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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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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 2 No 1 (2017)
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.

A Study of The Assessment for Boron Neutron Capture Therapy Agent Isman Mulyadi Triatmoko; Sutjipto Sutjipto
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

A study of the assessment criteria covers the synthesis and characterization of agent and test their biological effectiveness as boron neutron capture therapy (BNCT) agents in cancer treatment. The cellular uptake of this agent into the glioblastoma cells was assessed by boron analysis (ICP-MS) and by fluorescence imaging (confocal microscopy). The agent enters the glioblastoma cells exhibiting a similar profile, i.e., preferential accumulation in the cytoskeleton and membranes and a low cytotoxic activity (IC50 values higher than 200 μM). The cytotoxic activity and cellular morphological alterations after neutron irradiation in the Research Reactor (>107 neutrons cm−2 s−1) were assessed by the MTT assay and by electron microscopy (TEM). Post neutron irradiation revealed that BNCT has a higher cytotoxic effect on the glioblastoma cells. Results provide a strong rationale for considering one of these compounds as a lead candidate for a new BNCT agent.

Assessment of Analytical Instrumentation for Boron Measurement in BNCT System Isman Mulyadi Triatmoko; Sutjipto Sutjipto
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The methods boron measurement in BNCT system has generally progressed with developments in analytical instrumentation. Spectrophotometric methods remained the methods of choice for most routine applications until the development of ICP-OES. ICP-OES was also not adequately sensitive for nutritional and medical research involving animal tissues that are naturally low in boron (B). The development of plasma-source MS (e.g., ICP-MS) not only has overcome most of these drawbacks, but also its capability of measuring B isotopes. The application of nuclear reaction methods (mainly prompt-γ spectrometry) has remained limited to some specialized fields. The validity and comparability of three different analytical techniques (QNCR, PGAA, and ICP-MS) for boron measurement in biological samples and application of these methods for examination of blood and tissue samples from a clinical study on boron uptake in blood, tissue, and neoplastic tissue, after infusion of BPA. The PET-based approach to TPS has been applied in BDTPS and a preliminary evaluation of the correct operation has been performed using a heterogeneous boron phantom, called HEBOM. The validation has been accompanied by calculations done with SERA, following the standard approach. BDTPS needs further in vivo experimental validations.

Biological Evaluation of 99mTc-Kanamycin for Infection Imaging Eva Maria Widyasari; Iim Halimah; Rizky Juwita Sugiharti; Maula Eka Sriyani; Isti Daruwati; Iswahyudi Iswahyudi; Epy Isabela; Witri Nuraeni
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Kanamycin antibiotic was radiolabeled successfully with radioisotope technetium-99m for the potential use as radiopharmaceuticals for infection imaging. 99mTc-kanamycin complexes was prepared 93 % radiochemical purities by direct labelling using 5 mg kanamycin and 30 µg SnCl2. The reaction occurred at alkaline condition (pH=9) and under room temperature for 30 min to achieve high radiochemical purity. Radiochemical purity and stability of 99mTc-kanamycin was determined by ascending paper chromatography using Whatman 3 paper as the stationary phase, and acetone as the mobile phase to separate the radiochemical impurities in the form of 99mTc-pertechnetate. While impurities in the form of 99mTc-reduced were separated using the stationary phase ITLC-SG and 0.5 N NaOH as mobile phase. This study aimed to determine biological characteristic of 99mTc-kanamycin radiopharmaceutical. In vitro cell studies showed that the change of kanamycin structure after labeling with technetium-99m did not give a specific influence to the potency of kanamycin as an antibiotic. In addition on uptake study, a significantly higher uptake of 99mTc-kanamycin with S. aureus than E. coli. Biodistribution of 99mTc-kanamycin complexes was studied on normal and infection mice at 15, 30, 60 and 120 min post-injections. The biodistribution of 99mTc-kanamycin in infection mice showed that the complex accumulated in the infection sites. These results show that 99mTc-Kanamycin radiopharmaceutical have a potential application for infection diagnosis.

