Proceedings | Year: 2010
To accomplish safety requirements, a set of actions has to be performed following the recommendations of the IAEA safety series 35 applied to research reactor. Such actions are considered in modernization of the old system, improving the core cooling system and safety evaluations. Due to the complexity of the process and the difficulty in putting the apparatus in the reactor core, analytical and experimental study on the determination of flow and temperature distribution in the whole coolant channel are difficult to be done. In the present work, a numerical study of flow and temperature distribution in the coolant channel of TRIGA 2000 has been carried out using CFD package. For this study, simulations were carried out on 3-D tested model. The model consists of the reactor tank, thermal and thermalizing column, reflector, rotary specimen rack, chimney, fuel element, primary pipe, diffuser, beam tube and a part of the core are constructed by 1.50 million unstructured tetrahedral cell elements. The results show that for the initial condition (116 fuel elements in the core) and for the inlet temperature of 24°C and the primary velocity of 5.6 m/s, there no boiling phenomena occur in the coolant channel. Due to this result, it is now possible to improve the core cooling system of TRIGA 2000 reactor. Meanwhile, forced flow from the diffuser system only affected the flow pattern in the outside of chimney and put on a small effect to the fluid flow's velocity in the inside of chimney. © 2010 American Institute of Physics.
Fiantini R.,National Nuclear Energy Agency of Indonesia |
Umar E.,National Nuclear Energy Agency of Indonesia
AIP Conference Proceedings | Year: 2010
Common energy crisis has modified the national energy policy which is in the beginning based on natural resources becoming based on technology, therefore the capability to understanding the basic and applied science is needed to supporting those policies. National energy policy which aims at new energy exploitation, such as nuclear energy is including many efforts to increase the safety reactor core condition and optimize the related aspects and the ability to build new research reactor with properly design. The previous analysis of the modification TRIGA 2000 Reactor design indicates that forced convection of the primary coolant system put on an effect to the flow characteristic in the reactor core, but relatively insignificant effect to the flow velocity in the reactor core. In this analysis, the lid of reactor core is closed. However the forced convection effect is still presented. This analysis shows the fluid flow velocity vector in the model area without exception. Result of this analysis indicates that in the original design of TRIGA 2000 reactor, there is still forced convection effects occur but less than in the modified TRIGA 2000 design. © 2010 American Institute of Physics.
Suhaemi T.,National Nuclear Energy Agency of Indonesia |
Syaukat A.,National Nuclear Energy Agency of Indonesia
AIP Conference Proceedings | Year: 2010
Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R&D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix. © 2010 American Institute of Physics.