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Indonesian Journal of Physics and Nuclear Applications

ijpna
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Published by Universitas Kristen Satya Wacana

ISSN : 2549046X EISSN : - DOI : -

Core Subject : Science, Social,

Environmental Science Physics

Indonesian Journal of Physics and Nuclear Applications is an international research journal, which publishes top level work from all areas of physics and nuclear applications including health, industry, energy, agriculture, etc. It is inisiated by results on research and development of Indonesian Boron Neutron Capture Cancer Therapy (BNCT) Consortium. Researchers and scientists are encouraged to contribute article based on recent research. It aims to preservation of nuclear knowledge; provide a learned reference in the field; and establish channel of communication among academic and research expert, policy makers and executive in industry, commerce and investment institution.

Arjuna Subject : -

Articles 80 Documents

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Preparation of Dosimetry of Boron Neutron Capture Therapy (BNCT) for In vivo Test Planning system using Monte Carlo N-Particle Extended (MCNP-X) Software Muhammad Ilma Muslih Arrozaqi; Kusminarto Kusminarto; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 2 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Cancer is a disease with second largest patients in the world. In Indonesia, the number of radiotherapy facility in Indonesia is less than 30 units and every patients needs more than single exposure, so that it result a long waiting list of treatment up to one year. Now, a new treatment of cancer is developed. It is Boron Neutron Capture Therapy that using capture reaction of neutron by Boron-10. Before this method is applied to patient, it requires some testing which is one of them is in vivo test. This research has been conducting to prepare the in vivo test, especially in dosimetry. Preparation of dosimetry includes collimator design and mouse phantom model. The optimum specification of the collimator is consist of Nickel collimator wall with 2 cm of thickness, Aluminum moderator with 10 cm of thickness and lead gamma shield with 3.5 of thickness. This design result in 1.18 x 108 n/cm2s of epithermal and thermal neutron flux, 2,24 x 10-11 Gy cm2/s of fast neutron component dose, 1.35 x 10-12 Gy cm2/s of gamma dose component, and 7.18 x 10-1 of neutron current and flux ratio. Mouse phantom model is built by two basic kind of geometry, they are Ellipsoid and Elliptical Tory. Both of basic geometry can be used to make all important organs of mouse phantom for dosimetry purpose.

Quality Management System Program of in Vitro/in Vivo Test Facility of Boron Neutron Capture Therapy at Kartini Research Reactor Widarto Widarto; Isman Mulyadi Tri Atmoko; Gede Sutresna Wijaya
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 2 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The quality manajement system program of in vitro / in vivo test facility of Boron Neutron Capture Therapy (BNCT) methode as quality assurance requirement for utilization of radial pearcing beamport of Kartini research have been done. Identification and management of technical specification and parameters meassurement of to the radial piercing beamport have been determined for preparing in vitro / in vivo test facility. The parameters are epithermal neutron flux is 9,8243E+05 n cm-2 s-1and thermal neutron flux is 3,0691E+06 n cm-2 s-1, radiation shielding of parafin, dimension and size of piercing radial and instrumentatin and control system for automatic transfer of in vitro / in vivo samplels have been documented. Management system of the documents for fullfil basic guidance to perform working job of in vitro / in vivo at the piercing radial beamport of Kartini Research Reactor in order purpose utilization of the reactor for safety worker of the radiation area, society and invironment beeing safely

Radionuclide Release Prediction in Water and Soil at Demonstration Plant of Near Surface Disposal for Radioactive Waste Pandu Dewanto; Setyo Sarwanto Moersidik; Sucipta Sucipta
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 2 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Near Surface Disposal (NSD) for Radioactive Waste that should be developed due to increment of the low level radioactive waste, need to be analyzed and evaluated related to the radiological impact of the environment. A research method applied is done by modeling the distribution of radionuclide releases process. Analysis related with the releases of radionuclide in water and soil is using PRESTO (Prediction of Radiological Effects Due to Shallow Trench Operations). The application scenarios selected in this safety assessment is the migrations of Co-60 and Cs-137 scenario through the shallow groundwater flow pattern in the NSD site. The SigmaPlot software is also used to determine the concentration equation in well water and river water. The final results showed the concentration of radionuclide in wells and streams below the provision. Radionuclide activity concentrations in well ranged from 10-10Bq/m3 to 100Bq/m3 and in the river ranged from 10-15Bq / m3 to 10-1Bq / m3. The impact of radioactive waste of radionuclide Co-60 and Cs-137 will decrease to the background radiation level at a distance less than 10m and penetrate into the saturated layer up to 4m. In this study, an equation have been obtained that can predict radionuclide concentration patterns based on the distance and the depth of the ground surface against to the facility operation time.

