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All Journal Indonesian Journal of Physics and Nuclear Applications

Yohannes Sardjono

Pusat Sains Dan Teknologi Akselerator; Badan Tenaga Nuklir Nasional (PSTA BATAN) / Center of Science and Technology of Accelerator; National Nuclear Energy Agency

Author-ID : 2656934

Environmental Science Physics

Published : 5 Documents Claim Missing Document

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Articles

The Optimization of Collimator Material and In Vivo Testing Dosimetry of Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method Yohannes Sardjono; Kusminarto Kusminarto; Ikna Urwatul Wusko
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Boron Neutron Capture Therapy (BNCT) on radial piercing beam port Kartini nuclear reactor by MCNPX simulation method has been done in the National Nuclear Energy Agency Yogyakarta. BNCT is a type of therapy alternative that uses nuclear reaction 10B (n, α) 7Li to produce 2.79 MeV total kinetic energy. To be eligible IAEA conducted a study of design improvements and variations on some parameters to optimum condition which are Ni-nat thickness of 1.75 cm as collimator wall, Al2S3 as thick as 29 cm as moderator, Al2O3 0.5 cm thick as filter, Pb and Bi thickness of 4 cm as the end of the gamma shield collimators and Bi thickness of 1.5 cm as the base gamma shield collimators. The total dose was accepted in the tumor tissue 900 × 10-4 Gy/s. Radiation dose on the tumor tissue is 50±3 Gy with time irradiation of 9 minutes and 10 seconds. That dose was given into skin tissue and healthy liver tissue consecutively (6.00±0.05) × 10-2 Gy and (10.00±0.05) × 10-2 Gy. It shows the dose received by healthy tissue is still within safe limits.

Neutron Characterization of BNCT Water Phantom Based on Kartini Research Reactor Using PHITS Vika Hutaria; Susilo Susilo; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 1 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Boron Neutron Capture Therapy (BNCT) is a therapy that utilizes the interaction of thermal neutrons with a boron-10 core that produces alpha particles and lithium nuclei. The result of this boron reaction has high linear energy transfer (LET). BNCT has an advantage over other radiation therapy in that it has a high selectivity level. This research was run using PHITS simulation to find out the value of neutron flux spread over a water phantom. The conclusion of the research is the distribution of neutron flux in the water phantom without boron is higher the the distribution of neutron flux in the water phantom containing boron

Neutron Chareacterization of BNCT Water Phantom Based on 30 MeV Cyclotron Using PHITS Computational Code Okti Dyah Rahayuningsih; Susilo Susilo; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 1 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Cancer is the second leading cause of death globally and was responsible for 8,8 million deaths in 2015. Approximately 70% of deaths from cancer occur in low- and middle-income countries. The war on cancer has been fought with three tools – surgery (cut), radiation therapy (burn) including radiotherapy and bracytherapy, and also chemotherapy (poison). Cancer therapy has increased life expectancy of patients but each treatment modality has its own effects, complications and toxicity. Moreover we have found a new effective method to fight cancer, that is, Boron Neutron Capture Therapy (BNCT). Boron Neutron Capture Therapy (BNCT) has for many decades been advocated as an innovative form of radiotherapy that, in principle, has the potential to be the ideal form of treatment for many types of cancers. This research’s aim is the characterising neutron of BNCT water phantom based on 30 MeV cyclotron using PHITS computational code. The result from the simulation is that thickness of the water phantom, related to flux neutron.

MONTE CARLO N PARTICLE EXTENDED (MCNPX) RADIATION SHIELD MODELLING ON BORON NEUTRON CAPTURE THERAPY FACILITY USING D-D NEUTRON GENERATOR 2.4 MeV Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Based Studies were carried out to analyze the internal dose of radiation for workers at Boron Neutron Capture Therapy (BNCT) facility base on Cyclotron 30 MeV with BSA and a room that was actually designed before. This internal dose analyzation included interaction between neutrons and air. The air contained N2 (72%), O2 (20%), Ar (0.93%), CO2, Neon, Kripton, Xenon, Helium and Methane. That internal dose to the worker should be below the dose limit for radiation workers which is an amount of 20 mSv/years. From the particles that are present in the air, only Nitrogen and Argon can change into radioactive element. Nitrogen-14 activated to Carbon-14, Nitrogen-15 activated to Nitrogen-16, and Argon-40 activated to Argon-41. Calculation using tally facility in Monte Carlo N Particle version Extended (MCNPX) program for calculated Neutron flux in the air 3.16x107 Neutron/cm2s. The room design in the cancer facility has a measurement of 200 cm in length, 200 cm in width, and 166.40 cm in height. Neutron flux can be used to calculate the reaction rate which is 80.1x10-2 reaction/cm3s for carbon-14 and 8.75x10-5 reaction/cm3s. The internal dose exposed to the radiation worker is 9.08E-9 µSv.

In Vitro and In Vivo Test of Boron Delivery Agent for BNCT Sista Dyah Wijaya; Bagaswoto Poedjomartono; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

BNCT is an alternate therapy for treating cancer. The principle of BNCT involves a neutron boron uptake and a fission reaction that produce alpha particles and Li ions with a high level of linear energy transfer in the tissue. It is effective in killing tumor cells. To administer boron in the tumor cells, a boron delivery agent is needed. Thus far, there are a variety of boron delivery agents that have been developed. To date, just two main boron-based drugs, BPA and BSH, have been used for clinical studies. Many other boron delivery agents have been evaluated in vivo and in vitro but have not been evaluated clinically. Therefore, the other boron delivery agents have not been used in BNCT clinical studies.

Co-Authors Bagaswoto Poedjomartono Bagaswoto Poedjomartono Kusminarto Kusminarto Okti Dyah Rahayuningsih Sista Dyah Wijaya Susilo Susilo Susilo Susilo Vika Hutaria Wusko, Ikna Urwatul

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