Claim Missing Document
Check
Articles

Found 6 Documents
Search

DOSE DISTRIBUTION ANALYSIS OF PROTON THERAPY FOR MEDULLOBLASTOMA CANCER WITH PHITS 3.24 Moh. Miftakhul Dwi Fianto; Yohannes Sardjono; Andang Widi Harto; Isman Mulyadi Triatmoko; Gede Sutresna Wijaya; Yaser Kasesaz
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 24, No 1 (2022): February (2022)
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2022.24.1.6581

Abstract

One of the developments in particle therapy is proton radiation therapy. Meanwhile, a limited number of available proton therapy facilities makes research related to proton therapy difficult. Therefore, there is a need for alternative proton therapy simulations using programs other than those in proton therapy facilities. This research was aimed to simulate medulloblastoma brain cancer which children often experience.The program used in this research was PHITS version 3.24. The human body was modeled with the revised ORNL-MIRD phantom for a 10-year-old child. The therapy scheme was a whole posterior fossa boost of 19.8 Gy. The proton passive scattering was simulated by passing a uniform proton beam through the aperture and compensator with energy variations. The proton pencil beam scanning was simulated with small cylindrical beams with a radius of 0.5 cm, which were adjusted to the planning target volume with layers variations.The total duration to give the prescription dose was 550 seconds with passive scattering and 605 seconds with pencil beam scanning. In passive scattering, the OAR(s) with the most significant percentage of absorbed dose were the skin, cranium, and muscle, i.e., 8.22 ± 0.15 %, 5.51 ± 0.05 % and 1.39 ± 0,04 % respectively to their maximum tolerated dose, while in the pencil beam scanning, the OAR(s) with the most significant percentage of absorbed dose were the skin, cranium, and muscle, i.e., 5.42 ± 0.08 %, 4.43 ± 0.05 % and 0.51 ± 0.05 % respectively to their maximum tolerated dose. Dose distribution in passive scattering was relatively better than in pencil beam scanning in terms of dose homogeneity using dose sampling analysis at some points within the planning target volume.
PREDIKSI KESETIMBANGAN ADSORPSI URANIUM PADA AIR DAN BERBAGAI SEDIMEN Jasmi Budi Utami; Gede Sutresna Wijaya; Wahyudi Budi Sediawan; Bardi Murachman
Jurnal Forum Nuklir JFN Vol 9 No 1 Mei 2015
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (582.08 KB) | DOI: 10.17146/jfn.2015.9.1.3561

Abstract

PREDIKSI KESETIMBANGAN ADSORPSI URANIUM PADA  AIR DAN BERBAGAI SEDIMEN. Kegiatan penelitian, pengembangan, penambangan, dan pemurnian uranium berpotensi menimbulkan pencemaran lingkungan. Uranium merupakan salah satu logam berat berbahaya karena bersifat racun dan radioaktif sehingga perlu diketahui sampai sejauh mana sebaran uranium di lingkungan. Penelitian ini bertujuan meramalkan model kesetimbangan adsorpsi uranium yang dapat berlaku umum pada berbagai sedimen. Manfaat yang diharapkan dari penelitian ini adalah sebagai  data dukung bagi kegiatan analisis dampak lingkungan dalam pembangunan PLTN. Percobaan adsorpsi uranium dijalankan dalam sistem batch. Air limbah sebanyak 100 mL yang mengandung uranium dimasukkan ke dalam erlenmeyer dan pH larutan diatur menjadi 7. Sebanyak 0,5 g sedimen dengan berbagai kandungan bahan organik, dimasukkan ke dalam erlenmeyer. Erlenmeyer ditempatkan dalam shaker dengan kecepatan 100 rpm selama 6 jam dan dibiarkan selama 24 jam sampai tercapai kesetimbangan. Filtrat yang terbentuk disaring dan dianalisis menggunakan spektrofotometer.  Lima model kesetimbangan isotermal diajukan untuk mendekati data kesetimbangan. Kesetimbangan Chapman cocok dalam mendekati data percobaan pada berbagai sedimen dengan berbagai kadar bahan organik. Hasil olah data menunjukkan hanya bahan organik yang signifikan berperan dalam adsorpsi uranium. Berdasarkan asumsi hanya bahan organik yang mengadsorpsi uranium diajukan suatu metode yang dapat dipakai untuk meramalkan kesetimbangan adsorpsi uranium yang berlaku umum pada berbagai  sedimen. Sebagai hasil, kesetimbangan Chapman memiliki nilai parameter α, β, γ berturut-turt sebesar 255 mg/g bahan organik; 0,049 L/mg, dan 1,9.
Prediksi Kesetimbangan Adsorpsi Uranium pada Air dan Sedimen pada Berbagai pH Jasmi Budi Utami; Wahyudi Budi Sediawan; Bardi Murachman; Gede Sutresna Wijaya
Jurnal Rekayasa Proses Vol 7, No 2 (2013)
Publisher : Departemen Teknik Kimia Fakultas Teknik Universitas Gadjah Mada