Paper Strength Development with Beating and Polyamideamine-epichlorohydrin (PAE) Maria Ulfa; Bambang Setiaji; Wega Trisunaryanti; Triyono Triyono
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Thecharacter of coir handsheets prepared with beating and addition of polyamideamine-epichlorohydrin (PAE) was investigated. Pulp coir from soda-anthraquinone pulping was used as raw material for manufacture of coir handsheets. Physical and mechanical properties obtained with different beating level and PAE dosage were measured. The addition of PAE 10% w/w and beating on pulp stock of 3000 rev increased grammage and density at 1.9 and 15.8%, respectively. Instead it decreased thickness by 15.8%. Addition PAE dosage of 10% w/w at 10000 rev improved the density, but decreased the porosity and Cobb60 at 5.8; 10.2; and 19 %, respectively. The highest dry and wet tensile were obtained at 20 % w/w of PAE. Combination of beating and addition of PAE on pulp stock formed wet-strength handsheets with range between 28.0 to 34.2%.

Optimization of a Beam Shaping Assembly Design for Boron Neutron Capture Cancer Therapy Facility Based on 30 MeV Cyclotron I Made Ardana; Kusminarto Kusminarto; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

A series of simulations has been carried out using a Monte Carlo N Particle X code to find out the final composition and configuration of a neutron Beam Shaping Assembly (BSA) to moderate the fast neutron flux which is generated from the thick disk-type beryllium target. The final configuration for neutron BSA design included 35 cm lead as reflector, 39 cm alumina as moderator, 8.2 cm lithium fluoride as fast neutron filter and 0.5 cm boron carbide as thermal neutron filter. Bismuth, lead fluoride, and lead were chosen as the aperture, reflector, and gamma shielding, respectively. The disk-type of beryllium target is 19 cm in diameter with 0.5 cm thickness which is covered by copper plate to hold the water pressured coolant. A higher yield of neutron production requires a higher intensity of proton beams, which generate much heats and causes the target material to melt. Therefore, it is useful to consider the temperature distribution on the target material with ﬂowing water coolant by means of computer modeling while designing the target. ANSYS-Fluent code will be used to estimate the thermal transfer and heat calculation in a solid target during beam irradiation. Epithermal neutron flux in the suggested design were 1,03x109 n/cm2 s, with almost all IAEA parameters for BNCT BSA design has been satisfied.

BIOLOGICAL SAFETY EVALUATION OF 99mTc-DTPA-KETOCONAZOLE FOR DIAGNOSIS OF FUNGAL INFECTION Maula Eka Sriyani; Hendris Wongso; Eva Maria Widyasari; Rizky Juwita Sugiharti; Iim Halimah; Iswahyudi Iswahyudi; Ahmad Sidik; Epy Isabela; Witri Nuraeni
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Infectious diseases have become one of the leading cause of mortality around the world, including in the Southeast Asia. One of the microbial that cause infection is fungi. Occasionally, deep-seated fungal infection is difficult to detect using conventional diagnosis methods and therefore leads to inaccurate detection. Our previous research was conducted in order to obtain the labeled compound of 99mTc-DTPA-Ketoconazole with a high radiochemical purity (98.40 ± 0.86%). Moreover, the in-vitro assays showed that 99mTc-DTPA-Ketoconazole can potentially bind to Candida albicans. On the other hand, in clinical routine use, diagnostic kit should be safe for the patients. Consequently, this research was conducted to determine the biological safety parameters of 99mTc-DTPA-Ketoconazole on the animal study, including single dose and acute toxicity test, sterility, and apirogenicity test. The results showed that both the single dose at 34.6 μCi and dose until 149 times of the single dose did not stimulate the toxic response to the animals. In addition, the sterility data revealed that there was no microbial growth after 7 days of incubation at 37°C as well as fungal growth after 14 days of incubation at 25°C. Furthermore, the apirogenicity test using rabbits revealed that there was no increase in temperature more than 0.6°C for each animal and not more than 1.5°C of total increase of temperature for all the animals. It is concluded that the 99mTc-DTPA-Ketoconazole is satisfy the requirements of biological safety of a radiopharmaceutical and therefore was acceptable for fungal detection in nuclear medicine.

