Ade Saputra

@brin.go.id

Research Center for Nuclear Material and Radioactive Waste
National Research and Innovation Agency

Ade Saputra


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https://researchid.co/ade_saputra

RESEARCH, TEACHING, or OTHER INTERESTS

Inorganic Chemistry, Nuclear Energy and Engineering, Chemistry, Renewable Energy, Sustainability and the Environment
9

Scopus Publications

16

Scholar Citations

2

Scholar h-index

Scopus Publications

  • Tunable deoxygenation routes during lauric acid upgrading over reusable Cu-doped ZIF-67 catalysts
    Holanda Ramadhita, Monica Lestari, Gizky Dwi Andana, Kautsaradea Asabila, Aditia Nur Bakti, Fauzan Aulia, Ade Saputra, Lina Jaya Diguna, Fidelis Stefanus Hubertson Simanjuntak, Deliana Dahnum
    Journal of Analytical and Applied Pyrolysis, 2026
  • Neutronic analysis of U-7Mo-xTi/Al fuel elements as replacement candidates for Indonesia’s RSG-GAS research reactor fuel: Enrichment optimisation, burnup behaviour, and temperature coefficients
    Fikri A. Furqan, Deni Mustika, Saga Octadamailah, Mu’nisatun Sholikhah, G.K. Suryaman, Ade Saputra, Supardjo
    Annals of Nuclear Energy, 2026
  • NoisyAdamW: A novel optimizer for EfficientNetB0-UNet (EffB0-UNet) in low-grade glioma segmentation
    Julfa Muhammad Amda, Arya Adhyaksa Waskita, Ade Saputra, Niken Siwi Pamungkas, Zico Pratama Putra, Dede Sutarya, Sita Gandes Pinasti, M. Arif Efendi, Fitrotun Aliyah, Muhammad Yusuf, Dwi Seno Kuncoro Sihono
    Signal Image and Video Processing, 2026
  • Strategic utilization of covalent organic frameworks for uranium adsorption from high concentrate U–Th monazite sand: a review
    Ade Saputra, Iman Abdullah, Deliana Dahnum, Deni Mustika, Putra Oktavianto, Ainun Zakiah Noor, Niken Siwi Pamungkas, Muhammad Yusuf
    Journal of Radioanalytical and Nuclear Chemistry, 2025
  • Exploring The Heat-Treated Ammonium Diuranate Fingerprint for Nuclear Forensics
    Torowati Torowati, Ngatijo Ngatijo, Ade Saputra, Slamet Pribadi, Fikri Ahmad Furqon, Jan Setiawan
    Aip Conference Proceedings, 2024
    Uranium ore concentrate plays an essential role in the fabrication of uranium dioxide. Uranium ore concentrate as ammonium diuranate (ADU) is an intermediate nuclear material, making it one of the materials of concern in nuclear forensics. In industrial processes, ADU was dried at the temperature range of 120 – 400 °C and the calcination process in the temperature range of 400 – 850 °C, which allows for changes in morphology and structure. The final product is very dependent on the starting material. The ADU powder from the pilot conversion plant (PCP) – BRIN needed to be characterized for its fingerprint. Heat treatment was varied at 250 °C, 300 °C, and 400 °C with an air atmosphere. Characterization included uranium content, morphological observations using a Scanning Electron Microscope (SEM), and revealing the phase composition using X-Ray diffraction (XRD). The results showed that the uranium content increased with increasing temperature, the highest at a temperature of 400 °C, where the uranium content is 79.66 ± 0.51%. Visually, the pore size of the powder is getting smaller, and the amount decreases with increasing temperature. In ADU powder, before heat treatment consists of two phases, and after the heat treatment forms three phases. The results of this characterization can be devoted to a nuclear forensics database of nuclear and radioactive materials.
  • Comparison of UO2 Powder Products From Reduction Process Using Rotary Kiln H-1102 and Muffle Furnace ME-11 at Pilot Conversion Plant (PCP) Facility
    Putra Oktavianto, Ade Saputra, Nelsa Rahmita, Andri Saputra, Imam Abdurrosyid, Triarjo Triarjo, Sugeng Rianto
    Aip Conference Proceedings, 2024
    On the commissioning of the pilot conversion plant (PCP) facility in 2013, UO2 powder was produced, but it did not fulfill the required specifications. The rotary kiln H-1102 which is used in the final process to reduction U3O8 powder to UO2 powder is also often damaged so that the production of nuclear grade UO2 powder has trouble. Because it, a substitutive tool is needed for the reduction process. One alternative that can be used is the muffle furnace ME-11. The product from the muffle furnace ME-11 was compared with the rotary kiln H-1102 product to find out which one produced better quality. The tests carried out were testing the levels of uranium with an acceptable limit of > 87% and the content of impurities in the UO2 powder product. In the levels of uranium testing of the UO2 powder produced by the muffle furnace ME-11, the levels of uranium 86.95±0.92% were obtained, while in the rotary kiln H-1102 product is 83.43±0 59%. The resulting content of impurities above the allowed acceptance limit in the muffle furnace ME-11 numbered 5 elements, while the H-1102 rotary kiln 9 elements. Judging from its levels of uranium, the rotary kiln H-1102 UO2 powder product does not fulfill the specifications, while the muffle furnace ME-11 results are acceptable. Meanwhile, judging from the content of the impurities, the two tools have not fulfilled the required specifications. So, it can be concluded that the UO2 powder produced by both tools do not fulfill the specifications to be used as nuclear grade fuel. In comparison, UO2 powder products using the muffle furnace ME-11 are closer to the required specifications. To obtain nuclear grade UO2 powder, it is necessary to re-purify the produced UO2 powder to reduce the content of impurities that are still above the acceptable limit.
