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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 Jurnal Teori dan Aplikasi Fisika 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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Journal : Jurnal Fisika Unand

 1 
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 | Full PDF (922.881 KB) | 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.
Desain Konseptual Teras Reaktor Cepat Berumur Panjang Berpendingin S-CO2 dengan Bahan Bakar Uranium Metalik Alam Darmawati, Rahma; Ariani, Menik; Monado, Fiber
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.
Analisis Desain Teras Gas-Cooled Fast Reactor (GFR) Berpendingin S-CO2 Berbahan Bakar Uranium Nitrit dengan Minor Aktinida Gontina, Wulan; Monado, Fiber; Ariani, Menik
Jurnal Fisika Unand Vol 13 No 1 (2024)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.13.1.103-109.2024

Abstract

Telah dilakukan analisis desain teras Gas cooled Fast Reactor (GFR) berpendingin  S-CO2 berbahan bakar Uranium Nitrit dengan Minor Aktinida sehingga dapat beroperasi dalam waktu lama. Sistem suhu tinggi, keandalan spektrum cepat dan siklus bahan bakar tertutup GFR dapat meminimalkan limbah reaktor dengan penggunaan Uranium berkelanjutan dari minor aktinida. Karakteristik S-CO2 yang stabil, tidak mudah terbakar dan suhu puncak realtif rendah (~650oC) mampu mendinginkan teras reaktor.  Metode penyusunan bahan bakar menggunakan strategi burn-up Modified CANDLE. Strategi pembakaran MCANDLE dalam shuffling arah radial dengan dua skema pengisian bahan bakar, skema X (dari luar teras ke arah dalam) dan skema Y (dari pusat teras ke luar), telah diterapkan. Digunakan SRAC dan data JENDL-4.0 dalam perhitungan. Pada penelitian ini diperoleh studi parameter melalui perhitungan nilai faktor multiplikasi infinite, faktor multiplikasi efektif, reaktivitas dan distribusi daya. Hasil perhitungan menunjukkan nilai Keff sebelum penambahan Minor Aktinida untuk skema X dan Y adalah 1,0893 dan 1,0915. Setelah penambahan minor aktinida nilai Keff 1% - 7% pada skema X dan Y berada pada kondisi kritis dan setelah penambahan minor aktinida 4% - 7% reaktor berada pada kondisi superkritis. Reaktivitas reaktor pada skema X dan Y adalah 0,0939 dan 0,1089. Untuk distribusi daya arah aksial skema X dan Y 1,5285 dan 1,5323. Untuk distribusi daya arah radial pada skema X dan Y adalah 1,5862 dan 1,8320. Berdasarkan hasil tersebut penambahan minor aktinida dan skema penyusunan bahan bakar mempengaruhi kekritisan dan distribusi daya  teras GFR. 
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 Choirunnisa, Nurlaila Septi Damri Damri Darmawati, Rahma 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 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 Via Vionita Yulinar Adnan Zaki Su'ud Zaki Su’ud