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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 452 Documents
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Theoretical Inspecting of 211At Radionuclide via Coupled-Channel Model for Fusion Reaction of Stable Nuclei Z. M. Cinan; T. Başkan; B. Erol; A. H. Yılmaz
Atom Indonesia Vol 47, No 3 (2021): December 2021
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2021.1115

Abstract

This work has been carried out to obtain and inspect of 211At radionuclide through fusion reaction. Cross-sections for fusion reaction have been calculated with different interaction combinations and excitations for 19F + 192Os and 18O + 193Ir  reactions. All calculations have been performed on NRV Knowledge Base, CCFULL code, and Wong’s Formula. Firstly, we assigned reaction parameter values taking into account the compatibility with the experimental data 19F + 192Os reaction. Afterward, to enrich studies on 211At radionuclide, we proposed 18O + 193Ir reaction which did not have experimental data in the literature with the method and parameter values we determined. We examined the effects of phonon excitations in projectile and target nuclei on fusion cross sections and barrier distributions. With our research, we showed that the coupled channel model and the calculation codes used to explain the fusion cross-section data and barrier distributions well. This research sheds light on the importance of analyzing important medical radionuclides such as 211At by heavy-ion fusion reactions and encourages new researches.
Distribution of 137Cs In the Surface Soil of Serpong Nuclear Site E. Lubis
Atom Indonesia Vol 37, No 2 (2011): August 2011
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2011.63

Abstract

The distribution of 137Cs in the surface soil layer of Serpong Nuclear Site (SNS) was investigated by field sampling. The Objectives of the investigation is finding the profile of 137Cs distribution in the surface soil and the Tf value that can be used for estimation of radiation dose from livestock product-man pathways. The results indicates that the 137Cs activity in surface soil of SNS is 0.80 ± 0,29 Bq/kg, much lower than in the Antarctic. The contribution value of 137Cs from the operation of G.A.Siwabessy Reactor until now is undetectable. The Tf of 137Cs from surface soil to Panisetum Purpureum, Setaria Spha Celata and Imperata Cylindrica grasses were 0.71 ± 0.14, 0.84 ± 0.27 and 0.81 ± 0.11 respectively. The results show that value of the transfer factor of 137Cs varies between cultivated and uncultivated soil and also with the soils with thick humus. Received: 18 May 2010; Revised: 13 July 2011; Accepted: 20 July 2011
Glucose Metabolism in Sheep Fed Grass Supplemented with Gliricidia Sepium Y. Widiawati; E. Teleni; Suharyono Suharyono
Atom Indonesia Vol 40, No 3 (2014): December 2014
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2014.330

Abstract

The limiting factor on improving ruminant production for most of the available feed in developing countries are low in quality. Therefore high fibre diet must be supplemented by high nutritivefeed such as leguminous trees that much available in those regions. Gliricidia sepium was one of very potential candidates. Glucose as a major energy source in fed animals required precursor in form of propionat and amino acids from diet. Those precursors might be supplied by these legume leaves. The aim of this research was to investigate the glucose metabolism in the sheep fed grass supplemented by Gliricidia sepium. Fifteen sheeps (18 months old) were used in the experiment. Theseare were divided into three groups that fed by experimental diet of Mitchell grass (MG group), Gliricidia(GS group), and MG supplemented with GS (MGGS group). D-[U-14C]glucoseinfusate was infused continuously through the left jugular venous catheter of each animal to measure glucose metabolism in those sheeps. The measurements were done on feed utilisation and glucose metabolism. The results indicated that there was an improvement in efficiency of feed utilisation in the MGGS group as reflected by lower feed conversion ratio by the group. Plasma glucose concentration profile per unit of OM intake were similar for GS and MGGS groups, but higher than that in the MG group (P<0.01). Glucose entry rate (GER) increased in MG group through GS to the MGGS group, while N retention accordingly was increased. It can be concluded that theutilization of GS by the ruminant animal could be improved by feeding it with a low quality feed at a ratio of 40:60 (GS:Low quality feed) to achieve an NI:DOMI ratio of 0.03 - 0.04. This improvement would be manifested in increasing DOMI, with subsequent increase in GER or net protein deposition as might be expressed in positive N retention. Received: 8 October 2014; Revised: 12 December 2014; Accepted: 24 December 2014  
Theoretical and Practical Aspects of ‘Wasteless’ Nuclear Energy P. Anggraita
Atom Indonesia Vol 34, No 2 (2008): July 2008
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2008.102