  • Precipitation of Uranium from Uranium Liquid Waste Generated in Yellow Cake Conversion using NaH2PO4 and NaOH
    Jaka Rachmadetin, Ade Saputra, Dwi Luhur Ibnu Saputra, Maman Kartaman, Kuat Heriyanto, Wati Wati, Mirawaty Mirawaty, Gustri Nurliati, Aisyah Aisyah
    Aip Conference Proceedings, 2024
    The operation of pilot conversion plant in Serpong Nuclear Area to produce nuclear grade uranium dioxide from yellow cake generated liquid waste containing uranium. This uranium liquid waste remains problematic because the existing treatment processes for radioactive waste in the radioactive waste processing installation is yet to accommodate liquid waste which contained uranium. Therefore, the study for treatment of this kind of waste is necessary to support the radioactive waste management and to maintain the sustainability of the operation of the pilot conversion plant. The objective of this work is to recover uranium in the liquid waste by precipitation, thus decreasing the concentration of uranium in the liquid waste. The study was carried out by simulation using PHREEQC code and direct precipitation experiment with NaH2PO4 and NaOH as precipitating agents. The aqueous uranium in the liquid waste was precipitated with the addition of each of precipitating agent in a beaker glass to produce uranium precipitates. After the precipitation, the precipitates and the supernatant were separated by centrifugation. The uranium precipitates obtained from the experiment were washed with deionized water and ethanol. Then, a small portion of the precipitates was taken and coated with sputtered gold prior to analysis using SEM-EDS. The supernatant, meanwhile, was filtered and the concentration of uranium in the filtrate was determined using ICP-OES. The results shows that uranium precipitates with NaH2PO4 were crystalline, whereas with NaOH were amorphous. The initial concentration of uranium in the liquid waste was 2878 mg/l, whereas after the precipitation the concentration became approximately 1 mg/l. These values correspond to 99.9% aqueous removal by precipitation with those precipitating agents which indicates that this method is promising to be further developed for uranium liquid waste treatment.
  • Development of Small Modular Reactor iPWR Dynamics Simulator
    R Alfariji, S P Nurhidayah, S Bakhri, M Subekti, Kiswanta, Sudarno, A Saputra
    Journal of Physics Conference Series, 2024
    In the energy transition era, nuclear power serves as a significant source of electricity with low emissions, contributing to approximately 10% of the world’s total electricity production. The advanced and distinct features of iPWR-type SMR in the field of nuclear power generation contribute to a greater safety margin. This opens up possibilities for extending the utilization of secure, environmentally friendly, and dependable nuclear energy across various energy sectors. Moreover, the public need to understand the technical performance of the iPWR. To improve understanding of iPWR’s technical performance, a simulator is developed. The simulator is developed to provide a comprehensive study of nuclear reactor transient behavior, to serve as an educational tool for students, and to demonstrate the safety features during accident scenarios. This article introduces a simulator that combines modules of neutronics, reactor thermal-hydraulics, and the NSSS. The simulator uses the design parameters of iPWR with a power capacity of 160 MWt that relies on natural convection. The proposed simulator was developed using LabVIEW software to perform the reactor dynamics calculations. Furthermore, hardware devices for controlling the simulator can be integrated to simulate the control room of an NPP. The calculation was based on the standard lumped parameter point kinetics and thermal-hydraulic equations. To simplify the process and reduce computational cost, several assumptions are incorporated into the equations, including one-group thermal neutron and constant gain thermal power. The simulator development yields preliminary data for reactor calculations, the graphical user interface (GUI) of the simulator, and the Virtual Instruments (VIs) comprising the reactor model. The reactor model comprises multiple components, each represented as a subVI within the LabVIEW environment. This simulator serves as an effective educational and dissemination tool for increasing public acceptance of NPP by providing insights into the behavior of the reactor and facilitating a better understanding of its operation, safety features, and potential benefits.
  • Development of yellowcake powder feeding system in dissolver unit at pilot conversion plant (PCP)
    Ade Saputra, Nelsa Rahmita, Putra Oktavianto, Islah Mukminati, Agus Sartono, Imam Abdurrosyid, Anwar Muchsin
    Aip Conference Proceedings, 2023