Effect of pH on Adsorption of Cr(III) and Cr(VI) by zeolite A (from Fly Ash) Modified Surfactant HDTMA Jumaeri Jumaeri; Juari Santosa; Sutarno Sutarno; Ella Kusumastuti
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Adsorption of Cr(III) and Cr(VI) in aqueous solution by the zeolite A from coal fly ash modified hexadecyltrimethylammonium bromide (HDTMAB) at various pH conditions has been carried out. Zeolite A was synthesized from fly ash through modified alkaline fusion hydrothermal process in a reactor stainless steel. The surface modification was performed using cationic surfactant HDTMAB twice as much as the cationic exchange capacity of the elite A resulted. The surfactant modified zeolite A was then applied to adsorption the metal ion chromium as Cr(III) and Cr(VI) in aqueous solution. The results showed that the acidity (pH) of adsorption conditions, affect the ability of adsorption surfactant modified zeolite A (SMZA) to Cr(III) and Cr(VI) in aqueous solution. The optimum pH conditions for the adsorption of Cr(III) and Cr(VI) on SMZA exist at pH 6. Surfactant modified zeolite A capable to adsorb either cation Cr(III) or anion Cr(VI). Adsorption of SMZA on Cr(III) increased from 36.30% to 97.04% with the increase the acidity of pH of 2 to 6. Adsorption SMZA to Cr(VI) is lower than the adsorption of the Cr3+, adsorption increasing from 19.63 to 64.07% with increase pH of 2 to 6

The Voxel Mice Model of MCNPX for Simulation In Vivo Test BNCT Agung Prastowo; Yohannes Sardjono; Widarto Widarto
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

A study of voxel mice model of MCNPX has been done for in vivo test Boron Neutron Capture Therapy (BNCT). Mathematical and parameters were used to construct the stylized Mice model phantom. The geometry was modified into simulation software MCNPX (Monte Carlo N-Particle eXtended) simulation input. The result of mice stylized model phantom has been showed Figure 3.

Catalytic Activity of Zr4+/ZA on The Isomerization Reaction of α-Pinene and It’s Reusability Test Nico Aditya Wijaya; Nanik Wijayati; Edy Cahyono
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Production of turpentine oil from pine resin until December 2014th was reported to reaching 17.150 tones with the wide of pine forest is 876.992,66 acres. The main component of turpentine oil is α-pinena which isomer products have high value for industrial raw materials. Effects concentration of impregnation and reusability test a best catalyst on α-pinene isomerization reaction using catalysts Zr4+/natural zeolite in which modificated with different Zr4+ concentration were analyzed. Characterization of catalyst included X-ray Fluoroscent for detection of Zr concentration in natural zeolites, Surface Area Analyzer for determine catalyst porosity using BET method, and determination of acidity using vapor ammonia and pyridine base adsorption gravimetric method. Isomerization process used a batch reactor with variation in the concentrations of Zr4+ impregnations 10, 15, and 20 w/w as well as reusability test used best catalyst. The highest conversion of α-pinene used Zr4+/ZA 10% catalyst was 3,89% so as Zr4+/ZA 10% catalyst is best catalyst than other catalysts whereas highest conversion of α-pinene used Zr4+/ZA 10% regeneration catalyst was 4,26%. The product is produced from isomerization reaction of α-pinene used Zr4+/ZA all variations catalysts was camphene and limonene.

Biological Shielding Design of In Vitro Test Facility Boron Neutron Capture Therapy (BNCT) at Radial Piercing Beam Port of Kartini Research Reactor Using MCNPX Widarto Widarto; Buyung Edi Prabowo
Indonesian Journal of Physics and Nuclear Applications Vol 1 No 3 (2016)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

This research aimed to determine material specification of radiation biological shielding design of neutron and gamma output on radial piercing beamport of Kartini Research Reactor using MCNPX code, as safety radiation protection purpose of in vitro / in vivo irradiation test facility. Refference input data using parameters of neutron and gamma as result simmulation researcher before as follows Фth is 5.00 x 108 n.cm-2s-1, Фepi is 1.23 x 108 n.cm-2s-1, Фfast is 1.35 x 109 n.cm-2s-1, Ḋγ is 2.49 x 10-3 Sv.s-1, Ḋn is 3.63 x 10-1 Sv.s-1. [ Dwi W.]Optimation result of simulation using MCNPX to determine specification material for radiation protection safety are parafin block with thickness 75 cm for neutron shielding and covered by material lead (Pb) with thickness 15 cm for gamma shieding. By this optimation for the both thickness materials, determination for neutron and gamma dose rate are as follow , Ḋn = 1,1 x Sv.s-1 and with Ḋγ = 1,1 x 10-09 Sv.s-1. Those radiation dose rate of neutron and gamma parameters are still under requirement of safety dose standard that is 2.78 x 10-9 Sv.s-1 as regulation of Regulatory Body BAPETEN. [Perka BAPETEN No. 4 Tahun 2014]. It can be concluded that by the Biological Shielding Design of In Vitro Test Facility Boron Neutron Capture Therapy (BNCT) at Radial Piercing Beam Port of Kartini Research Reactor Using MCNPX can operated safely.

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