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Journal : ASEAN Journal on Science and Technology for Development

Dose Analysis of In Vitro and In Vivo Test for Boron Neutron Capture Therapy (BNCT) Faqqiyyah, Hamidatul; Sunarno, Sunarno; Akhlis, Isa; Sardjono, Yohannes
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

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Abstract

The purpose of this study was to determine the in vitro and in vivo doses of boron neutron capture cancer therapy (BNCT) using the SHIELD-HIT12A program. To be able to determine the recoil energy, the research was conducted using the Monte Carlo method. Running data obtained the value of ionization activity and recoil lost. The results showed that in vitro and in vivo doses of BNCT for soft tissue irradiation had a value of 0.312 × 10-2 Sv, which is safe and does not harm healthy body tissue around the cancer cells because it is below the threshold of 1.5 Rem or 15 × 10-3 Sv, in accordance with the provisions of the upper value permitted by the International Commission on Radiation Protection in 1966. While the comparative targets are water, the optimal target absorption dose was obtained at concentrations of 3.232 × 10-3 Gy. The dose of carbon equivalent in water with the type of thermal neutron radiation was 16.16 × 10-3 Sv; this dose is classified as unsafe.
Dose Analysis of BNCT Treatment Method for Rhabdomyosarcoma in the Head and Neck Regions Based on PHITS Code Syamputra, Dhani Nur Indra; Sardjono, Yohannes; Mahmudah, Rida Siti Nur’aini
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

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Abstract

 The objectives of this research were to find (1) the optimum boron dose for treating rhab- domyosarcoma in the head and neck regions and (2) the effective irradiation time to treat rhab- domyosarcoma in the head and neck regions. This research used the particle and heavy ions transport code system (PHITS) to simulate the neutron source and BNCT doses. The neutron source used was Kartini Reactor. The simulation was carried out by creating the geometry of cancer tissue in the head and neck regions. Boron concentration variance was 30, 35, 40, 45, and 50 µg/g tissue. The output of PHITS was a neutron flux and neutron dose. The neutron flux value was used to acquire the alpha dose, proton dose, and gamma dose inside the tissue. The results showed that (1) the optimum boron dose for treating rhabdomyosarcoma in the head and neck regions was 50 µg/g tissue and (2) the effective irradiation time was 7 hours and 4 minutes, which was acquired with a boron concentration of 50 µg/g tissue. The higher the boron concentration level, the higher the dose rate, the quicker the irradiation time, and the lower the radiation dose received by healthy tissues.
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 Maysaroh, Atika; Kusminarto, Kusminarto; Palupi, Dwi Satya; Sardjono, Yohannes
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

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Abstract

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 Fasni, Bagus Novrianto; Sardjono, Yohannes; Lapanporo, Boni Pahlanop
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

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Abstract

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) Harish, Ahmad Faisal; Warsono, Warsono; Sardjono, Yohannes
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

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Abstract

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 μg/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; Suparta, Gede Bayu; Hermanto, Arief; Palupi, Dwi Satya; Sardjono, Yohannes
ASEAN Journal on Science and Technology for Development Vol 36 No 1 (2019)
Publisher : Universitas Gadjah Mada

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Abstract

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

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Abstract

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.
Co-Authors Abdullah Nur Aziz Adrian Tesalonika, Adrian Agung Prastowo, Agung Andang Widi Harto Andang Widiharto Anggraeni Dwi Susilowati, Anggraeni Dwi Aniti Payudan, Aniti Arief Hermanto Aulia Setyo Wicaksono, Aulia Setyo Bemby Yulio Vallenry Bilalodin Bilalodin Bima Caraka Putra, Bima Boni Pahlanop Lapanporo Budi Setyahandana Darmayanti, Alifia Dwi Satya Palupi Eko Priyono Fahrudin Nugroho Fajar Nurjaman Faqqiyyah, Hamidatul Fasni, Bagus Novrianto Ferdy S. Rondonuwu Gede Bayu Suparta Gede Sutisna Wijaya, Gede Sutisna Giner Maslebu, Giner Harish, Ahmad Faisal Hasyim, Kholidah Hilmi Tantawy, Hilmi I Made Ardana Irhas Irhas, Irhas Isa Akhlis Isman Mulyadi Triatmoko, Isman Mulyadi Jans P B Siburian, Jans P B Jodelin Muninggar, Jodelin Kusminarto Kusminarto Larry E. Fennern Larry E. Fennern M. Ibnu Khaldun, M. Ibnu Mahmudah, Rida Siti Nur’aini Martinus I Made Adrian Dwiputra, Martinus I Made Adrian Masanori Aritomi Maysaroh, Atika Mu’Alim, Muhammad Muhammad Ilma Muslih Arrozaqi, Muhammad Ilma Muslih Nina Fauziah Ntoy, Suhendra Gunawan Nur Endah Sari, Nur Endah Prayoga Isyan, Prayoga Priambodo, Gani Ralind Re Marla Ranti Warfi, Ranti Ratnasari, Nunung Gupita Rosenti Pasaribu, Rosenti S.B., Ramadhan Valiant Gill Sigit Santosa Siti Rosidah Slamet Parmanto Soeparmi Soeparmi, Soeparmi Sri Yuniarti Sunardi Sunardi Sunarno Sunarno Sungkowo Wahyu Santoso Supardi Supardi Suryasatriya Trihandaru Susilo Susilo Susilo Widodo, Susilo Syamputra, Dhani Nur Indra Syarip Syarip Wahyuni, Nur Setyo Warsono Warsono Widarto Widarto Wusko, Ikna Urwatul Yosaphat Sumardi Yuliana Dian N, Yuliana Dian Zailani, Rosilatul