Analysis of Enhance Reliability Gas-Cooled Fast Reactor (GFR) Based on Fuel Uranium Nitride (UN)

Energy demand will continue to increasing number of human populations and needs in the industrial world. PLTN ( Nuclear Power Plant) is one alternative energy source that utilizes nuclear fission reactions to produce energy and in its operation does not produce air pollution. This study presents an analysis of the reliability design of a Uranium-Nitride (UN) based GFR reactor, with a cladding of stainless steel (SS316) and helium-cooled. The calculation is done using a set of Standard Reactor Analysis Code (SRAC) programs. The results of the calculation design of the fast reactor core based on Uranium Nitride with 9.5% enrichment Uranium 235, using 60% fuel volume fraction, 10% cladding and 30% coolant showed critical values> 1 (1,008-1,051) with excess reactivity 0.031% then the reactor can operate for 10 years without refueling.