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (686.109 KB) | DOI: 10.22146/jrekpros.4950

Abstract

Kegiatan yang melibatkan uranium sebagai bahan bakar nuklir berpotensi menimbulkan pencemaran lingkungan. Uranium merupakan salah satu logam berat berbahaya dan bersifat radioaktif sehingga perlu diketahui penyebarannya di alam. Penelitian ini bertujuan untuk menentukan model kesetimbangan adsorpsi uranium pada air dan sedimen. Model yang disusun diharapkan sesuai untuk berbagai pH air. Percobaan adsorpsi uranium dijalankan dalam sistem batch. Air limbah sebanyak 100 ml yang mengandung uranium dimasukkan ke dalam erlenmeyer dan pH larutan diatur menjadi 3, 5, 7, atau 9. Sebanyak 0,5 g tanah dimasukkan ke dalam erlenmeyer. Erlenmeyer ditempatkan dalam shaker dengan kecepatan 100 rpm selama 6 jam dan dibiarkan selama 24 jam sampai tercapai kesetimbangan. Filtrat yang terbentuk disaring dan dianalisis menggunakan spektrofotometer. Lima model kesetimbangan isotermal diajukan untuk mendekati data kesetimbangan. Sebagai hasil, kesetimbangan Chapman cocok dalam mendekati data percobaan pada berbagai pH air. Dari hasil perhitungan diketahui ion UO22+ memiliki nilai parameter α, β, γ masing-masing sebesar 25 mg/g, 2,3 l/mg, dan 18,1 sedangkan untuk ion (UO2)3(OH)7- masing-masing sebesar 19 mg/g, 0,095 l/mg, dan 3,4. Penelitian ini diharapkan bermanfaat sebagai data pendukung bagi analisis dampak lingkungan dalam pembangunan PLTN. Kata kunci: adsorpsi, kesetimbangan, uranium, prediksi, sedimen, pH Activities involving uranium as nuclear fuel has potentially polluted the environment. Since uranium is a toxic and radioactive heavy metal, it is necessary to identify its distribution in nature. This study aims to define uranium adsorption equilibrium model in water and sediment. The model is also supposed to be appropriate for various pH of water. Experiments were performed in a batch system. One hundred mL of waste water for National Atomic Energy Agency (BATAN) containing uranium was placed in an erlenmeyer flask and the pH was varied at 3, 5, 7, or 9. Soil was used as adsorbent. The process was shaken at 100 rpm for six hours and then was left for 24 hours to reach the equilibrium. The resulting filtrate was filtered and analyzed using a spectrophotometer. Five different isotherm equilibrium models were proposed in order to fit the equilibrium experimental data. It was found that Chapman equilibrium could fit the data more thoroughly than the other models. From the calculation, it was known that UO22+ parameter values of α, β, γ were 25 mg/g-soil, 2,3 l/mg, and 18,1 respectively, while for (UO2)3(OH)7- were 19 mg/g, 0,095 l/mg, and 3,4 respectively. It is expected that this research will be useful as supporting data for environment impact analysis in nuclear power plants development. Keywords: adsorption, equilibrium, uranium, sediment, pH
Prediksi Kesetimbangan Adsorpsi Uranium pada Air dan Sedimen pada Berbagai pH Jasmi Budi Utami; Wahyudi Budi Sediawan; Bardi Murachman; Gede Sutresna Wijaya
Jurnal Rekayasa Proses Vol 7, No 2 (2013)
Publisher : Departemen Teknik Kimia Fakultas Teknik Universitas Gadjah Mada