RECENT SCHOLAR PUBLICATIONS

  • NoisyAdamW: A novel optimizer for EfficientNetB0-UNet (EffB0-UNet) in low-grade glioma segmentation: JM Amda et al.
    JM Amda, AA Waskita, A Saputra, NS Pamungkas, ZP Putra, D Sutarya, ...
    Signal, Image and Video Processing 20 (5), 303 , 2026
    2026
  • Neutronic analysis of U-7Mo-xTi/Al fuel elements as replacement candidates for Indonesia’s RSG-GAS research reactor fuel: Enrichment optimisation, burnup behaviour, and …
    FA Furqan, D Mustika, S Octadamailah, M Sholikhah, GK Suryaman, ...
    Annals of Nuclear Energy 229, 112091 , 2026
    2026
  • Strategic utilization of covalent organic frameworks for uranium adsorption from high concentrate U–Th monazite sand: a review
    A Saputra, I Abdullah, D Dahnum, D Mustika, P Oktavianto, AZ Noor, ...
    Journal of Radioanalytical and Nuclear Chemistry 334 (6), 3843-3864 , 2025
    2025
    Citations: 2
  • INTEGRATION OF SAFETY ANALYSIS USING HAZOPS AND FTA ON PRECIPITATION PROCESS IN URANIUM REFINING AND CONVERSION FACILITY
    P Oktavianto, A Saputra, M Sholikhah
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 31 (1), 57-66 , 2025
    2025
  • FORMULASI INHIBITOR KOROSI BERBASIS ZINK–FOSFAT DAN MIKO–DEA PADA PIPA PENDINGIN SEKUNDER REAKTOR SERBA GUNA GERRIT AUGUSTINUS SIWABESSY
    R Kriswarini, A Insani, M Khotib, K Sutriah, A Nugroho, JC Sihotang, ...
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 30 (2), 109–122-109–122 , 2024
    2024
  • PROSES REKOVERI, PEMURNIAN DAN KONVERSI URANIUM DARI EFLUEN PROSES DI PILOT CONVERSION PLANT (PCP)
    N Rahmita, K Sunandar, A Saputra, P Oktavianto, A Sari
    Technopex 2024 , 2024
    2024
  • PENGOLAHAN URANIUM DALAM BENTUK YELLOW CAKE COGEMA MENJADI SERBUK UO2 SEBAGAI BAHAN BAKAR REAKTOR NUKLIR DI FASILITAS NUKLIR SERPONG
    P Oktavianto, A Saputra, A Saputra
    JURNAL TEKNOLOGI KIMIA MINERAL 3 (1), 1-9 , 2024
    2024
    Citations: 1
  • Comparison of UO 2 powder products from reduction process using rotary kiln H-1102 and muffle furnace ME-11 at pilot conversion plant (PCP) facility
    P Oktavianto, A Saputra, N Rahmita, A Saputra, I Abdurrosyid, T Triarjo, ...
    AIP Conference Proceedings 2967 (1), 110008 , 2024
    2024
    Citations: 1
  • Precipitation of uranium from uranium liquid waste generated in yellow cake conversion using NaH 2 PO 4 and NaOH
    J Rachmadetin, A Saputra, DLI Saputra, M Kartaman, K Heriyanto, W Wati, ...
    AIP Conference Proceedings 2967 (1), 180005 , 2024
    2024
    Citations: 1
