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All Journal Jurnal Penelitian Saintek Jurnal Ilmu Dasar POSITRON SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir JURNAL FISIKA Jurnal Fisika Unand SEMIRATA 2015 JOURNAL ONLINE OF PHYSICS Jurnal Fisika FLUX Science and Technology Indonesia Jurnal Pengabdian UntukMu NegeRI Jurnal Penelitian Sains PROSIDING SEMINAR NASIONAL FISIKA (E-JOURNAL) Jurnal Riset Fisika Indonesia
Fiber Monado
Department Of Physics, Faculty Of Mathematics And Natural Sciences, Sriwijaya University, Palembang, 30662, Indonesia
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ANALISIS NEUTRONIK KEKRITISAN TERAS REAKTOR NUSCALE BERBAHAN BAKAR DENGAN MENGGUNAKAN SOFTWARE OPENMC Canti Dwi Putri; Fiber Monado; Menik Ariani
JOURNAL ONLINE OF PHYSICS Vol. 8 No. 1 (2022): JOP (Journal Online of Physics) Vol 8 No 1
Publisher : Prodi Fisika FST UNJA

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.22437/jop.v8i1.20812

Abstract

[Title: Neutronic Analysis of the criticality level of the nuscale reactor core with fuel using the openMC software] This study analyzed the design of the NuScale reactor, which aims to determine the level of criticality by modeling the shape of the cell pin, assembly, and core with nuclear fuel in the form of uranium dioxide, which will be varied by changing the percentage of uranium-235 content as much as 0% to 7% by using monte carlo methods in OpenMC program code. This study was conducted to obtain the design of nuclear reactors as well as the calculation of the effective multiplication factor, fission reaction rate, and neutron flux distribution for two years of the combustion process (Burn-up). The result of the calculation for the effective multiplication factor and reaction rate states that the greater the percentage of enrichment in uranium-235, the greater the value of the resulting in both parameters. While the distribution of neutron flux produces the most significant value in the middle region or center of the fuel and is seen from the average value produced, and the smallest value is at the edge of the cell. The analysis of this NuScale reactor can later be used as a reference in preparing a safe and efficient reactor core.
The Characteristic Analysis of Caffeine Molecularly Imprinted Polymers Synthesized Using The Cooling-Heating Method, for Application as a Sensor Material Idha Royani; Amalia Amalia; Jorena Jorena; Fitri Suryani Arsyad; Erry Koriyanti; Fiber Monado
Science and Technology Indonesia Vol. 6 No. 4 (2021): October
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2021.6.4.256-260

Abstract

The cooling-heating method was used to successfully synthesize molecularly imprinted polymers on caffeine. Caffeine was used as a template and mixed with chloroform solvent, methacrylic acid as a monomer, ethylene glycol dimethacrylate as a cross-linker, and benzoyl peroxide as an initiator. The solution was stirred for 15 minutes and placed in a vial. Then it was placed in a cooler with a temperature of -5○C for 60 minutes and then inserted into an oven with an increasing temperature at 75○C, 80○C, and 85○C for 3, 2 and 1 hour, respectively. Furthermore, the repeated washing process resulted in solid polymer, which was subjected to template leaching to produce polymers with specific cavities called molecularly imprinted polymers (MIP). The resulting caffeine polymer and MIP were tested using SEM, FTIR, and XRD methods. In addition, the SEM image analysis data showed 388 cavities in the polymer after template leaching, compared to the 121 cavities in the unwashed polymer. This result was supported by the FTIR spectrum analysis which showed that caffeine MIP has a higher transmittance value than the polymer. Therefore, the caffeine concentration was significantly reduced after the leaching process. The XRD spectra showed that caffeine MIP had a smaller halfmaximum diffraction peak width (FWHM) compared to the polymer. Also, the low FWHM value depicted a larger crystalline size in the caffeine MIP compared to the polymer.
Analisis Neutronik Gas Cooled Fast Reactor Berpendingin S-CO2 dengan Bahan Bakar Thorium Nitride Erwin Alparis; Menik Ariani; Fiber Monado; Akmal Johan
Jurnal Penelitian Sains Vol 25, No 2 (2023)
Publisher : Faculty of Mathtmatics and Natural Sciences

