Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code

Abstract

The fuel volume fraction analysis has been carried out with uranium carbide in GasCooled Fast Reactor using the SRAC Code (Standard Reactor Analysis Code). This code was developed by the Japan Atomic Energy Agency (JAEA) and uses the latest nuclear data library JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. The optimum design based on the analysis that has been carried out is the fuel volume fraction of 49% with a heterogeneous core configuration of 3 types of fuel percentages, for Fuel type 1 = 9%, Fuel type 2 = 12% and Fuel type 3 = 15% with the reactor is cylindrical and has a core diameter of 240 cm and a core height of 100 cm