  • Development of yellowcake powder feeding system in dissolver unit at pilot conversion plant (PCP)
    A Saputra, N Rahmita, P Oktavianto, I Mukminati, A Sartono, I Abdurrosyid, ...
    AIP Conference Proceedings 2893 (1), 040001 , 2023
    2023
  • Peningkatan Kemampuan Mesin Bubut untuk Pemesinan Proses Freis dengan Menambahkan Alat Bantu Cekam
    D Wicaksono, M Yanis, A Saputra
    Rekayasa Mesin 23 (2), 49-53 , 2023
    2023
    Citations: 2
  • Safety integrity level assessment at uranium evaporator and deposition vessel in non nuclear reactor installations
    P Oktavianto, AN Kundari, A Saputra, I Abdurrosyid, M Sholikhah, ...
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 29 (1), 11-20 , 2023
    2023
  • PENGEMBANGAN SISTEM MONITORING PROSES PEMURNIAN DI INSTALASI PEMURNIAN DAN KONVERSI
    S Rianto, JM Amda, T Triarjo, A Saputra, H Ghufron, R Langenati
    PROSIDING SNAST, D1-9 , 2022
    2022
  • STUDI KELAYAKAN YELLOWCAKE HASIL SAMPING PETROKIMIA GRESIK SEBAGAI BAHAN BAKU PROSES PEMURNIAN DAN KONVERSI DI FASILITAS PILOT CONVERSION PLANT
    A Saputra, E Yusnitha, I Abdurrosyid, R Langenati
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 27 (2), 93-102 , 2021
    2021
    Citations: 1
  • Utilization of the yellow cake pilot conversion plant (PCP) dissolution unit as an evaporator for uranium waste liquid
    A Saputra, YD Agus, H Ghufron, A Sari
    2019
  • Production of UO2 powder through yellow cake conversion process using pilot conversion plant facilities in Center for Nuclear Fuel technology-BATAN
    A Sartono, A Saputra
    Proceedings of ALTA 2019 Uranium-REE Sessions including Developments in IX … , 2019
    2019
  • Pendayagunaan Unit Pelarutan Yellow Cake Pilot Conversion Plant (PCP) Sebagai Evaporator Cairan Limbah Uranium
    A Saputra, A Saputra, YDA Susanto, H Ghufron, H Ghufron, AS Sari
    Pengelolaan Instalasi Nuklir 12 (23), 519970 , 2019
    2019
    Citations: 2
  • Kontrol Parameter pada Proses Pemekatan Seksi 600 di Instalasi Pemurnian dan Konversi (PCP)
    P Oktavianto, A Ariyanita, A Saputra
    Maj. Ilm. PIN 11 (20), 61-70 , 2018
    2018
    Citations: 3
  • The drying process of ammonium diuranate (ADU) in the pilot conversion plant (PCP) laboratory was carried out using the spray dryer Dr-1100
    A Sartono, D Sutarya, A Saputra
    2018
  • PROSES PENGERINGAN LARUTAN AMONIUM DIURANAT (ADU) MENGGUNAKAN SPRAY DRYER DR-1100
    ASD Santosa, DS Sutarya, A Saputra
    PIN Pengelolaan Instalasi Nuklir, Vol. 12 No. 21 12 (21), 1-11 , 2018
    2018
    Citations: 2

