DESIGN AND ANALYSIS OF VODO-VODYANOI ENYERGETICHESKIY REAKTOR-1000 (VVER-1000) WITH MONTE CARLO N-PARTICLE (MCNP)
Kevin Wijaya(a*), Dwi Irwanto(a,b), and Sidik Permana(a,b)

a) Nuclear Physics and Biophysics Research Division, Physics Department, Faculty of Mathematics and Natural Science, Bandung Institute of Technology, Jalan Ganesha 10 Bandung 40132, Indonesia.
*kevinwijaya3001[at]gmail.com
b) Nuclear Science and Engineering Department, Faculty of Mathematics and Natural Science, Bandung Institute of Technology, Jalan Ganesha 10 Bandung 40132, Indonesia.

Abstract

Currently, electrical energy is still one of the sources of human needs in everyday life. With the depletion of fossil energy, nuclear power plants can become one of the suppliers of electricity that can be used. In Indonesia, there is still no nuclear reactor for nuclear power plants, only for research purposes.
One type of nuclear reactor is the Vodo-Vodyanoi Enyergeticheskiy Reaktor-1000 (VVER-1000).VVER-1000 is a generation III fission reactor with a thermal power of 3000 MWth. In this final project, we will discuss the design and analysis of the VVER-1000 using a program based on Monte Carlo N-Particle (MCNP) which is a license code from the Los Alamos National Laboratory (LANL). The purpose of this study was to determine the fuel assembly model, determine the multiplication factor, and determine the multiplication factor as a function of burnup and burnup rate with variations of uranium enrichment and gadolinium variations using MCNP. Broadly speaking, this research is divided into three stages, namely the literature study stage, the MCNP simulation and modeling stage, and the processing and analysis stage. Based on the experiments carried out, obtained a model of the fuel assembly along with the fuel cell, guide tube cell, and central tube cell. Then, it was obtained information that variations in uranium and gadolinium enrichment affect the value of the multiplication factor which affects the amount of neutron production. Then the results of the multiplication are obtained which changes the value of each factor and the variations used do not affect the burnup rate value.

Keywords: Burnup, fuel assembly, MCNP, multiplication factor, VVER-1000

Topic: Innovative Nuclear Energy Systems