Analisis Neutronik dan Temperatur Bahan Bakar Setelah Depressurized Loss of Forced Cooled (DLOFC) pada Pebble Bed Reactor (PBR) dengan Upgrade Daya
DOI:
https://doi.org/10.25077/jfu.9.2.231-237.2020Abstract
Pada penelitian ini dilakukan analisis neutronik dan temperatur bahan bakar setelah DLOFC pada Pebble Bed Reactor (PBR) dengan upgrade daya. Reaktor acuan yang digunakan dalam penelitian ini yaitu HTR-PM. Penelitian ini bertujuan untuk memperoleh desain reaktor dengan daya 300 MWt. Perhitungan dalam penelitian ini menggunakan software PEBBED6 code. Pada tahap awal dilakukan upgrade daya pada desain default HTR-PM. Parameter neutronik yang diperhatikan dalam penelitian ini yaitu nilai burnup yang tinggi dan temperatur puncak bahan bakar setelah DLOFC tidak melebihi 1620 oC. Berdasarkan capaian kedua parameter tersebut, daya pada desain default HTR-PM hanya dapat ditingkatkan hingga 260 MWt. Selanjutnya perhitungan pada daya yang di-upgrade disertai dengan pengaturan pada enrichment dan HM loading. Dari hasil pengamatan disimpulkan bahwa dengan enrichment dan HM loading yang tinggi maka semakin tinggi densitas bahan fisil sehingga dapat memperbesar nilai burnup dan juga temperatur puncak setelah DLOFC. Selanjutnya dilakukan optimasi ketinggian dan diameter teras reaktor dengan volume teras default (77,44 m3). Diameter teras yang diperkecil dapat menghantarkan panas hasil reaksi fisi keluar teras lebih maksimal. Kemudian dilakukan pengaturan enrichment dan HM loading bahan bakar kembali untuk mendapatkan daya maksimal. Desain optimal pada penelitian ini diperoleh untuk daya 300 MWt dengan HM loading 6 gU/pebble, enrichment 8,5% dan tinggi teras 14,64 m yang dapat menghasilkan nilai burnup 77,11 MWd/Kg.HM.
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In this research neutron and fuel temperature analysis is done after DLOFC on the Pebble Bed Reactor (PBR) with a power upgrade. The reference reactor used in this study is HTR-PM. This study aims to obtain a reactor design with 300 MWt of power. The calculation in this study use the PEBBED6 code software. In the initial stage, a power upgrade is performed on the default HTR-PM design. The neutronic parameters considered in this study are high burnup values and peak temperature after DLOFC do not exceeding 1620 oC. Based on the achievement of the two parameters, the power in the default HTR-PM design can only be increased up to 260 MWt. Furthermore, calculation on the upgraded power are accompanied by setting on the enrichment and HM loading. The next step is optimizing the height and diameter of the reactor core by maintaining the default core volume (77.44 m3). The reduced diameter of the terrace can deliver maximum heat from the fission reaction outside the terrace. Then the enrichment and HM loading of the fuel are regulated to get maximum power. The optimal design in this study was obtained for 300 MWt power with HM loading of 6 gU/pebble, 8.5% enrichment and a terrace height of 14.64 m which can produce a burnup value of 77.11 MWd/Kg.HM.
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