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22146/jrekpros.4950

Abstract

Kegiatan yang melibatkan uranium sebagai bahan bakar nuklir berpotensi menimbulkan pencemaran lingkungan. Uranium merupakan salah satu logam berat berbahaya dan bersifat radioaktif sehingga perlu diketahui penyebarannya di alam. Penelitian ini bertujuan untuk menentukan model kesetimbangan adsorpsi uranium pada air dan sedimen. Model yang disusun diharapkan sesuai untuk berbagai pH air. Percobaan adsorpsi uranium dijalankan dalam sistem batch. Air limbah sebanyak 100 ml yang mengandung uranium dimasukkan ke dalam erlenmeyer dan pH larutan diatur menjadi 3, 5, 7, atau 9. Sebanyak 0,5 g tanah dimasukkan ke dalam erlenmeyer. Erlenmeyer ditempatkan dalam shaker dengan kecepatan 100 rpm selama 6 jam dan dibiarkan selama 24 jam sampai tercapai kesetimbangan. Filtrat yang terbentuk disaring dan dianalisis menggunakan spektrofotometer. Lima model kesetimbangan isotermal diajukan untuk mendekati data kesetimbangan. Sebagai hasil, kesetimbangan Chapman cocok dalam mendekati data percobaan pada berbagai pH air. Dari hasil perhitungan diketahui ion UO22+ memiliki nilai parameter α, β, γ masing-masing sebesar 25 mg/g, 2,3 l/mg, dan 18,1 sedangkan untuk ion (UO2)3(OH)7- masing-masing sebesar 19 mg/g, 0,095 l/mg, dan 3,4. Penelitian ini diharapkan bermanfaat sebagai data pendukung bagi analisis dampak lingkungan dalam pembangunan PLTN. Kata kunci: adsorpsi, kesetimbangan, uranium, prediksi, sedimen, pH Activities involving uranium as nuclear fuel has potentially polluted the environment. Since uranium is a toxic and radioactive heavy metal, it is necessary to identify its distribution in nature. This study aims to define uranium adsorption equilibrium model in water and sediment. The model is also supposed to be appropriate for various pH of water. Experiments were performed in a batch system. One hundred mL of waste water for National Atomic Energy Agency (BATAN) containing uranium was placed in an erlenmeyer flask and the pH was varied at 3, 5, 7, or 9. Soil was used as adsorbent. The process was shaken at 100 rpm for six hours and then was left for 24 hours to reach the equilibrium. The resulting filtrate was filtered and analyzed using a spectrophotometer. Five different isotherm equilibrium models were proposed in order to fit the equilibrium experimental data. It was found that Chapman equilibrium could fit the data more thoroughly than the other models. From the calculation, it was known that UO22+ parameter values of α, β, γ were 25 mg/g-soil, 2,3 l/mg, and 18,1 respectively, while for (UO2)3(OH)7- were 19 mg/g, 0,095 l/mg, and 3,4 respectively. It is expected that this research will be useful as supporting data for environment impact analysis in nuclear power plants development. Keywords: adsorption, equilibrium, uranium, sediment, pH
PEMODELAN BNCT SHIELDING BERBAHAN PARAFIN DAN ALUMINIUM UNTUK FASILITAS MENGGUNAKAN SIMULATOR MCNP A CONCEPTUAL SHIELDING DESIGN USING PARAFFIN AND ALUMINIUM FOR BNCT FACILITY BY MCNP SIMULATOR Afifah Hana Tsurayya; Yosi Aprian Sari; Gede Sutresna Wijaya
Jurnal Ilmu Fisika dan Terapannya (JIFTA) Vol 6, No 5 (2017): Jurnal Fisika
Publisher : Prodi Fisika, Departemen Pendidikan Fisika