MOST CITED SCHOLAR PUBLICATIONS

  • Kontrol Parameter pada Proses Pemekatan Seksi 600 di Instalasi Pemurnian dan Konversi (PCP)
    P Oktavianto, A Ariyanita, A Saputra
    Maj. Ilm. PIN 11 (20), 61-70 , 2018
    2018
    Citations: 3
  • Strategic utilization of covalent organic frameworks for uranium adsorption from high concentrate U–Th monazite sand: a review
    A Saputra, I Abdullah, D Dahnum, D Mustika, P Oktavianto, AZ Noor, ...
    Journal of Radioanalytical and Nuclear Chemistry 334 (6), 3843-3864 , 2025
    2025
    Citations: 2
  • Peningkatan Kemampuan Mesin Bubut untuk Pemesinan Proses Freis dengan Menambahkan Alat Bantu Cekam
    D Wicaksono, M Yanis, A Saputra
    Rekayasa Mesin 23 (2), 49-53 , 2023
    2023
    Citations: 2
  • Pendayagunaan Unit Pelarutan Yellow Cake Pilot Conversion Plant (PCP) Sebagai Evaporator Cairan Limbah Uranium
    A Saputra, A Saputra, YDA Susanto, H Ghufron, H Ghufron, AS Sari
    Pengelolaan Instalasi Nuklir 12 (23), 519970 , 2019
    2019
    Citations: 2
  • PROSES PENGERINGAN LARUTAN AMONIUM DIURANAT (ADU) MENGGUNAKAN SPRAY DRYER DR-1100
    ASD Santosa, DS Sutarya, A Saputra
    PIN Pengelolaan Instalasi Nuklir, Vol. 12 No. 21 12 (21), 1-11 , 2018
    2018
    Citations: 2
  • PENGOLAHAN URANIUM DALAM BENTUK YELLOW CAKE COGEMA MENJADI SERBUK UO2 SEBAGAI BAHAN BAKAR REAKTOR NUKLIR DI FASILITAS NUKLIR SERPONG
    P Oktavianto, A Saputra, A Saputra
    JURNAL TEKNOLOGI KIMIA MINERAL 3 (1), 1-9 , 2024
    2024
    Citations: 1
  • Comparison of UO 2 powder products from reduction process using rotary kiln H-1102 and muffle furnace ME-11 at pilot conversion plant (PCP) facility
    P Oktavianto, A Saputra, N Rahmita, A Saputra, I Abdurrosyid, T Triarjo, ...
    AIP Conference Proceedings 2967 (1), 110008 , 2024
    2024
    Citations: 1
  • Precipitation of uranium from uranium liquid waste generated in yellow cake conversion using NaH 2 PO 4 and NaOH
    J Rachmadetin, A Saputra, DLI Saputra, M Kartaman, K Heriyanto, W Wati, ...
    AIP Conference Proceedings 2967 (1), 180005 , 2024
    2024
    Citations: 1
  • STUDI KELAYAKAN YELLOWCAKE HASIL SAMPING PETROKIMIA GRESIK SEBAGAI BAHAN BAKU PROSES PEMURNIAN DAN KONVERSI DI FASILITAS PILOT CONVERSION PLANT
    A Saputra, E Yusnitha, I Abdurrosyid, R Langenati
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 27 (2), 93-102 , 2021
    2021
    Citations: 1
  • PEMBUATAN SERBUK UO2 DARI YELLOW CAKE COGEMA DI PILOT CONVERSION PLANT (PCP)
    A Muchsin, A Saputra, A Sartono, A Ariyanita, I Mukminati