Abstract

The problem associated with the current NPP is the generation of nuclear waste and some elements in the waste have very long time of radioactivity. This paper reviews some concepts of nuclear energy generation with less nuclear waste. A concept of accelerator driven system (ADS) or energy amplifier (EA) was proposed by Carlo Rubbia, recipient of 1984 Nobel Prize in particle physics. The system is supposed to generate nuclear energy with radioactive waste of much less and shorter lifetime than those generated by present generation of nuclear power reactors. Less radioactive waste will also be generated by fusion reactions, either in hot fusion of high temperature plasma confined in a very strong magnetic field, or in cold fusion conceptually happens in muon-catalytic and lattice-trap fusions. A concept of neutronless nuclear reaction, hence activating no radioisotopes, to generate nuclear power was proposed. Present nuclear power reactors based on fission are also the source of very large number of electron neutrinos, which can be used to study neutrino oscillations.
Comparison of Radiosensitivity of Human Chromosomes 1, 2 and 4 from One Healthy Donor D. Ramadhani; S. Purnami; M. Yoshida
Atom Indonesia Vol 42, No 2 (2016): August 2016
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2016.505

Abstract

In general, it was assumed that the chromosome aberration induced by ionizing radiation is proportional to the chromosome size. From this viewpoint, the higher chromosome size, the more resistant to radiation. However, different opinions, in which chromosomes are particularly sensitive or resistant to radiation, are also still followed until now. Here in this research, we compared the chromosome sensitivity between chromosomes number 1, 2, and 4 using the FISH (fluorescence in situ hybridization) technique. From this research, we expect that the information obtained could show clearly whether a longer chromosome is more frequently involved in translocations and also more resistant to radiation than a shorter one. The type of chromosome aberration considered was limited only to translocation and we used one sample donor in order to avoid donor variability. The whole blood from a healthy female was irradiated with γ-rays with doses of 1, 3 and 5 Gy, respectively. Isolated lymphocytes from the whole blood were then cultured for 48 hours. After the culture process was completed, preparations of harvest and metaphase chromosomes were carried out. Chromosomes 1, 2, and 4 were stained with different fluorochromes. The translocation of each chromosome at each dose point was subsequently evaluated from 50 images obtained from an automated metaphase finder and capturing system. An additional analysis was performed to identify which chromosome arm was more frequently involved in translocation. Further analyses were also conducted with the aim of determining which chromosome band had a higher frequency of radiation-induced breakage. The experimental results showed that chromosome number 4 was more frequently involved in translocations compared to chromosomes 1 and 2 at 5 Gy. In contrast, at doses of 1 and 3 Gy translocations involving chromosomes number 1 and 2 were more numerous compared to the ones involving chromosome 4. However, if the number of translocation was accumulated for all the doses applied, the chromosome number 4 was the chromosome most frequently involved in translocations. Breakpoint analysis revealed that in chromosome 1, chromosome 2, and chromosome 4, the highest chromosome bands as break position were in band q32, p13, and q21, respectively. It can be concluded that chromosome 4 is more sensitive to radiation in all doses point, despite having less DNA content than chromosomes  1 and 2. Thus, it was showed that our research cannot support the general assumption about chromosome aberration induced by radiation being proportional to DNA content.Received: 29 September 2015; Revised: 29 March 2016; Accepted: 31 March 2016
Analysis of Neutron Flux Distribution in Rsg-Gas Reactor With U-Mo Fuels Taswanda Taryo; T.M. Sembiring
Atom Indonesia Vol 30, No 1 (2004): January 2004
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2004.212

Abstract

The use of U-Mo fuels in research reactors seems to be promising and, recently, world researchers have carried out these such activities actively. The National Nuclear Energy Agency (BATAN) which owns RSG-GAS reactor available in Serpong Research Center for Atomic Energy should anticipate this trend. It is, therefore, this research work on the use of U-Mo fuels in RSG-GAS reactor should be carried out. The work was focused on the analysis of neutron flux distribution in the RSG-GAS reactor using different content of molybdenum in U-Mo fuels. To begin with, RSG-GAS reactor core model was developed and simulated into X, Y and Z dimensions. Cross section of materials based on the developed cells of standard and control fuels was then generated using WIMS-D5-B. The criticality calculations were finally carried out applying BATAN-2DIFF code. The results showed that the neutron flux distribution obtained in U-Mo-fuel-based RSG-GAS core is very similar to those achieved in the 300-gram sillicide-fuel-based RSG-GAS reactor core. Indeed, the utilization of the U-Mo RSG-GAS core can be very similar to that of the high-density sillicide reactor core and even could be better in the future.
Trial Production of Surgical Gloves from Irradiated Natural Rubber Latex on Factory Scale M. Utama; Herwinarni Herwinarni; M. Sumarti; Siswanto Siswanto; Suharyanto Suharyanto; S Ruslim
Atom Indonesia Vol 31, No 2 (2005): July 2005
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2005.362

