EFFECT OF FUEL ASSEMBLY COMPOTITION ON NEUTRON MULTIPLICATION FACTOR VALUE IN NUSCALE REACTOR USING MONTE CARLO NPARTICLE CODE (MCNP)

• Main Author: David P. Tambunan, Sandi
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/67520
• Institution: Institut Teknologi Bandung

Nuclear Power Plant (NPP) is a thermal power plant that uses one or more nuclear reactors as its heat source. One type of nuclear reactor is the Small Modular Reactor (SMR). NuScale was developed using the PWR (Pressurized Water Reactor) type without a primary pump so that the reactor heat transfer from the core uses natural circulation. Due to its simpler design, probabilistic analysis for worse accident cases based on intrinsic design such as primary pump failure has been omitted. In this final project, we will discuss the neutronic aspect of the effect of fuel assembly composition on the value of the neutron multiplication factor in the NuScale reactor using the Monte Carlo N-Particle (MCNP) code. The purpose of this final project is to determine the effect of the fuel assembly composition on the value of the neutron multiplication factor in the NuScale reactor, analyze the neutronic characteristics of the NuScale reactor fuel assembly, and analyze the results of the simulation calculation of the NuScale fuel assembly burn-up scheme using MCNP. In this study, several variations were carried out including uranium enrichment variation, %Gd variation, and volume variation. This research is broadly divided into three stages, namely: the literature study stage, the MCNP modeling stage, and the data processing and analysis stage and drawing conclusions. Based on the research that has been done, the NuScale reactor fuel assembly design has been successfully made using the MCNP code. As well as the analysis of neutronic characteristics and calculation results of the simulation of the burn-up fuel assembly NuScale scheme using MCNP were obtained.