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.56064/jps.v25i2.839

Abstract

Analisis neutronik Gas Coleed Fast Reactor dilakukan dengan menggunakan simulasi program SRAC. Reaktor ini menggunakan bahan bakar utama Thorium-232 yang diperkaya dengan Uranium-233 agar reaktor dapat beroperasi, serta berpendingin karbondioksida superkritis S-CO2. Strategi pembakaran bahan bakar menggunakan prinsip modified CANDLE. Susunan bahan bakar pada metode modified CANDLE dibagi menjadi 10 wilayah bahan bakar dan 10 tahun siklus pembakaran. Setelah 10 tahun proses burn-up bahan bakar di wilayah pertama dipindahkan ke wilayah kedua, bahan bakar di wilayah kedua dipindahkan ke wilayah ketiga, bahan bakar di wilayah ketiga dipindahkan ke wilayah keempat, dan seterusnya. Bahan bakar di wilayah 10 kemudian dikeluarkan. Wilayah pertama diisi dengan bahan bakar baru uranium alam. Proses tersebut diulangi sampai tercapai kondisi keseimbangan. Dari hasil simulasi perhitungan pada desain teras diperoleh nilai faktor multiplikasi  (keff) serta level burn up yang paling optimal.
Studi Awal Pengaruh Kloroform Sebagai Pelarut Pada Proses Ekstraksi Molecularly Imprinted Polymer (MIP) Nano Kafein Maimuna, Maimuna; monado, fiber; Royani, Idha
Jurnal Fisika Vol 10, No 1 (2020)
Publisher : Universitas Negeri Semarang

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.15294/jf.v10i1.23806

Abstract

Proses ekstraksi sangat penting dalam sintesis Molecularly Imprinted Polymer (MIP). Proses tersebut sangat menentukan jumlah kafein yang terbuang. Keberhasilan proses ini tidak hanya bergantung pada proses sintesis namun juga tergantung pada ukuran partikel templat dan pelarut yang digunakan saat proses tersebut. Sintesis polimer nano kafein telah berhasil dibuat menggunakan metode cooling-heating melibatkan MAA sebagai monomer fungsional, EDMA sebagai ikatan silang, BPO sebagai inisiator, dan kloroform sebagai pelarut. NIP juga dibuat sebagai polimer pembanding tanpa nano kafein. Serbuk nano polimer yang dihasilkan selanjutnya diekstraksi menggunakan kloroform, metanol/asam asetat (1:20), dan metanol. Terakhir polimer dicuci menggunakan metanol/aquabidest (1:20). Hasil FTIR menunjukkan adanya gugus fungsi amina yang merupakan gugus fungsi khas kafein. Nilai persentase transmitansi pada MIP nano kafein lebih besar dibandingkan polimer nano kafein. Hal ini menunjukkan bahwa proses ekstraksi templat nano kafein menggunakan larutan kloroform berhasil dilakukan. Hasil XRD menunjukkan MIP memiliki ukuran kristal yang lebih besar dibandingkan NIP. Ukuran kristal yang besar terlihat dari tingginya puncak intensitas yang dihasilkan.
Synthesis of Ion Imprinted Polymers (IIPs) Adsorbent Materials Using Fe(III) Leaching Process with Variation of Hydrochloric Acid Solvent Concentration and Heat Treatment Royani, Idha; Maimunah; Edianta, Jaya; Alfikro, Ihsan; Fiber Monado; Jorena; Satya, Octavianus Cakra; Virgo, Frinsyah
Science and Technology Indonesia Vol. 9 No. 2 (2024): April
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2024.9.2.336-344