Analysis of Safety and Health of Radiation Officer at Pilot Plant BNCT Yuliana Dian N; Soeparmi Soeparmi; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Radiation is emission energy which derived from the process of transformation of atoms or nuclei unstable. The emission energy was emitted by a hoarse radiation, can cause changes in physical, chemical and biological material in its path so that the radiation worker should give special attention to health and safety during operate the installation using radiation. Limits opportunities for stochastic effects occur, or the risk resulting from the use of radiation that can be accepted by the public, and workers and prevent the occurrence of deterministic result of radiation harm to the individual. Equivalent dose of radiation received by workers or the public should not be beyond Dose Limit Value (NBD). This also applies to the radiation workers who operate tools for cancer therapy method using boron or Boron Neutron Capture Therapy (BNCT). BNCT is a method of new cancer therapies that are being developed, which combines methods of chemotherapy and radiotherapy. BNCT method utilizing 10B or boron compounds are likely to capture neutrons in thermal energy, which is produced by high - Linear Energy Transfer (LET). Medical examinations for radiation workers should be done regularly and follow the general principles of treatment work, namely the examination before work and after work. Threshold limit radiation exposure was 0.2 to 0.5 Sv. When a person is exposed to radiation overdose, the investigation dosage needs to be done specifically include biological dosimetry.

Conceptual Design of Collimator at Boron Neutron Capture Therapy Facility with 30 MeV Cyclotron and Target 9Be as Neutron Generator Using Monte Carlo N-Particle Extended Simulator Prayoga Isyan; Andang Widi Harto; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 1 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The optimization of collimator has been studied which resulted epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) using Monte Carlo N Particle Extended (MCNPX). Cyclotron 30 MeV and 9Be target is used as a neutron generator. The design criteria were based on recommendation from IAEA. Mcnpx calculations indicated by using 25 cm and 40 cm thickness of PbF2 as reflector and back reflector, 15 cm thickness of TiF3 as first moderator, 35 cm thickness of AlF3 as second moderator, 25 cm thickness of 60Ni as neutron filter, 2 cm thickness of Bi as gamma filter, and aperture with 20 cm of diameter size, an epithermal neutron beam with an intensity 1.21 × 109 n.cm-2.s-1, fast neutron and gamma doses per epithermal neutron of 7.04 × 10-13 Gy.cm2.n-1 and 1.61 × 10-13 Gy.cm2.n-1, minimum thermal neutron per epithermal neutron ratio of 0.043, and maximum directionality of 0.58, respectively could be produced. The results have not passed all the IAEA’s criteria in fast neutron component and directionality.

An Optimization Design of Collimator in The Thermal Column of Kartini Reactor For BNCT M. Ibnu Khaldun; Andang Widi Harto; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 2 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Studies were carried out to design a collimator which results in epithermal neutron beam for in vivo experiment of Boron Neutron Capture Therapy (BNCT) at the Kartini Research Reactor by means of Monte Carlo N-Particle (MCNP) codes. Reactor within 100 kW of thermal power was used as the neutron source. All materials used were varied in size, according to the value of mean free path for each material. MCNP simulations indicated that by using 6 cm thick of Natural Nickel as collimator wall, 65 cm thick of Al as moderator, 3 cm thick of Ni-60 as filter, 6 cm thick of Bi as γ-ray shielding, 3.5 cm thick of Li2CO3-polyethilene, with 2 cm aperture diameter. Epithermal neutron beam with maximum flux of 6.60 x 108n.cm-2.s-1 could be produced. The beam has minimum fast neutron and γ-ray components of, respectively, 1.82 x 10-13Gy.cm2.n-1 and 1.70 x 10-13 Gy.cm2.n-1, minimum thermal neutron per epithermal neutron ratio of 0.041, and maximum directionality of 2,12. It did not fully pass the IAEA’s criteria, since the epithermal neutron flux was below the recommended value, 1.0 x 109 n.cm-2.s-1. Nonetheless, it was still usable with epithermal neutron flux exceeding 5.0 x 108 n.cm-2.s-1. it is still feasible for BNCT in vivo experiment.