Abstract

Trial production of surgical gloves from irradiated natural rubber latex at the PT. Laxindo Utama Serang Banten glove factory has been carried out. The variation of heating temperature and leaching time during processing were evaluated. The physical and mechanical properties and the protein allergen respond of surgical gloves using ELISA method were measured. The results showed that the physical and mechanical of surgical gloves such as tensile strength, modulus, and elongation at break arefound to meet the requirements of the ISO or SNI standard for surgical gloves. While the allergic response through clinical tested latex-sensitive protein allergen known as ELISA test is found to be negative.
Conceptual Design Study of 13 MeV Proton Cyclotron Silakhuddin Silakhuddin; S. Santosa
Atom Indonesia Vol 38, No 1 (2012): April 2012
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2012.135

Abstract

A study to determine the conceptual design of a 13 MeV proton cyclotron for PET (Positron Emission Tomography) facility has been carried out. Based on studies on reactions of PET radioisotopes production, reaction cross-sections and some design references, a design of the proton cyclotron is proposed. The design criteria for the main components are decided using empirical and semitheoretical methods, as well as by referring to data regarding cyclotrons for PET production. The empirical method was carried out by using some data from operational experiences of BATAN cyclotron at Serpong, while the semitheoretical method was carried out by using the commonly used equations of cyclotron basic theory. The general layout of components and the main components, namely the ion source, the RF dees, the magnet, and the extractor are discussed. Based on the calculations and on the data used, the cyclotron is designed as a negative ion acceleration cyclotron with internal ion source. The designated proton energy and beam currents are 13 MeV and 50 µA. Its magnetic field is in the relativistic mode with sectors on the pole. The magnetic field intensity at the extraction radius is 12.745 kG and in the innermost radius is 12.571 kG. The magnetic poles consist of four sectors to make adequate space for components placement such as dees, ion source, extractor and beam probe. The dee angle is 430. The dee operates at 78 MHz on the fourth harmonic. A multifoil extractor is chosen to obtain an efficient operation.Received: 28 April 2011; Revised: 27 March 2012; Accepted: 30 April 2012
Conductivity and Structure of Superionic Composite (AgI)0.6(NaPO3)0.4 E Kartini; T Sakuma; A Purwanto; T Kamiyama; MF Collins
Atom Indonesia Vol 31, No 1 (2005): January 2005
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2005.125

Abstract

Superionic conductors are of considerable interest from both application and fundamental points of view. Superionic solid electrolytes can be used for batteries, fuel cells and sensors. We have used melt quenching to make a new superionic composite (AgI)0.6(NaPO3)0.4 which exhibits an ionic conductivity of about 2 x 10-4 S/cm at ambient temperature. The conductivity of crystalline AgI and NaPO3 glass are lower of orders of magnitude. (AgI)0.6(NaPO3)0.4 is a composite material containing both crystalline and glass phases. The paper presents the conductivity as a function of temperature measured by impedance spectroscopy and the crystal structure performed by a high resolution powder diffractometer, VEGA at the Neutron Science Laboratory (KENS), KEK, Japan.
RIA Analysis of Unprotected TRIGA Reactor M.H. Altaf; S.M. Tazul Islam; N.H. Badrun
Atom Indonesia Vol 43, No 2 (2017): August 2017
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2017.568

Abstract

An RIA (reactivity initiated accident) analysis has been carried out for the TRIGA Mark II research reactor considering both step and ramp reactivity ranges within 0.5 % dk/k (< $1) to 2.0 % dk/k (>$2). The insertion time was set at 10 s. Based on the fact that a reactor becomes unprotected if scram does not work at the event of danger, to define unprotected conditions, the time to actuate scram (trip) was taken as close to total simulation time. In this long duration of scram inactivity, it is obtained from the present analysis that the reactor remained safe to up to 1.8 % dk/k ($2.57) for step reactivity and 1.99 % dk/k ($2.84) for ramp reactivity. In addition to negative temperature coefficient of reativity, probably the longer time of reactivity insertion keeps TRIGA safe even at larger magnitudes of reactivity during unprotected reactor transients. Coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/R has been utilized for this work. It appears that EUREKA-2/RR predicts the sequence of unprotected transient scenario of TRIGA core with good approximation and the results will definitely be helpful for the reactor operators.

Page 37 of 46 | Total Record : 452

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