Abstract

Fe(III)-IIPs material was prepared using a cooling-heating method with different leaching variations. The synthesis process used several chemical components, including EGDMA, MAA, and BPO as the crosslinker, functional monomer, and initiator. This study focused on the template formation process of IIPs with leaching variations, using parameters such as molarity concentration, solution mixture, and temperature to influence the amount of template formed in the polymer body. The spectra of XRD showed a widening value of FWHM as higher molarity was applied during the leaching process, with the widest one at 0.163 rad for IIPs 3 M. Fe(III) peak is located at 680-610 cm−1 or 1386-1350 cm−1 within the unleached sample, according to FTIR spectra. It also can be traced at minimum intensity in leached samples. SEM data processing showed that higher concentrations were essential in releasing Fe(III) ions from the polymer body. Meanwhile, heat treatment did not strongly impact the template formation sites of IIPs. Synthesized Fe(III)-IIPs materials had adsorption capacity, optimum time, and efficiency of 9.35 mg.g−1, 40 minutes, and 93.48%, respectively. Based on the results, Fe(III)-IIPs materials had great potential as adsorbents for removing metal pollutants from water.
The Effect of Burnable Poison Np-237 on the Conceptual Design of the GFR-2400 MWt Using MCANDLE Burnup Strategy Monado, Fiber; Berliani, Berliani; Supardi, Supardi; Royani, Idha; Ariani, Menik; Kaban, Hadir; Su'ud, Zaki
POSITRON Vol 14, No 1 (2024): Vol. 14 No. 1 Edition
Publisher : Fakultas Matematika dan Ilmu Pengetahuan Alam, Univetsitas Tanjungpura

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26418/positron.v14i1.65433

Abstract

This study was used to design the Gas-cooled Fast Reactor (GFR) with 2400 MWt power as well as to implement a modified CANDLE (MCANDLE) burning strategy. Metallic uranium with Neptunium-237 at a concentration of 1% to 10% was used as burnable poison in the fuel while helium was applied as a coolant. Neptunium has been produced in conventional reactors by the decay product of plutonium obtained from U-238. This isotope has a relatively high absorption cross-section. As a nuclear waste, it is very useful to utilize as a burnable poison to reduce waste in the future and extend reactor operation lifetime with negligible reactivity. Moreover, the reactor was designed to operate for 100 years of burnup. Nuclear Fuel cell level calculations were conducted using the PIJ module and the reactor core was analyzed using the CITATION module contained in the SRAC. The core height was found to be 420 cm while the diameter was 300 cm and it was designed to have a refueling period of ten years. The survey parameters evaluated include burnup level, factor multiplication, conversion ratio, atomic density, and power distribution. The calculation conducted at the fuel cell level showed that the maximum value in the 76th year for the infinite multiplication factor was 1.30097. It was also discovered that the reactor core for the effective multiplication factor parameter with a fuel fraction of 55% was 1.094 without the addition of burnable poison.
Desain Konseptual Teras Reaktor Cepat Berumur Panjang Berpendingin S-CO2 dengan Bahan Bakar Uranium Metalik Alam Rahma Darmawati; Menik Ariani; Fiber Monado
Jurnal Fisika Unand Vol 9 No 3 (2020)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.9.3.401-407.2020

Abstract

Telah dibuat sebuah desain konsep teras reaktor cepat berpendingin S-CO2 dengan bahan bakar uranium metalik alam yang dapat beroperasi dalam waktu yang lama (berumur panjang). Metode penyusunan bahan bakar dilakukan menggunakan strategi burn-up modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production). Strategi pembakaran CANDLE yang dimodifikasi dengan region pertama berada di dekat region terakhir telah diterapkan. Perhitungan teras reaktor dilakukan menggunakan modul CITATION pada sistem kode SRAC (Standard Reactor Analysis Code). Tahap awal penelitian dengan menghitung sel bahan bakar menggunakan modul PIJ sebagai input siklus telah dilakukan. Parameter perhitungan yang diamati adalah nilai faktor multiplikasi efektif (k-eff), distribusi daya arah aksial dan radial serta reaktivitas pada teras reaktor. Hasil perhitungan menunjukkan nilai k-eff dari awal siklus pembakaran sekitar 1,0490 hingga akhir siklus sebesar 1,0598. Distribusi daya arah aksial paling besar terjadi pada ketinggian teras 115 cm yaitu sebesar 1,9824 watt/cc. Sedangkan untuk distribusi daya arah radial paling besar terjadi di tengah teras yaitu sebesar 2,1697 watt/cc. Nilai  reaktivitas rata-rata selama waktu operasi sebesar 0,0562. Berdasarkan hasil tersebut, keadaan teras reaktor memenuhi syarat untuk beroperasi. The conceptual design of a fast reactor core has been made with S-CO2 as a coolant and natural metallic uranium as a fuel, which can operate for a long time (long-life reactor). The fuel preparation method uses a strategy of burn-up modified CANDLE (Constant Axial shape of Neutron flux, nuclide density, and power shape During Life of  Energy production). The modified CANDLE burning strategy with the first region near the last region has been implemented. The reactor core calculation is performed using the CITATION module on the SRAC (Standard Reactor Analysis Code) code system. The initial phase of research by counting fuel cells using the PIJ module as a cycle input has been carried out. The calculation parameters observed were effective multiplication factor (k-eff), axial and radial power distribution, and reactivity on the reactor core. The calculation results show the k-eff value from the burning of life (BOL) cycle around 1.0490 until the end of the cycle of 1.0598. The largest axial power distribution occurs at the reactor core height of 115 cm,  equal to 1.9824 watts/cc, whereas the largest radial power distribution occurs in the center of the core, which is equal to 2.1697 watts/cc. The average reactivity value during the operation time of around 0.0562. Based on these results, the reactor core condition qualifies for operation.
Efek Penambahan Plutonium pada Sel Bahan Bakar MOX terhadap Performa Reaktor GFR 250MWth Muhammad Aldi Kurniawan; Menik Ariani; Monado, Fiber; Johan, Akmal; Kaban, Hadir
Jurnal Fisika Unand Vol 14 No 2 (2025)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.14.2.152-159.2025

