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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega JURNAL ILMIAH PENDIDIKAN FISIKA AL BIRUNI Jurnal Fisika FLUX Jurnal Pendidikan Fisika dan Teknologi
Gusti Atika Urfa
Universitas Lambung Mangkurat
Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Materials Science & Nanotechnology Physics

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Neutron Generated during Proton Bombardment in Water Molecule Gusti Atika Urfa; Nurma Sari; Amar Vijai Nasrulloh
Jurnal Fisika Flux: Jurnal Ilmiah Fisika FMIPA Universitas Lambung Mangkurat Vol 20, No 1 (2023): Jurnal Fisika Flux: Jurnal Ilmiah Fisika FMIPA Universitas Lambung Mangkurat
Publisher : Lambung Mangkurat University Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.20527/flux.v20i1.14684

Abstract

Proton therapy is a treatment modality which can deliver dose precisely to cancer tumor in comparison to photon therapy, However, study about the biological effect of proton therapy are not well known. In this study, simulation of proton bombardment with energy 110 MeV to water is conducted using Geant4 software. The selection of water as the object of proton bombardment due to majority of human body is consisted of water. Water molecule in this simulation is a cube shaped with 10 x 10 x 10 cmand surrounded by PMMA material with 0.5 cm thickness. From the simulation results, it can be seen that <2% neutrons particle are formed due to the interaction of proton particles with water material. Small dose of neutron can be dangerous for body because it has high biological effectiveness and thus even a small absorbed dose might cause negative side effects in the patient.
Study of Alternative Radiation Material Shielding for Gamma Radiation using Monte Carlo Simulation Urfa, Gusti Atika; Wianto, Totok; Manik, Tetti Novalina; Nasrulloh, Amar Vijai
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 25, No 3 (2023): October 2023
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2023.6925

Abstract

Lead as the most commonly used material for radiation shielding but possessing toxic properties. This research aims to identify alternative, lead-free, and non-toxic materials for gamma radiation shielding through Monte Carlo simulations. Bismuth Oxide (Bi2O3), Barium Oxide (BaO), Tungsten Trioxide (WO3), Tungsten Dioxide (WO2), and Molybdenum Trioxide (MoO3) were selected as potential substitutes for lead. Pure lead (Pb) and Lead Oxide (PbO) were used for comparison. The simulation were performed using Particle Heavy Ion Tracking System (PHITS) software, with a gamma energy of 662 keV. The result of the simulation shows that the linear attenuation coefficient values for Pb and PbO were 0.902 mm-1 and 0.74 mm-1, respectively. Meanwhile, the simulation results of those simulated materials that are closest to Pb and PbO are Bi2O3 and WO2 with an attenuation coefficient of 0.71 mm-1. This simulation shows that for non-lead materials, BiO2 and WO2 have potential as alternative of non-lead radiation shielding.
Comparison of Dose Distribution in Proton and Gamma Radiation for Cervical Cancer Using Monte Carlo Simulation Urfa, Gusti Atika; Kartika, Listiana; Fitrianti, Intan; Seftina, Rahmi; Rachman, Rezky Rachmadhany; Wianto, Totok; Sudarningsih, Sudarningsih; Suarso, Eka
Jurnal Ilmiah Pendidikan Fisika Al-Biruni Vol 14 No 1 (2025): Jurnal Ilmiah Pendidikan Fisika Al-Biruni
Publisher : Universitas Islam Negeri Raden Intan Lampung, Indonesia

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.24042/jipfalbiruni.v14i1.25083

Abstract

Precision in radiation dose delivery is critical in cervical cancer treatment to ensure effective tumor control while minimizing damage to surrounding healthy tissues. Given the increasing adoption of advanced radiation therapies, comparative studies on dose distribution between different modalities are essential for evidence-based treatment planning. This study aims to compare the dose absorption in cervical cancer treatment using proton and gamma radiation through Monte Carlo simulation modeling. A Monte Carlo simulation was conducted using the Particle and Heavy Ion Transport code System (PHITS). Proton beams with an energy of 120 MeV and gamma rays at 30 MeV were applied from the anteroposterior (AP) direction using a pencil beam configuration (1 mm × 1 mm). Anatomical data were obtained from Digital Imaging and Communications in Medicine (DICOM) files sourced from RSUD Ulin Banjarmasin. Dose distribution was assessed in the target region and organs at risk (OAR). The results showed that proton therapy delivered a higher absorbed dose to the cervical target area (34.5 ± 1.5 MeV) than gamma radiation (16.7 ± 2.3 MeV). While both conformed to ICRU Report No. 78, gamma radiation resulted in higher doses to nearby organs such as the rectum and bladder, indicating a greater risk of radiation-induced side effects. Proton therapy offers more targeted dose delivery with reduced exposure to surrounding organs, making it a potentially safer and more effective modality for cervical cancer treatment. These findings underscore the importance of modality selection in optimizing therapeutic outcomes and minimizing complications in radiotherapy.
Monte Carlo Simulation to Test the Effectiveness of Crystal Detector Length for PHITS-Based PET Modality Urfa, Gusti Atika; Sari, Nurma; Wianto, Totok; Wahyono, Sri C; Fahrudin, Arfan E; Nasrulloh, Amar V
Jurnal Pendidikan Fisika dan Teknologi (JPFT) Vol 9 No 1 (2023): Januari - Juni
Publisher : Department of Physics Education, Universitas Mataram

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.29303/jpft.v9i1.4896

Abstract

PET (Positron-emission tomography) is used to determine physiological and metabolic functions in the body. Monte Carlo simulation is an important part of PET imaging, and the Particle Heavy Ion Transport code System (PHITS) is a simulation platform that can be used to perform Monte Carlo simulations. This study uses a Monte Carlo simulation based on PHITS to determine the range of gamma absorption with an energy of 511 keV in a scintillation detector crystal material. The gamma absorption range determines the effective crystal length in the PET modality. The simulation process is carried out by shooting Gamma at various types of materials, which are the materials used in PET scintillation crystals. The materials used in this simulation are NaI (Sodium Iodide), BaF2 (Barium Florida), BGO (Bismuth Germanate), and GSO (Gadolinium Oxyorthosilicate), considering their atomic number and crystal density. The crystal material is capable of absorbing gamma radiation with an energy of 511 keV with detailed crystal lengths for each NaI crystal of 0.26 cm; 0.25 cm BaF2 crystals; 0.1cm BGO crystals; and 0.18 cm GSO crystals. The crystal length from this simulation is smaller than the commercially available crystal length (range 1-3 cm). Based on the crystal length data, the most effective crystal for absorbing gamma radiation is the BGO crystal.
Co-Authors Amar Vijai Nasrulloh Fahrudin, Arfan E Intan Fitrianti, Intan Kartika, Listiana Manik, Tetti Novalina Nasrulloh, Amar V Nasrulloh, Amar Vijai Nurma Sari Nurma Sari, Nurma Rachman, Rezky Rachmadhany Seftina, Rahmi Suarso, Eka Sudarningsih Sudarningsih Totok Wianto Wahyono, Sri C