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Jwaher Alnaqbi,Donny Hartanto,Reem Alnuaimi,Muhammad Imron,Victor Gillette 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.2
The United Arab Emirates is currently building and operating four units of the APR-1400 developed by aSouth Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR1400 reactor core analysis by using the well-known two-step method. The two-step method wasapplied to the APR-1400 first cycle using the open-source nodal diffusion code, KOMODO. In this study,the group constants were generated using CASMO-4 fuel transport lattice code. The simulation wasperformed in Hot Zero Power (HZP) at steady-state and transient conditions. Some typical parametersnecessary for the Nuclear Design Report (NDR) were evaluated in this paper, such as effective neutronmultiplication factor, control rod worth, and critical boron concentration for steady-state analysis. Otherparameters such as reactivity insertion, power, and fuel temperature changes during the ReactivityInsertion Accident (RIA) simulation were evaluated as well. The results from KOMODO were verifiedusing PARCS and SIMULATE-3 nodal core simulators. It was found that KOMODO gives an excellentagreement