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Juliyanto S, Dita Pertiwi L, Nurmanjaya A, Pujiyanto A, Setiawan H, Rindiyantono F, Abidin, Fikri A, Putra AR, Forentin AM, Susilo VY, Febrian MB, Ritawidya R, Yulizar Y. Phytosynthesis of gold-198 nanoparticles for a potential therapeutic radio-photothermal agent. Appl Radiat Isot 2024; 204:111141. [PMID: 38071856 DOI: 10.1016/j.apradiso.2023.111141] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/14/2023] [Revised: 11/22/2023] [Accepted: 12/04/2023] [Indexed: 12/31/2023]
Abstract
We produced spherical gold-198 nanoparticles with an average size of 41 nm, good stability, and high radiochemical purity for a promising single agent of radio-photothermal therapy using Curcuma longa rhizome extract as a reducing and capping agent. The combination of in vitro treatment using gold-198 nanoparticles and irradiation of 980 nm wavelength lasers with a power output of 2 W/cm2 induced hyperthermia temperature and exhibited enhancement of the percentage dead on MDA-MB-123 cancer cells compared to gold-198 nanoparticles alone.
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Affiliation(s)
- Sumandi Juliyanto
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia; Department of Chemistry, Faculty of Mathematics and Natural Sciences, Universitas Indonesia, Depok, 16424, Indonesia.
| | - Ligwina Dita Pertiwi
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Ahid Nurmanjaya
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Anung Pujiyanto
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Herlan Setiawan
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Fernanto Rindiyantono
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Abidin
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Ahsanal Fikri
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia; Department of Chemistry, Faculty of Mathematics and Natural Sciences, Universitas Indonesia, Depok, 16424, Indonesia
| | - Amal Rezka Putra
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Alfian Mahardika Forentin
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Veronika Yulianti Susilo
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Muhamad Basit Febrian
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Rien Ritawidya
- Research Center for Radioisotope, Radiopharmaceutical, and Biodosimetry Technology, Research Organization for Nuclear Energy-National Research and Innovation Agency, BRIN, Puspiptek Area, South Tangerang, 15314, Indonesia
| | - Yoki Yulizar
- Department of Chemistry, Faculty of Mathematics and Natural Sciences, Universitas Indonesia, Depok, 16424, Indonesia
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Feasibility of 153Sm production using MNSR research reactor through a multi-stage approach. Appl Radiat Isot 2018; 139:195-200. [PMID: 29803141 DOI: 10.1016/j.apradiso.2018.04.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 01/04/2018] [Revised: 03/19/2018] [Accepted: 04/18/2018] [Indexed: 11/23/2022]
Abstract
The main objective of this study was to explore the feasibility of producing 153Sm radioisotope in miniature neutron source reactors (MNSRs) in Isfahan-Iran. As the first step of this study, the MNSR's geometry was created by using the MCNP6.2 simulation code and afterwards a validity check was performed by comparing the results with the experimental data. Then, by applying values obtained through simulation, the production process was followed up to 20 irradiation cycles using different irradiation and cooling periods (irradiation setups). The results showed that the proposed simulation technique has an acceptable agreement with the experiments (with a difference of nearly 6%). In spite of limitations, such as irradiation time and flux in such reactors, our results showed that by choosing the correct irradiation setup, it is possible to produces 153Sm up to 852.26 mCi g-1 in 20 successive irradiation cycles. However, after the 10th cycle, the production reached 90% of the maximum point. Nevertheless, the continuance of the irradiation process with a new target (by 10 plus 10 discrete irradiation) can double the total activity in comparison with 20 successive irradiation cycles, without any increase in the fuel consumption of the reactor. These findings increase the prospect of a large-scale production of the life-saving 153Sm radioisotope in MNSR reactors.
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