Comparative Study on Various Thermal Power for Gas Cooled Fast Reactor with Uranium Plutonium Nitride Fuel

Abstract

Comparative study on various thermal powers for gas cooled fast reactor with uranium plutonium nitride fuel has been done. The purpose of this study was to compare various thermal powers on nuclear power plant (NPP) Gas Cooled Reactor type. Neutronics calculation was design by using SRAC Code version 2006 (Standard Reactor Analysis Code) with the data nuclides from JENDL-4.0 under the Linux Operating System with nuclear data library JENDL4.0. Neutronic calculations were done through some parameter surveys to obtain the optimal results. The first step was calculation of fuel cell (PIJ-method) by using hexagonal cell and then followed by calculation of core reactor (CITATION-method). The power variations carried out are seven variations of power, namely from 100 MWth to 700 MWth. In this power variation all parameters are made the same. The parameters that are made are the same, namely the percentage of plutonium, the volume fraction of the fuel, the reactor geometry type, the diameter and the active core height (terrace). All power variations have an average power density value and maximum power density increases along with the increase in thermal power. When thermal power increases, the k-eff peak value will be increase too. It shows that if the thermal power increases, the burn-up fuel is also increase more than before, so that the fuel is used for the burn-up process which causes k-eff increase. The increasing graph which shows in the figure explains that the reactor breeding occurs, while the declining graph shows the reactor is burning.