Show Abstract | Download Original | Original Source | Check in Google Scholar

Abstract

AbstrakTelah dilakukan penelitian yang bertujuan untuk mengetahui laju dosis radiasi setelah melewati shielding berbahan parafin dan aluminium serta mengetahui material shielding yang tepat untuk keselamatan pekerja radiasi. Penelitian ini menggunakan simulator MCNP untuk memodelkan sumber neutron BNCT dan shieldingDesain shielding harus dapat menahan radiasi hingga batas laju dosis maksimal sebesar 10,42 µSv/jam dengan asumsi nilai tersebut merupakan batasan yang paling konservatif, yakni dengan lama waktu pekerja 1920 jam dalam satu tahun. Desain awal menghasilkan laju dosis yang masih di atas batas maksimal, maka dari itu dilakukan optimasi dengan menambahkan timbal pada bagian terluar shielding. Hasil yang diperoleh setelah optimasi adalah laju dosis menurun setelah diberi lapisan timbal dengan ketebalan tertentu. Beberapa lokasi yang masih di atas standar diatasi dengan aspek proteksi radiasi yang lain, yaitu jarak dan waktu. Parafin diberi aluminium sebagai casing yang bertujuan untuk memperkuat struktur shielding, dan timbal ditambahkan untuk menyerap radiasi gamma. Kata kunci: BNCT, Shielding, Parafin, Aluminium, MCNPAbstract   The research was aimed to measure the radiation dose rate over the shielding which was made of paraffin and aluminium and to know the right shielding material for safety of radiation workers. The examination used MCNP (Monte Carlo N-Particle) simulator to model the BNCT neutron source and the shielding. The shielding should reduce the radiation to less than the dose limit of 10.42 µSv/hour, which is assumed to be the most conservative limit, i.e. whileduration of workers was 1920 hours. The first design resulted the radiation dose rate which was still above the limit. Therefore, optimization was done by adding the lead on the outer of the shielding. After optimization by adding the leads with certain layer, the radiation dose rate were decreasing. Some locations over the limit could be overcome by the other radiation protection aspect, i.e. distance and time. The paraffin blocks were covered by aluminium to keep the shielding structure, then the lead was used to absorb the gamma rays. Keywords: BNCT, Shieling, Paraffin, Aluminium, MCNP
The Simulation of Radiation Shielding Made of Portland Material in a 230 MeV 300 NA Cyclotron Room for Proton Therapy Facility Using PHITS Code System Damar Adhiwidya Suyanto; Aditya Tri Oktaviana; Yohannes Sardjono; Gede Sutresna Wijaya; Isman Mulyadi Triatmoko
Jurnal Engine: Energi, Manufaktur, dan Material Vol. 9 No. 2 (2025)
Publisher : Proklamasi 45 University

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.30588/jeemm.v9i2.2339

Abstract

This study investigates the effectiveness of radiation shielding made from Portland material in a 230 MeV, 300 NA cyclotron room for a proton therapy facility. Proton therapy is an advanced treatment method for cancer that uses protons to irradiate tumors with high precision. However, the high energy of protons requires effective shielding to protect the surrounding environment and personnel from radiation exposure. In this research, the radiation shielding performance of Portland material was evaluated using the PHITS (Particle and Heavy Ion Transport System) version 3.351 simulation software. The study focuses on assessing the attenuation of radiation within the cyclotron room under various operational conditions. The results from PHITS simulations provide insights into the potential of Portland material in reducing radiation levels in proton therapy rooms, contributing to the safety and efficiency of such facilities. This analysis is essential for optimizing shielding design.