Abstract

A fast-type reactor that operates on high-speed neutrons, GFR (Gas-cooled Fast Reactor) can produce various fissile materials and fertilizers. This production capability is very beneficial for the stability of nuclear fuel in the reactor core, especially reactors that use closed cycles such as GFR. Plutonium (Pu) from the residue from burning reactors such as PWR or LWR can be used as a mixed fuel to increase fissile nuclides in MOX fuel. MOX (Mixed Oxide) is a mixture of uranium (U) and plutonium (Pu) in certain amounts. The composition of plutonium (Pu) in MOX greatly influences the level of fuel combustion in the core at the start of operation. The research aims to vary the percentage of plutonium (Pu) to enable design adjustments to maximize fuel use efficiency. Simulations were conducted computationally to determine the performance of each percentage of Pu used in MOX. Depletion calculations were carried out for 10 years using the OpenMC code and ENDF/B VIII.0 nuclear data. The research results show that the best design performance is at a Pu percentage of 11% which is determined based on the range of effective multiplication factor (keff ) values and excess reactivity and is in line with expectations.
Synthesis and Characterization of Polyvinyl Alcohol (PVA) Nanofiber Membranes with Annonamuricata and Terminalia catappa Leaf Extract Fitria, Silfiyana; Almafie, Muhammad Rama; Alfikro, Ihsan; Monado, Fiber; Sriyanti, Ida; Royani, Idha
Science and Technology Indonesia Vol. 10 No. 3 (2025): July
Publisher : Research Center of Inorganic Materials and Coordination Complexes, FMIPA Universitas Sriwijaya

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26554/sti.2025.10.3.837-846

Abstract

Polyvinyl alcohol (PVA) is hydrophilic, flexible, elastic, and environmentally friendly, leading to the wide use as a binder in nanofiber matrices. The nanofibers of PVA are frequently combined with extract possessing antibacterial properties for characterization. Therefore, this study aimed to produce PVA nanofibers incorporating soursop leaf extract (ALE) and catappa leaf extract (CLE) using electrospinning for the investigation of the physicochemical, mechanical, and antibacterial properties. Electron microscopy showed that the electrospun nanofibers had a yellowish-brown surface with diameters ranging from 962 nm to 1323 nm. Fourier Transform Infrared (FTIR) analysis revealed the presence of functional groups interacting through hydrogen bonding, leading to a shift in wavenumbers. The tensile strength of PAC-1, PAC-2, and PAC-3 nanofibers decreased from 8.46 MPa to 4.27 MPa, followed by a reduction in Young’s modulus from 20.2 MPa to 0.89 MPa. The effect of extract concentration on the reduction in tensile strength and Young’s modulus was related to aggregation in certain areas of the nanofibers and weakened intermolecular polymer interactions. Pure extract had strong antibacterial activity and nanofiber membranes had moderate activity with inhibition zones ranging from 12.3 to 16.8 mm and 8.0 to 14.4 mm, respectively. The results showed that the produced fibers could be used in the biomedical field for wound dressings and filtration, as well as in textiles.
Studi Parameter Burn-up Sel Bahan Bakar Uranium Nitrit Dengan Penambahan Minor Aktinida Berpendingin S-CO2 Gontina, Wulan; Monado, Fiber; Ariani, Menik
Jurnal Penelitian Sains Vol 24, No 3 (2022)
Publisher : Faculty of Mathtmatics and Natural Sciences

