Text
DESAIN NEUTRONIK TERAS REAKTOR CEPAT BERPENDINGIN S-CO2 BERBASIS BAHAN BAKAR URANIUM METAL BERDAYA 500 MWt DENGAN STRATEGI BURN-UP MODIFIED CANDLE
This research discusses the neutronic design of a fast reactor core of the GFR type with a thermal power of 500 Mwt based on metallic uranium (U-10% wtZr) fuel with a coolant in the form of S-CO2, and by applying the strategy burnup Modified CANDLE in the preparation of fuel during combustion. Neutronic calculations for fuel cells and reactor cores were carried out using the PIJ and CITATION modules in the SRAC program package with the JENDL 4.0 library. Determination of design criteria is done by optimizing the size of the reactor core to get a convergent value of the effective multiplication factor (keff). A convergent size was obtained at the radial of the active core is 116 cm and the height of the active core is 200 cm, with a ratio of the pin pitch volume fraction used of 60% fuel, 10% cladding 30% coolant and pin pitch diameter of 1.4 cm. This is indicated by the value of the effective multiplication factor (keff) reaching a critical value (keff ≥ 1) excess reactivity ≤ 10%. This design can operate for 100 years with a refueling period every 10 years. Furthermore, the analysis of the addition of minor actinides in the form of Am-241, after the addition of Am-241 to the fuel the keff value remained significantly increased and for the keff value with the addition of 1% Am-241 the value was lower than the keff value before the addition of Am-241. Meanwhile, the addition of Am-241 by 2% to 7% showed a higher keff value than the keff value before the addition of Am-241. This minor addition of actinides aims to utilize nuclear waste.
Inventory Code | Barcode | Call Number | Location | Status |
---|---|---|---|---|
2207003968 | T78442 | T784422022 | Central Library (Referens) | Available but not for loan - Not for Loan |
No other version available