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ASEAN Journal on Science and Technology for Development

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Published by Universitas Gadjah Mada

ISSN : 22249028 EISSN : 22249028 DOI : -

Core Subject : Science, Education, Engineering,

Biochemistry, Genetics & Molecular Biology Chemical Engineering, Chemistry & Bioengineering Computer Science & IT Mathematics

The coverage is focused on, but not limited to, the main areas of activity of ASEAN COST, namely: Biotechnology, Non-Conventional Energy Research, Materials Science and Technology, Marine Sciences, Meteorology and Geophysics, Food Science and Technology, Microelectronics and Information Technology, Space Applications, and Science and Technology Policy, Infrastructure and Resources Development.

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Articles 477 Documents

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Beam Shaping Assembly Optimization for Boron Neutron Capture Therapy Facility Based on Cyclotron 30 MeV as Neutron Source Fauzi, Arief; Tsurayya, Afifah Hana; Harish, Ahmad Faisal; Wijaya, Gede Sutresna
ASEAN Journal on Science and Technology for Development Vol. 35 No. 3 (2018): Developments in Nuclear Techniques in the Treatment of Cancer
Publisher : Universitas Gadjah Mada

A design of beam shaping assembly (BSA) installed on cyclotron 30 MeV model neutron source for boron neutron capture therapy (BNCT) has been optimized using simulator software of Monte Carlo N-Particle Extended (MCNPX). The Beryllium target with thickness of 0.55 cm is simulated to be bombarded with 30 MeV of proton beam. In this design, the parameter regarding beam characteristics for BNCT treatment has been improved, which is ratio of fast neutron dose and epithermal neutron flux. TiF3 is replaced to 30 cm of 27Al as moderator, and 1.5 cm of 32S is combined with 28 cm of 60Ni as neutron filter. Eventually, this design produces epithermal neutron flux of 2.33 × 109, ratio between fast neutron dose and epithermal neutron flux of 2.12 × 10-13,ratio between gamma dose and epithermal neutron flux of 1.00 × 10-13, ratio between thermal neutron flux and epithermal neutron flux is 0.047, and ration between particle current and total neutron flux is 0.56.

Dosimetry of In Vivo Experiment for Lung Cancer Based on Boron Neutron Capture Therapy on Radial Piercing Beam Port Kartini Nuclear Reactor by MCNPX Simulation Method Atika Maysaroh; Kusminarto Kusminarto; Dwi Satya Palupi; Yohannes Sardjono
ASEAN Journal on Science and Technology for Development Vol. 35 No. 3 (2018): Developments in Nuclear Techniques in the Treatment of Cancer
Publisher : Universitas Gadjah Mada

Cancer is one of the leading causes of death globally, with lung cancer being among the most prevalent. Boron Neutron Capture Therapy (BNCT) is a cancer therapy method that uses the interaction between thermal neutrons and boron-10 which produces a decaying boron-11 particle and emits alpha, lithium 7 and gamma particles. A study was carried out to model an in vivo experiment of rat organisms that have lung cancer. Dimensions of a rat’s body were used in Konijnenberg research. Modeling lung cancer type, non-small cell lung cancer, was used in Monte Carlo N Particle-X. Lung cancer was modeled with a spherical geometry consisting of 3 dimensions: PTV, GTV, and CTV. In this case, the neutron source was from the radial piercing beam port of Kartini Reactor, Yogyakarta. The variation of boron concentration was 20, 25, 30, 35, 40, and 40 µg/g cancer. The output of the MCNP calculation was neutron scattering dose, gamma-ray dose and neutron flux from the reactor. A neutron flux was used to calculate the alpha proton and gamma-ray dose from the interaction of tissue material and thermal neutrons. The total dose was calculated from a four-dose component in BNCT. The results showed that the dose rate will increase when the boron concentration is higher, whereas irradiating time will decrease.

Dose Analysis of Gadolinium Neutron Capture Therapy (GdNCT) on Cancer Using SHIELD-HIT12A Bagus Novrianto Fasni; Yohannes Sardjono; Boni Pahlanop Lapanporo
ASEAN Journal on Science and Technology for Development Vol. 35 No. 3 (2018): Developments in Nuclear Techniques in the Treatment of Cancer
Publisher : Universitas Gadjah Mada

This research aimed to determine the dose of radiation received in cancer therapy for each decay of Gadolinium atomic nuclei with isotope 157 (157Gd) in Gadolinium Neutron Capture Therapy using the SHIELD-HIT12A program. Knowing the amount of dose given to cancer tissue should aid in minimizing the damage that could occur in the healthy tissue around the cancer tissue, effectively killing only the cancer cells. The simulation employed in this research used the SHIELD-HIT12A program by providing input on beam.dat, mat.dat, detect.dat, and geo.dat files. The output data from the program comprised the value of recoil energy lost (energy absorbed into the target materials) for each of the 157Gd atomic nuclei, which was then processed by the dose determination equation to determine the dose given by the 157Gd nucleus to soft tissue. Based on the results, the amount of the dose given by each atomic nucleus 157Gd to soft tissue was 5.44 × 1011 Gy/decay.

