摘要：This study presents the calculation results of the cell, and core Gas-cooled Fast Reactor (GFR) based fuel UraniumPlutonium Nitride (U, Pu)N. Parameter survey results of calculations of the fuel cell consisting of a kinf, burnup level, and the conversion ratio and for the calculation of the reactor core produce value keff during a refueling cycle. The calculation was performed by using a set of SRAC program by comparing three types of fuel cell designs. Reactor Design A based on natural uranium could not reach criticality because of keff < 1. Design B used the enrichment of uranium-235 by 9.5% to reach a critical condition at keff > 1. The critical state was also achieved by Design C utilizing natural uranium, and plutonium 5.5% result value keff = 1.015 in the first year of burnup and continues to increase 1.083 in the tenth year without refueling. Moreover, plutonium can replace the uranium enrichment process.
其他摘要：Penelitian ini menyajikan hasil perhitungan sel dan teras gas-cooled fast reactor (GFR) berbasis bahan bakar UraniumPlutonium Nitride (U,Pu)N. Parameter Survey untuk hasil perhitungan sel bahan bakar terdiri dari kinf, level burnup, dan conversion ratio.
