Skripsi
ANALISIS TERAS REAKTOR CANDLE GAS-COOLED FAST REACTOR (GFR) BERBAHAN BAKAR URANIUM NITRIDE MENGGUNAKAN OPENMC
The increasing emission of carbon dioxide has driven the need for the development of low-emission energy sources, one of which is Generation IV nuclear reactors. The Gas-Cooled Fast Reactor (GFR) is a fast reactor concept that offers high efficiency and improved potential for radioactive waste management. This study analyzes the core performance of a GFR based on the CANDLE burn-up concept using Uranium Nitride (UN) fuel with varying additions of Plutonium (Pu). The simulations were conducted using the Monte Carlo method with the OpenMC code for an operation period of up to 80 years. The analyzed parameters include the effective multiplication factor (k_{eff}), neutron flux distribution, fission reaction rate, isotopic densities of Xe135 and Am241, and changes in heavy metal (HM) mass. The results indicate that variations in fuel composition significantly affect the reactivity characteristics of the reactor core. The UN + 10% Pu fuel variation exhibits the highest initial k_{eff} value of 1.15559, while the UN + 9% Pu variation, with an initial k_{eff} of 1.1114, is able to maintain a k_{eff} value close to unity up to approximately the 14th year of operation (k_{eff} = 1.00478). This behavior demonstrates good reactivity stability without excessively high initial reactivity. These findings suggest that the application of the CANDLE concept in a GFR using UN fuel has strong potential to support long-term reactor operation with stable reactivity.
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