Dose Analysis of Boron Neutron Capture Therapy (BNCT) Treatment for Lung Cancer Based on Particle and Heavy Ion Transport Code System (PHITS) Ahmad Faisal Harish; Warsono; Yohannes Sardjono
ASEAN Journal on Science and Technology for Development Vol. 35 No. 3 (2018): Developments in Nuclear Techniques in the Treatment of Cancer
Publisher : Universitas Gadjah Mada

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.29037/ajstd.545

The objectives of this study were to determine the effect of boron concentration on total dose rate for lung cancer treatment, and to determine the effect of boron concentration on the length of irradiation time for lung cancer treatment. This study was computer simulation-based using the Particle and Heavy Ion Transport code System (PHITS) by defining the geometry and components of lung cancer and the surrounding organism as the object being studied and the source of radiation used. The type of phantom used was the ORNL of an adult Asian male. The neutron source used was Kartini Reactor. The independent variable was the boron concentration of 30, 40, 50, 60, and 70 ?g/g cancer tissue and the dependent variables were the dose rate and the irradiation time. The results of this study indicated that the larger the amount of boron concentration that was injected, the higher the rate of total dose the organ received, where the total dose rate for each variation of boron concentration were 1.34 × 10-3 Gy/s, 1.71 × 10-3 Gy/s, 2.07 × 10-3 Gy/s, 2.42 × 10-3 Gy/s, and 2.78 × 10-3 Gy/s, and the larger the amount of boron concentration that was injected, the faster the irradiation time for the treatment of lung cancer was, where the irradiation time required for each variation of boron concentration was 37294 s, 29240 s, 24180 s, 20633 s, and 17996 s.

Characteristics in Water Phantom of Epithermal Neutron Beam Produced by Double Layer Beam Shaping Assembly Bilalodin Bilalodin; Gede Bayu Suparta; Arief Hermanto; Dwi Satya Palupi; Yohannes Sardjono
ASEAN Journal on Science and Technology for Development Vol. 36 No. 1 (2019): Vol 36 No 1 (2019)
Publisher : Universitas Gadjah Mada

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 × 10-3 Gy at a depth of 2 cm in the phantom.

Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities Rini Murtafi'atin; Widarto Widarto; Susilo Susilo; Ngurah Made Dharma Putra
ASEAN Journal on Science and Technology for Development Vol. 36 No. 1 (2019): Vol 36 No 1 (2019)
Publisher : Universitas Gadjah Mada

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–3 density had a neutron attenuation coefficient of 0.0871 cm–3.

Removal of Heavy Metals from an Actual Small Scale Gold Mining Wastewater by Sorption onto Cocopeat Jessie O. Samaniego; Maria Antonia N. Tanchuling
ASEAN Journal on Science and Technology for Development Vol. 36 No. 1 (2019): Vol 36 No 1 (2019)
Publisher : Universitas Gadjah Mada

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.

Gamma Radiography Testing of Collimators for Boron Neutron Capture Therapy Deo Clinton Maranatha Simangunsong; Yohannes Sardjono; Budi Setyahandana; Sigit Santosa; Fajar Nurjaman
ASEAN Journal on Science and Technology for Development Vol. 36 No. 1 (2019): Vol 36 No 1 (2019)
Publisher : Universitas Gadjah Mada

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.

Investigation on the behavior of rigid polyvinylchloride pipes subjected to uniaxial compression loads Abdullah Ali Nasser Alhamati; Abdul Halim Ghazali; Jamalodin Norzaie
ASEAN Journal on Science and Technology for Development Vol. 23 No. 3 (2006): ASEAN Journal on Science and Technology for Development (AJSTD)
Publisher : Universitas Gadjah Mada

The objective of this research was to investigate the capability of rigid Polyvinylchloride (PVC-U) pipes to sustain axial loads. The behavior of PVC-U pipes specimens subjected to short-term uniaxial compression loads were experimentally investigated. Results of the load-displacement tests on pipes of different wall thickness, diameter, and specimen heights were recorded. The experimental test results show that the PVC-U pipes are capable of supporting loads greater than the required design load (3.4 kN). Increasing the pipe specimen height decreases the pipe strength for supporting the axial loads. Euler buckling was observed in the pipe specimens with small diameter and long axial height. Furthermore, an attempt has been made to utilize the ANSYS finite element commercial package to model the pipe system using eight noded brick element and the results were compared with those obtained from the experimental tests. Good agreement was found between the two sets of results, within the elastic range of the load-displacement curve.

ANT INTELLIGENCE ROUTING Chye Ong Gan; K. Daniel Wong; Wei-Le Woon
ASEAN Journal on Science and Technology for Development Vol. 25 No. 1 (2008): ASEAN Journal on Science and Technology for Development (AJSTD)
Publisher : Universitas Gadjah Mada

We introduce AIR, a new ant-based routing protocol for ad hoc wireless networks. AIR incorporates recent technology advances in ad hoc routing protocols, such as ring-based searching and third-party reply, while retaining the characteristics and benefits of ant-based routing protocols, including probabilistic routing tables and pheromone evaporation. In addition, we combine the best features of previous ant-based routing protocols with new features like update ants and two-way route establishment, to further improve performance. We compare the performance of AIR against AODV and DSR using appropriately chosen simulations, the results of which are presented and discussed. We find that AIR is especially useful for ad hoc networks requiring low end-to-end delay where mobility rates are high.

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