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ANALISIS NEUTRONIK BAHAN BAKAR MIXED OXIDE ((U-Pu)O2) PADA DESAIN TERAS GAS COOLED FAST REACTOR (GFR) MENGGUNAKAN OPENMC
This research discusses the use of MOX fuel in the Gas-cooled Fast Reactor (GFR) core using OpenMC code. GFR is one of GEN-IV reactors that operate at high temperatures and fast neutrons. MOX is a nuclear fuel consisting of uranium (U≤96%) and plutonium (Pu≥4%) where plutonium can be obtained from combustion products from thermal reactors such as PWR. The plutonium material in MOX used in this study was 11% and natural uranium as a blanket material to extend the operating life. OpenMC is an open-source Monte Carlo particle, which uses the Evaluated Nuclear Data File (ENDF/B VIII.0) as the nuclear data library. The physical parameters that became the result of this study included the value of the effective multiplication factor, which was able to reach a critical condition until the tenth year with the highest point in the fifth year, namely 1,02743, and the core was successful in achieving breeding conditions with a conversion ratio value of more than one (CR>1) until the tenth year. Changes in the composition of the material from fertile to fissile, in this case, U238, which transmuted to Pu239, continued until the tenth year, which resulted in a long operating life. Other parameter surveys that have been successfully obtained are flux distribution and fission reaction rate distribution. In addition, the calculation of the reactor kinetic parameters, namely the Dopper reactivity coefficient and the coolant void reactivity value, each gave good results.
Inventory Code | Barcode | Call Number | Location | Status |
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2207003228 | T75962 | T759622022 | Central Library (Referens) | Available but not for loan - Not for Loan |
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