http://ajstd.org/index.php/ajstd/issue/feed ASEAN Journal on Science and Technology for Development 2019-07-12T11:35:49+07:00 Widodo ajstd.journal@gmail.com Open Journal Systems <h2>About the <em>ASEAN Journal on Science &amp; Technology for Development</em></h2> <p style="font-weight: 300; font-size: 1.01rem;">Jointly published by the ASEAN Committee on Science and Technology and the Ministry of Research, Technology, and Higher Education of the Republic of Indonesia, the <em>ASEAN Journal on Science &amp; Technology for Development</em> (print ISSN 0217-5460; online ISSN 2224-9028) is a peer-reviewed open access journal focusing on the publication of articles that make positive, tangible contributions to science and technology in the ASEAN region. Its main aim is to promote andGoogle Scholar, ID Scopus, ResearchGate, Orcid), accelerate the discovery and ultimate ASEAN-wide application of scientific and technological innovations, the consequence of which should be greater prosperity for the people of Southeast Asia.</p> <p style="font-weight: 300; font-size: 1.01rem;">AJSTD covers a wide range of technology-related subjects in the context of ASEAN, including biotechnology, non-conventional energy research, materials science and technology, marine sciences, meteorology and geophysics, food science and technology, microelectronics and information technology, space applications, science and technology policy, and infrastructure and resources development.</p> <h2>About The ASEAN Committee on Science and Technology</h2> <p style="font-weight: 300; font-size: 1.01rem;">The ASEAN Committee on Science and Technology was established to strengthen and enhance the capability of ASEAN in science and technology so that it can promote economic development and help achieve a high quality of life for its people. Its terms and reference are:</p> <ul class="asean-terms" style="font-weight: 300; font-size: 1.01rem;"> <li class="show">To generate and promote development of scientific and technological expertise and manpower in the ASEAN region;</li> <li class="show">To facilite and accelerate the transfer of scientific and technological development among ASEAN countries and from more advanced regions of the world to the ASEAN region;</li> <li class="show">To provide support and assistance in the development and application of research discoveries and technological practices of endogenous origin for the common good, and in the more effective use of natural resources available in the ASEAN region and in general; and</li> <li class="show">To provide scientific and technological support towards the implementation of existing and future ASEAN projects.</li> </ul> <p style="font-weight: 300; font-size: 1.01rem;">Further information about the activities of ASEAN COST can be <a class="border-hover" href="http://astnet.asean.org/index.php?option=com_content&amp;view=categories&amp;id=8&amp;Itemid=130" target="_blank" rel="noopener">found on its website</a>.</p> http://ajstd.org/index.php/ajstd/article/view/558 Removal of Heavy Metals from an Actual Small Scale Gold Mining Wastewater by Sorption onto Cocopeat 2019-07-03T17:11:18+07:00 Jessie O. Samaniego josamaniego@pnri.dost.gov.ph Maria Antonia N. Tanchuling josamaniego@pnri.dost.gov.ph <p>Cocopeat, a by-product of coconut husk, was used as adsorbent material to remove mercury (Hg) and other heavy metals (As, Ba, Cd, Pb) from the wastewater gathered from the tailings collection tank of a ball mill facility at the small scale gold mining (SSGM) area in Camarines Norte province, Philippines. Batch sorption tests were carried out using actual wastewater samples with reduced suspended solids collected after 60 min of settling and without modifying the pH and other parameters to simulate the actual condition in the field. Batch tests of water samples with an initial pH of 7.30 and adsorbent dose of 1.0 g cocopeat/L were tested for Lagergren first-order, pseudo-second-order, intra-particle diffusion, and Freundlich models to evaluate kinetic parameters and adsorption isotherms. The removal efficiencies obtained for the heavy metals after the equilibrium time of 240 min were 97.14%, 94.74%, 10.00%, 66.67%, and 27.01% for Hg, As, Ba, Cd, and Pb, respectively. The pseudo-second order kinetics model represented well the adsorption process as demonstrated with its higher correlation coefficients among the models.