    Hasil-hasil penelitian EBN Tahun 2018, 27-36 , 2018
    2018
    Citations: 1
  • NoisyAdamW: A novel optimizer for EfficientNetB0-UNet (EffB0-UNet) in low-grade glioma segmentation: JM Amda et al.
    JM Amda, AA Waskita, A Saputra, NS Pamungkas, ZP Putra, D Sutarya, ...
    Signal, Image and Video Processing 20 (5), 303 , 2026
    2026
  • Neutronic analysis of U-7Mo-xTi/Al fuel elements as replacement candidates for Indonesia’s RSG-GAS research reactor fuel: Enrichment optimisation, burnup behaviour, and …
    FA Furqan, D Mustika, S Octadamailah, M Sholikhah, GK Suryaman, ...
    Annals of Nuclear Energy 229, 112091 , 2026
    2026
  • INTEGRATION OF SAFETY ANALYSIS USING HAZOPS AND FTA ON PRECIPITATION PROCESS IN URANIUM REFINING AND CONVERSION FACILITY
    P Oktavianto, A Saputra, M Sholikhah
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 31 (1), 57-66 , 2025
    2025
  • FORMULASI INHIBITOR KOROSI BERBASIS ZINK–FOSFAT DAN MIKO–DEA PADA PIPA PENDINGIN SEKUNDER REAKTOR SERBA GUNA GERRIT AUGUSTINUS SIWABESSY
    R Kriswarini, A Insani, M Khotib, K Sutriah, A Nugroho, JC Sihotang, ...
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 30 (2), 109–122-109–122 , 2024
    2024
  • PROSES REKOVERI, PEMURNIAN DAN KONVERSI URANIUM DARI EFLUEN PROSES DI PILOT CONVERSION PLANT (PCP)
    N Rahmita, K Sunandar, A Saputra, P Oktavianto, A Sari
    Technopex 2024 , 2024
    2024
  • Development of yellowcake powder feeding system in dissolver unit at pilot conversion plant (PCP)
    A Saputra, N Rahmita, P Oktavianto, I Mukminati, A Sartono, I Abdurrosyid, ...
    AIP Conference Proceedings 2893 (1), 040001 , 2023
    2023
  • Safety integrity level assessment at uranium evaporator and deposition vessel in non nuclear reactor installations
    P Oktavianto, AN Kundari, A Saputra, I Abdurrosyid, M Sholikhah, ...
    Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir 29 (1), 11-20 , 2023
    2023
  • PENGEMBANGAN SISTEM MONITORING PROSES PEMURNIAN DI INSTALASI PEMURNIAN DAN KONVERSI
    S Rianto, JM Amda, T Triarjo, A Saputra, H Ghufron, R Langenati
    PROSIDING SNAST, D1-9 , 2022
    2022
  • Utilization of the yellow cake pilot conversion plant (PCP) dissolution unit as an evaporator for uranium waste liquid
    A Saputra, YD Agus, H Ghufron, A Sari
    2019
  • Production of UO2 powder through yellow cake conversion process using pilot conversion plant facilities in Center for Nuclear Fuel technology-BATAN
    A Sartono, A Saputra
    Proceedings of ALTA 2019 Uranium-REE Sessions including Developments in IX … , 2019
    2019