Desain Konseptual Teras Reaktor Cepat Berumur Panjang Berpendingin S-CO2 dengan Bahan Bakar Uranium Metalik Alam
DOI:
https://doi.org/10.25077/jfu.9.3.401-407.2020Abstract
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.
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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.
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