</p> 2019-04-27T00:00:00+07:00 ##submission.copyrightStatement## http://ajstd.org/index.php/ajstd/article/view/519 Characteristics in Water Phantom of Epithermal Neutron Beam Produced by Double Layer Beam Shaping Assembly 2019-07-03T17:13:01+07:00 Bilalodin Bilalodin bilalodin.unsoed@gmail.com Gede Bayu Suparta pradiastuti_sari@ugm.ac.id Arief Hermanto pradiastuti_sari@ugm.ac.id Dwi Satya Palupi syahrul@ugm.ac.id Yohannes Sardjono pradiastuti_sari@ugm.ac.id <p>A Double Layer Beam Shaping Assembly (DLBSA) was designed to produce epithermal neutrons for BNCT purposes. The Monte Carlo N-Particle eXtended program was used as the software to design the DLBSA and phantom. Distribution of epithermal neutron and gamma flux in the DLBSA and phantom and absorbed dose in the phantom were computed using the Particle and Heavy Ion Transport code System program. Testing results of epithermal neutron beam irradiation of the water phantom showed that epithermal neutrons were thermalized and penetrated the phantom up to a depth of 12 cm. The maximum value of the absorbed dose was 2&nbsp;<span class="js-about-item-abstr">×</span> 10<sup>-3</sup> Gy at a depth of 2 cm in the phantom.</p> 2019-04-27T00:00:00+07:00 ##submission.copyrightStatement## http://ajstd.org/index.php/ajstd/article/view/567 Gamma Radiography Testing of Collimators for Boron Neutron Capture Therapy 2019-07-03T17:10:05+07:00 Deo Clinton Maranatha Simangunsong deocms44@gmail.com Yohannes Sardjono deocms44@gmail.com Budi Setyahandana deocms44@gmail.com Sigit Santosa deocms44@gmail.com Fajar Nurjaman deocms44@gmail.com <p>Boron neutron cancer therapy is a cancer treatment method that encompasses epithermal neutron irradiation of boron delivered to tumor cells. Using collimators, fast neutrons are moderated into epithermal neutrons. When radiation is performed, neutron beams are emitted and filtered by a collimator. In this study, 12 collimators used in the BNCT process were inspected for their quality, in terms of defects or flaws. The inspected collimators were manufactured by centrifugal casting and were composed of 99% pure nickel. They had the following dimensions: height of 145 mm, outer diameter of 190 mm, inner diameter of 160 mm, and thickness of 15 mm. The inspection method used was gamma radiography testing with an Iridium-192 gamma source. Using a single wall single image technique, the collimators were exposed for 30 seconds. Six FUJI films were placed behind the object to record the resulting images, which showed light or dark areas on each collimator, the latter of which indicated porosity or flaws. Based on these images, collimators 1 and 5 were found to contain cracks, and porosity was identified in almost all of the collimators. It is suggested that both collimators with cracks be recycled, while the collimators with porosities should be investigated further to determine their suitability for boron neutron cancer therapy.</p> 2019-04-27T00:00:00+07:00 ##submission.copyrightStatement## http://ajstd.org/index.php/ajstd/article/view/528 Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities 2019-07-12T11:35:49+07:00 Rini Murtafi'atin rinimurtafiatin@ajstd.org Widarto Widarto rinimurtafiatin@ajstd.org Susilo Susilo rinimurtafiatin@ajstd.org Ngurah Made Dharma Putra rinimurtafiatin@ajstd.org <p>This research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology in Yogyakarta, Indonesia. The experiment consisted of two parts, namely density analysis and determination of the neutron attenuation coefficient. For the latter, plutonium-beryllium was used as the neutron source, while a high purity germanium detector was used to measure the neutron radiation level. The results showed that barite concrete with a 2130 kg.m<sup>–3</sup> density had a neutron attenuation coefficient of 0.0871 cm<sup>–3</sup>.</p> 2019-04-27T00:00:00+07:00 ##submission.copyrightStatement##