Calculation of Absorbed Dose Distribution for Breast Brachytherapy Simulation By CS-1 131Cs Seed and ADVANTAGETM 103Pd Seed Using Monte Carlo N Particle Extended Simulator Faisal Reza Rahmat; Mondjo Mondjo; Alexander Agung
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 2 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Simulation using Monte Carlo code has been conducted to determine the distribution of absorbed dose to the breast brachytherapy with 131Cs and 103Pd radionuclide sources. Simulations performed on stage I breast cancer with cancer diameter is 2 cm. Sources of radionuclides simulated in the form of seed is modeled with CS-1 which is made by IsoRay 131Cs and seed ADVANTAGETM103Pd which is made by IsoAID, LLC. Seed was planted in breast cancer cells. Calculation of absorbed dose distribution was performed by varying the distance from the seed. Variations of the distance started from a radius of 0.3 cm to 2 cm with a range of 0.1 cm respectively. In this simulation will also be reviewed the value of absorbed dose for healthy cell like breast, sternum, and lung. The relation between the absorbed dose and the distance from the seed can be described in the form of power law. The results of the calculation show that the maximum absorbed dose is in the target site of the cancer cells (5.791 ± 0.002) Gy per 5 MBq of 131Cs and (2.755 ± 0.009) Gy per 5 MBq for 103Pd. The absorbed dose at sternum (1.514 ± 0.011) x 10-4 Gy per 5 MBq of 131Cs and (7.515 ± 0.633) x 10-7 Gy per 5 MBq for 103Pd. While the absorbed dose in the lungs is and (3.615 ± 0.082) x 10-5 Gy per 5 MBq for 131Cs and (3.972 ± 0.591) x 10-8 Gy per 5 MBq for 103Pd.

Analysis of Radiation Effects on Workers and Environment Pilot Plant Boron Neutron Capture Therapy (BNCT) Nur Endah Sari; Yohannes Sardjono; Andang Widi Harto
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 2 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

BNCT is a new method in nuclear technology. The aim of BNCT application is to reduce human risk which used to kills cell targeting characteristic. The impact of using this technology should be considered before it is applied, among the effects of radiation on workers and the surrounding environment BNCT pilot plant. A research on modeling of BNCT pilot plant used a collimator for a 30 MeV cyclotron neutron sources which had been designed from the past research. Radiation shielding modeling for treatment room used MCNPX software. The radiation shielding was concrete baryte on each side that includes coated borated polyethylene 2 cm thick and it is featured with a sliding door with dimensions 220 × 87 × 200 cm coated with stainless steels 2 cm thick. Results obtained value equivalent dose rate of neutron and gamma of each 41.5 µSv.h-1 and 2.05 µSv.h-1. Effects of radiation received by workers in the form of deterministic effects did not have a significant are impact.

A Conceptual Design Optimization of Collimator With 181Ta as Neutron Source for Boron Neutron Capture Therapy Based Cyclotron Using Computer Simulation Program Monte Carlo N Particle Extended Jans P B Siburian; Andang Widi Harto; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 2 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The optimization of collimator with 30 MeV cyclotron as neutron source and 181Ta as its proton target. cyclotron assumed work at 30 MeV power with 1 mA and 30 kW operation condition. Criteria of design based on IAEA’s recommendation. Using MCNPX as simulator, the result indicated that with using 181Ta as target material with 0.55 cm thickness and 19 cm diameter, 25 cm and 45 cm PbF2 as reflector and back reflector, 30 cm 32S as a moderator, 20 cm 60Ni as fast neutron filter, 2 cm 209Bi as gamma filter, 1 cm 6Li2 CO3- polyethylenes as thermal neutron filter, and 23 cm diameter of aperture, an epithermal neutron beam with intensity 4.37 x 109 n.cm-2.s-1, fast neutron and gamma doses per epithermal neutron of 1.86 x 10-16 Gy.cm2.n-1 and 1.93 x 10-13Gy.cm2.n-1, minimum thermal neutron per epithermal neutron ratio of 0.003, and maximum directionality 0,728, respectively could be produced. The results have passed all the IAEA’s criteria.

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