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.56064/jps.v24i3.744

Abstract

Abstrak Bahan bakar nuklir adalah komponen utama dalam reaktor yang diperoleh dari isotop alami seperti Uranium. Dengan penambahan unsur-unsur minor aktinida  pada bahan bakar dapat dilihat performa sel bahan bakar selama burn-up nya. Studi parameter pada penelitian ini diperoleh dari perhitungan tingkat sel bahan bakar uranium nitrit pada perbandingan 95% uranium nitrit dan 5% penambahan minor aktinida berupa nuklida Am241 dan Np237 dengan komposisi 1% hingga 7% dengan pendingin  S-CO2.  Persentase fraksi volume tingkat sel adalah 65% fuel, 10% cladding (stainless steel) dan 25% coolant. Hasil  perhitungan terhadap parameter survey tingkat sel bahan bakar diperoleh dari nilai K-inf sepanjang sejarah burn-up selama 120 tahun,  level burn-up sepanjang sejarah burn-up selama 120 tahun, densitas atom terkait U235,U238 dan Pu239,konversi rasio sepanjang sejarah burn-up selama 120 tahun. Hasil perhitungan parameter neutronik tingkat sel memperlihatkan dampak dari penambahan minor aktinida terhadap bahan bakar uranium nitrit untuk performa sel bahan bakar selama burn-up nya. Kata kunci : sel bahan bakar, uranium nitrit, minor aktinida, S-CO2 Abstract Nuclear fuel is the main component in the reactor which is obtained from natural isotopes such as Uranium. By adding actinide minor elements to the fuel, it can be seen how the performance of the fuel cell during its burn-up can be seen. Parameter studies in this study were obtained from the calculation of the level of uranium nitrite fuel cells at a ratio of 95% uranium nitrite and 5% the addition of minor actinides with Am241 and Np237 nuclides with a composition of 1% to 7% with S-CO2 coolant. The percentage of cell level volume fraction is 65% fuel, 10% cladding (stainless steel) and 25% coolant. Calculation results for the fuel cell level survey parameters are obtained from the K-inf value over the 120 year burn-up history, the burn-up level over the 120 year burn-up history, the atomic density associated with U235, U238 and Pu239, the conversion ratio over the 120 year burn-up history . The results of the calculation of the cell-level neutronic parameters show the impact of the minor addition of actinide to uranium nitrite fuel on the performance of the fuel cell during its burn-up. Keywords: fuel cell, uranium nitrite, actinide minor, S-CO2 
Co-Authors Akmal Johan Alfikro, Ihsan Almafie, Muhammad Rama Amalia Amalia Ananda, Dwi QIsah Sally Apriansyah, Muhammad Rendy Assaidah, Assaidah Balya Lutviana Laila Saro Balya Lutviana Laila Saro Berliani, Berliani Canti Dwi Putri Damri Damri Edianta, Jaya Enda Susanty Erni Erni Erry Koriyanti Erry Koriyanti Erwin Alparis Fitri Suryani Arsyad Fitria, Silfiyana Frinsyah Virgo Gontina, Wulan Hadi Hadi Hadir Kaban Hadir Kaban, Hadir Hesti Dwi Kartika Ida Sriyanti Idha Royani Idha Royani Islami, Rifqi Jorena Jorena Jorena Jorena Jorena, Jorena Maimuna Maimuna, Maimuna Maimunah Menik Ariani Muhammad - Subekti Muhammad Aldi Kurniawan Norman, Muhamad Tauffan Hidayatullah Octavianus Cakra S. Octavianus Cakra Satya Rahma Darmawati Ramadhani, Athiyyah Ridha Mayanti Simanullang, Trivanti Su'ud, Zaki Su’ud, Zaki Supardi Supardi Syakuroh, Abdan Yulinar Adnan Zaki Su'ud Zaki Su’ud