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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 12 Documents

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Search results for , issue "Vol. 35 No. 3 (2018): Developments in Nuclear Techniques in the Treatment of Cancer" : 12 Documents clear

Boron Neutron Capture Therapy for Cancer: Future Prospects in Indonesia Bagaswoto Poedjomartono; Hanif Afkari; Edy Meiyanto; Alan Bangun; Yohanes 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.510

Boron neutron capture therapy (BNCT) is a form of cancer therapy based on the interaction of low-energy thermal neutrons and boron-10 (10-B) to produce alpha radiation from He-4 and Li-7 with a high linear energy transfer. A beam of neutrons irradiates a boron drug injected into the tumor, resulting in the boron-injected cancer cells receiving a lethal dose of radiation with the surrounding, healthy cells being minimally affected. Two boron drugs have been used clinically in BNCT, boron sodium captate (BSH) and borophenylalanine (BPA), while a third, pentagamaboronon-0 (PGB-0), is currently under development in the Faculty of Pharmacy of Universitas Gadjah Mada, Indonesia. In Indonesia, there has been a growing interest in the study and use of BNCT to treat cancer, as this method is expected to be safer and more effective than traditional cancer treatment methods.

Overview of Boron Neutron Capture Therapy: a Medical Aspect Alan Anderson Bangun; Bagaswoto Poedjomartono
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 an abnormal growth of a cell due to the cell’s inability to control and maintain its proliferation, differentiation and apoptosis cycle. There are several methods to treat cancer; one of which is boron neutron capture therapy (BNCT). BNCT is a radiation modality by which a high radiation dose is delivered to tumor cells with lower damage to surrounding normal tissue. This modality has been used widely as a treatment for several cancer cases, such as head and neck cancer, breast cancer, and liver cancer. BNCT uses sodium borocaptate (BSH) or boronophenylalanine (BPA) as the delivery agent. Then, the tumor cell is irradiated by thermal radiation. This technique has excellent potential to become a main method of cancer therapy in the future, since it is noninvasive and has fewer side effects than other methods. Further studies on BNCT are needed to improve its performance as a cancer treatment modality.

Overview on Steady-state Nuclear Methods for BWR Nuclear Core Design and Analysis Ren-Tai Chiang
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

An overview on nuclear methods for boiling water reactors (BWR) core design and analysis is provided based on the ANS Standard 19.3. The steady-state BWR nuclear methods, composed of neutron cross section library generation method, lattice physics method and core physics method, are systematically reviewed and associated computer codes in common use for BWR core design and analysis are listed. Veri?cation and validation, the two complementary aspects in determining the range of applicability of the calculation system, are discussed extensively. The biases and uncertainties for the predictions from the calculation system over its demonstrated range of applicability are also discussed.

Dose Analysis of BNCT Treatment Method for Rhabdomyosarcoma in the Head and Neck Regions Based on PHITS Code Dhani Nur Indra Syamputra; Yohannes Sardjono; Rida Siti Nur’aini Mahmudah
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.521

The objectives of this research were to ?nd (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 ?ux and neutron dose. The neutron ?ux 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.

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

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.

Characteristics of Paraffin Shielding of Kartini Reactor, Yogyakarta Lana Khanifah; Susilo Widodo; Widarto; Ngurah Made Dharma Putra; Argo Satrio
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.526

The National Nuclear Energy Agency (BATAN) Yogyakarta uses two kinds of paraffin for shielding radiation of Kartini reactor. For developing BNCT research, the radiation attenuation capability of paraffin has been analyzed to find out the coefficient attenuation, density, and composition of both kinds of paraffin. The components of the paraffin were analyzed using Fourier transform infrared (FTIR) spectroscopy, scanning electron microscopy (SEM), and energy dispersive X-ray (EDX) spectroscopy characterization. Paraffin P1 has a density of 0.689 gr/mL and paraffin P2 is 0.578 gr/mL. Paraffin samples P1 and P2 were the sample content of functional group CH, CH2, and OH when analyzed by FTIR. Paraffin P2 had an additional content namely CO. The concentration of carbon (C) and oxide (O) of paraffin P2 was much greater than that of paraffin P1. Hydrogen (H) in the paraffin has the function of moderating neutrons, but hydrogen content in both kinds of paraffin could not be detected by EDX. The acquired neutron coefficient attenuation of paraffin P2 was 0.0382 cm-1 and the gamma coefficient attenuation was 0.0535 cm-1.

Conceptual Shield Design for Boron Neutron Capture Therapy Facility Using Monte Carlo N-Particle Extended Simulator with Kartini Research Reactor as Neutron Source Afifah Hana Tsurayya; Azzam Zukhrofani Iman; R. Yosi Aprian Sari; Arief Fauzi; Gede Sutresna Wijaya
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

The research aims to measure the radiation dose rate over the radiation shielding which is made of paraffin and aluminium and to determine the best shield material for the safety of radiation workers. The examination used MCNP (Monte Carlo N-Particle) simulator to model the BNCT neutron source and the shield. The shield should reduce radiation to less than the dose limit of 10.42 µSv/h, which is assumed to be the most conservative limit when the duration of workers is 1920 h. The first design resulted in a radiation dose rate which was still greater than the limit. Therefore, optimization was done by adding the lead on the outer part of the shield. After optimization by adding the lead with certain layers, the radiation dose rate decreased, with the largest dose being 57.60 µSv/h. Some locations over the limit could be overcome by other radiation protection aspects such as distance and time. The paraffin blocks were covered by aluminium to keep the shield structure. The lead was used to absorb the gamma ray which resulted from the interaction between the neutrons and aluminium.

Analysis of Radiation Interactions and Biological Effects for Boron Neutron Capture Therapy Ren-Tai Chiang
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

The direct and indirect ionizing radiation sources for boron neutron capture therapy (BNCT)are identi?ed. The mechanisms of physical, chemical and biological radiation interactions for BNCT are systematically described and analyzed. The relationship between the effect of biological radiation and radiation dose are illustrated and analyzed for BNCT. If the DNAs in chromosomes are damaged by ion- izing radiations, the instructions that control the cell function and reproduction are also damaged. This radiation damage may be reparable, irreparable, or incorrectly repaired. The irreparable damage can result in cell death at next mitosis while incorrectly repaired damage can result in mutation. Cell death leads to variable degrees of tissue dysfunction, which can affect the whole organism’s functions. Can- cer cells cannot live without oxygen and nutrients via the blood supply. A cancer tumor can be shrunk by damaging angiogenic factors and/or capillaries via ionizing radiations to decrease blood supply into the cancer tumor. The collisions between ionizing radiations and the target nuclei and the absorption of the ultraviolet, visible light, infrared and microwaves from bremsstrahlung in the tumor can heat up and damage cancer cells and function as thermotherapy. The cancer cells are more chemically and biologically sensitive at the BNCT-induced higher temperatures since free-radical-induced chemical re- actions are more random and vigorous at higher temperatures after irradiation, and consequently the cancer cells are harder to divide or even survive due to more cell DNA damage. BNCT is demonstrated via a recent clinical trial that it is quite effective in treating recurrent nasopharyngeal cancer.

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.

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